This table contains the priority designations for all issues listed in this report. The Status/Safety Priority Ranking column notes those issues covered in other issues described in this document. For example, a notation of I.A.2.2 in the Status/Safety Priority Ranking column for item I.A.2.6(3) means that item I.A.2.6(3) is covered in item I.A.2.2. For resolved issues that resulted in new requirements for operating plants, the appropriate multiplant licensing action number is given in the MPA No. column. (The multiplant licensing action numbering system is not related to the numbering systems used to identify the prioritized issues.) This table is maintained primarily for historical purposes.
LEGEND
ACTIVE Generic issue that involves actions under the GI Program DROP Issue dropped from further pursuit as a generic issue
EI Environmental issue
I Resolved TMI Action Plan item with implementation of resolution mandated by NUREG 0737 L Licensing issue
MEDIUM Medium safety priority MPA Multiplant action
NA Not applicable
NOTE 3(a) Resolution resulted in regulatory products (rule, Standard Review Plan change, or equivalent) NOTE 3(b) Resolution did not result in a regulatory product
NOTE 5 Issue that is not a generic safety issue but should be assigned resources for completion. As clarified by SECY-11-0101, Summary of Activities Related to Generic Issues Program, dated July 26, 2011, Generic Issues Program will not pursue any further actions toward resolution of Licensing and Regulatory impact issues.
R Regulatory impact issue
LEGEND (Continued)
ROI Regulatory office implementation: A formal GI for which RES actions of safety/risk assessment or regulatory assessment are complete and remaining actions reside with program offices (e.g., regulatory compliance, reactor oversight process, rulemaking, further research, coordination with industry initiatives)
USI Unresolved safety issue
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.A | OPERATING PERSONNEL | ||||||
| I.A.1 | Operating Personnel and Staffing | ||||||
| I.A.1.1 | Shift Technical Advisor | - | NRR/DHFS/ LQB | I | 3 | 12/31/97 | F 01 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.A.1.2 | Shift Supervisor Administrative Duties | - | NRR/DHFS/ LQB | I | 3 | 12/31/97 | |
| I.A.1.3 | Shift Manning | - | NRR/DHFS/ LQB | I | 3 | 12/31/97 | F 02 |
| I.A.1.4 | Long-Term Upgrading | R. Colmar | RES/DFO/ HFBR | NOTE 3(a) | 3 | 12/31/97 | |
| I.A.2 | Training and Qualifications of Operating Personnel | ||||||
| I.A.2.1 | Immediate Upgrading of Operator and Senior Operator Training and Qualifications | ||||||
| I.A.2.1(1) | Qualifications Experience | - | NRR/DHFS/ LQB | I | 6 | 12/31/97 | F 03 |
| I.A.2.1(2) | Training | - | NRR/DHFS/ LQB | I | 6 | 12/31/97 | F 03 |
| I.A.2.1(3) | Facility Certification of Competence and Fitness of Applicants for Operator and Senior Operator Licenses | - | NRR/DHFS/ LQB | I | 6 | 12/31/97 | F 03 |
| I.A.2.2 | Training and Qualifications of Operations Personnel | R. Colmar | NRR/DHFS/ LQB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.2.3 | Administration of Training Programs | - | NRR/DHFS/ LQB | I | 6 | 12/31/97 | |
| I.A.2.4 | NRR Participation in Inspector Training | R. Colmar | NRR/DHFS/ LQB | LI (NOTE 3) | 6 | 12/31/97 | NA |
| I.A.2.5 | Plant Drills | R. Colmar | NRR/DHFS/ LQB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.2.6 | Long-Term Upgrading of Training and Qualifications | - | - | - | |||
| I.A.2.6(1) | Revise Regulatory Guide 1.8 | R. Colmar | NRR/DHFT/ HFIB | NOTE 3(a) | 6 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.A.2.6(2) | Staff Review of NRR 80 117 | R. Colmar | NRR/DHFS/ LQB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.2.6(3) | Revise 10 CFR 55 | R. Colmar | NRR/DHFS/ LQB | I.A.2.2 | 6 | 12/31/97 | NA |
| I.A.2.6(4) | Operator Workshops | R. Colmar | NRR/DHFS/ LQB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.2.6(5) | Develop Inspection Procedures for Training Program | R. Colmar | NRR/DHFS/ LQB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.2.6(6) | Nuclear Power Fundamentals | R. Colmar | NRR/DHFS/ LQB | DROP | 6 | 12/31/97 | NA |
| I.A.2.7 | Accreditation of Training Institutions | R. Colmar | NRR/DHFS/ LQB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.3 | Licensing and Requalification of Operating Personnel | ||||||
| I.A.3.1 | Revise Scope of Criteria for Licensing Examinations | R. Emrit | NRR/DHFS/ LQB | I | 6 | 12/31/97 | |
| I.A.3.2 | Operator Licensing Program Changes | R. Emrit | NRR/DHFS/ OLB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.3.3 | Requirements for Operator Fitness | R. Colmar | RES/DRAO/ HFSB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.3.4 | Licensing of Additional Operations Personnel | D. Thatcher | NRR/DHFS/ LQB | NOTE 3(b) | 6 | 12/31/97 | NA |
| I.A.3.5 | Establish Statement of Understanding with INPO and DOE | D. Thatcher | NRR/DHFS/ HFEB | LI (NOTE 3) | 6 | 12/31/97 | NA |
| I.A.4 | Simulator Use and Development | ||||||
| I.A.4.1 | Initial Simulator Improvement | ||||||
| I.A.4.1(1) | Short-Term Study of Training Simulators | D. Thatcher | NRR/DHFS/ OLB | NOTE 3(b) | 6 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.A.4.1(2) | Interim Changes in Training Simulators | D. Thatcher | NRR/DHFS/ OLB | NOTE 3(a) | 6 | 12/31/97 | |
| I.A.4.2 | Long-Term Training Simulator Upgrade | ||||||
| I.A.4.2(1) | Research on Training Simulators | R. Colmar | NRR/DHFT/ HFIB | NOTE 3(a) | 6 | 12/31/97 | |
| I.A.4.2(2) | Upgrade Training Simulator Standards | R. Colmar | RES/DFO/ HFBR | NOTE 3(a) | 6 | 12/31/97 | |
| I.A.4.2(3) | Regulatory Guide on Training Simulators | R. Colmar | RES/DFO/ HFBR | NOTE 3(a) | 6 | 12/31/97 | |
| I.A.4.2(4) | Review Simulators for Conformance to Criteria | R. Colmar | NRR/DLPQ/ LOLB | NOTE 3(a) | 6 | 12/31/97 | |
| I.A.4.3 | Feasibility Study of Procurement of NRC Training Simulator | R. Colmar | RES/DAE/ RSRB | LI (NOTE 3) | 6 | 12/31/97 | NA |
| I.A.4.4 | Feasibility Study of NRC Engineering Computer | R. Colmar | RES/DAE/ RSRB | LI (NOTE 3) | 6 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.B. | SUPPORT PERSONNEL | ||||||
| I.B.1 | Management for Operations | ||||||
| I.B.1.1 | Organization and Management Long-Term Improvements | ||||||
| I.B.1.1(1) | Prepare Draft Criteria | R. Colmar | NRR/DHFT/HFIB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.B.1.1(2) | Prepare Commission Paper | R. Colmar | NRR/DHFT/HFIB | NOTE 3(b) | 4 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.B.1.1(3) | Issue Requirements for the Upgrading of Management and Technical Resources | R. Colmar | NRR/DHFT/HFIB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.B.1.1(4) | Review Responses to Determine Acceptability | R. Colmar | NRR/DHFT/HFIB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.B.1.1(5) | Review Implementation of the Upgrading Activities | R. Colmar | OIE/DQASIP/ ORPB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.B.1.1(6) | Prepare Revisions to Regulatory Guides 1.33 and 1.8 | R. Colmar | NRR/DHFS/LQB | I.A.2.6(1), 75 | 4 | 12/31/97 | NA |
| I.B.1.1(7) | Issue Regulatory Guides 1.33 and 1.8 | R. Colmar | NRR/DHFS/LQB | I.A.2.6(1), 75 | 4 | 12/31/97 | NA |
| I.B.1.2 | Evaluation of Organization and Management Improvements of Near-Term Operating License Applicants | ||||||
| I.B.1.2(1) | Prepare Draft Criteria | - | NRR/DHFS/LQB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.B.1.2(2) | Review Near-Term Operating License Facilities | - | NRR/DHFS/LQB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.B.1.2(3) | Include Findings in the SER for Each Near-Term Operating License Facility | - | NRR/DL/ORAB | NOTE 3(b) | 4 | 12/13/97 | NA |
| I.B.1.3 | Loss of Safety Function | ||||||
| I.B.1.3(1) | Require Licensees to Place Plant in Safest Shutdown Cooling Following a Loss of Safety | G. Sege | RES | LI (NOTE 3) | 4 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Function Due to Personnel Error | |||||||
| I.B.1.3(2) | Use Existing Enforcement Options to Accomplish Safest Shutdown Cooling | G. Sege | RES | LI (NOTE 3) | 4 | 12/31/97 | NA |
| I.B.1.3(3) | Use Nonfiscal Approaches to Accomplish Safest Shutdown Cooling | G. Sege | RES | LI (NOTE 3) | 4 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.B.2 | Inspection of Operating Reactors | ||||||
| I.B.2.1 | Revise OIE Inspection Program | ||||||
| I.B.2.1(1) | Verify the Adequacy of Management and Procedural Controls and Staff Discipline | G. Sege | OIE/DQASIP/ RCPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.1(2) | Verify that Systems Required to Be Operable Are Properly Aligned | G. Sege | OIE/DQASIP/ RCPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.1(3) | Followup on Completed Maintenance Work Orders to Assure Proper Testing and Return to Service | G. Sege | OIE/DQASIP/ RCPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.1(4) | Observe Surveillance Tests to Determine whether Test | G. Sege | OIE/DQASIP/ RCPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Instruments Are Properly Calibrated | |||||||
| I.B.2.1(5) | Verify that Licensees Are Complying with Technical Specifications | G. Sege | OIE/DQASIP/ RCPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.1(6) | Observe Routine Maintenance | G. Sege | OIE/DQASIP/ RCPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.1(7) | Inspect Terminal Boards, Panels, and Instrument Racks for Unauthorized Jumpers and Bypasses | G. Sege | OIE/DQASIP/ RCPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.2 | Resident Inspector at Operating Reactors | G. Sege | OIE/DQASIP/ ORPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.3 | Regional Evaluations | G. Sege | OIE/DQASIP/ ORPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| I.B.2.4 | Overview of Licensee Performance | G. Sege | OIE/DQASIP/ ORPB | LI (NOTE 3) | 1 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.C | OPERATING PROCEDURES | ||||||
| I.C.1 | Short-Term Accident Analysis and Procedures Revision | ||||||
| I.C.1(1) | Small Break LOCAs | - | NRR | I | 4 | 12/31/97 | |
| I.C.1(2) | Inadequate Core Cooling | - | NRR | I | 4 | 12/31/97 | F-04 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.C.1(3) | Transients and Accidents | - | NRR | I | 4 | 12/31/97 | F-05 |
| I.C.1(4) | Confirmatory Analyses of Selected Transients | R. Riggs | NRR/DSI/RSB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.C.2 | Shift and Relief Turnover Procedures | - | NRR | I | 4 | 12/31/97 | |
| I.C.3 | Shift Supervisor Responsibilities | - | NRR | I | 4 | 12/31/97 | |
| I.C.4 | Control Room Access | - | NRR | I | 4 | 12/31/97 | |
| I.C.5 | Procedures for Feedback of Operating Experience to Plant Staff | - | NRR/DL | I | 4 | 12/31/97 | F-06 |
| I.C.6 | Procedures for Verification of Correct Performance of Operating Activities | - | NRR/DL | I | 4 | 12/31/97 | F-07 |
| I.C.7 | NSSS Vendor Review of Procedures | - | NRR/DHFS/ PSRB | I | 4 | 12/31/97 | |
| I.C.8 | Pilot Monitoring of Selected Emergency Procedures for Near-Term Operating License Applicants | - | NRR/DHFS/ PSRB | I | 4 | 12/31/97 | |
| I.C.9 | Long-Term Program Plan for Upgrading of Procedures | R. Riggs | NRR/DHFS/ PSRB | NOTE 3(b) | 4 | 12/31/97 | NA |
| I.D | CONTROL ROOM DESIGN | ||||||
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.D.1 | Control Room Design Reviews | - | NRR/DL | I | 8 | 12/31/97 | F-08 |
| I.D.2 | Plant Safety Parameter Display Console | - | NRR/DL | I | 8 | 12/31/97 | F-09 |
| I.D.3 | Safety System Status Monitoring | D. Thatcher | RES/DE/MEB | NOTE 3(b) | 8 | 12/31/97 | NA |
| I.D.4 | Control Room Design Standard | D. Thatcher | RES/DRPS/ RHFB | NOTE 3(b) | 8 | 12/31/97 | NA |
| I.D.5 | Improved Control Room Instrumentation Research | ||||||
| I.D.5(1) | Operator-Process Communication | D. Thatcher | RES/DFO/ HFBR | NOTE 3(b) | 8 | 12/31/97 | NA |
| I.D.5(2) | Plant Status and Post-Accident Monitoring | D. Thatcher | RES/DFO/ HFBR | NOTE 3(a) | 8 | 12/31/97 | |
| I.D.5(3) | On-Line Reactor Surveillance System | D. Thatcher | RES/DE/MEB | NOTE 3(b) | 8 | 12/31/97 | NA |
| I.D.5(4) | Process Monitoring Instrumentation | D. Thatcher | RES/DFO/ ICBR | NOTE 3(b) | 8 | 12/31/97 | NA |
| I.D.5(5) | Disturbance Analysis Systems | D. Thatcher | RES/DRPS/ RHFB | LI (NOTE 3) | 8 | 12/31/97 | NA |
| I.D.6 | Technology Transfer Conference | D. Thatcher | RES/DFO/ HFBR | LI (NOTE 3) | 8 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.E | ANALYSIS AND DISSEMINATION OF OPERATING EXPERIENCE | ||||||
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| I.E.1 | Office for Analysis and Evaluation of Operational Data | P. Matthews | AEOD/PTB | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.E.2 | Program Office Operational Data Evaluation | P. Matthews | NRR/DL/ORAB | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.E.3 | Operational Safety Data Analysis | P. Matthews | RES/DRA/RRBR | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.E.4 | Coordination of Licensee, Industry, and Regulatory Programs | P. Matthews | AEOD/PTB | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.E.5 | Nuclear Plant Reliability Data System | P. Matthews | AEOD/PTB | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.E.6 | Reporting Requirements | P. Matthews | AEOD/PTB | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.E.7 | Foreign Sources | P. Matthews | IP | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.E.8 | Human Error Rate Analysis | P. Matthews | RES/DFO/HFBR | LI (NOTE 3) | 3 | 12/31/97 | NA |
| I.F | QUALITY ASSURANCE | ||||||
| I.F.1 | Expand QA List | J. Pittman | RES/DRA/ARGIB | NOTE 3(b) | 4 | 12/31/98 | NA |
| I.F.2 | Develop More Detailed QA Criteria | ||||||
| I.F.2(1) | Assure the Independence of the Organization Performing the Checking Function | J. Pittman | OIE/DQASIP/ QUAB | DROP | 5 | 9/30/11 | NA |
| I.F.2(2) | Include QA Personnel in | J. Pittman | OIE/DQASIP/ QUAB | NOTE 3(a) | 5 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Review and Approval of Plant Procedures | |||||||
| I.F.2(3) | Include QA Personnel in All Design, Construction, Installation, Testing, and Operation Activities | J. Pittman | OIE/DQASIP/ QUAB | NOTE 3(a) | 5 | 9/30/11 | NA |
| I.F.2(4) | Establish Criteria for Determining QA Requirements for Specific Classes of Equipment | J. Pittman | OIE/DQASIP/ QUAB | DROP | 5 | 9/30/11 | NA |
| I.F.2(5) | Establish Qualification Requirements for QA and QC Personnel | J. Pittman | OIE/DQASIP/ QUAB | DROP | 5 | 9/30/11 | NA |
| I.F.2(6) | Increase the Size of Licensees' QA Staff | J. Pittman | OIE/DQASIP/ QUAB | NOTE 3(a) | 5 | 9/30/11 | NA |
| I.F.2(7) | Clarify that the QA Program Is a Condition of the Construction Permit and Operating License | J. Pittman | OIE/DQASIP/ QUAB | DROP | 5 | 9/30/11 | NA |
| I.F.2(8) | Compare NRC QA Requirements with Those of Other Agencies | J. Pittman | OIE/DQASIP/ QUAB | DROP | 5 | 9/30/11 | NA |
| I.F.2(9) | Clarify Organizational Reporting Levels for the QA Organization | J. Pittman | OIE/DQASIP/ QUAB | NOTE 3(a) | 5 | 9/30/11 | NA |
| I.F.2(10) | Clarify Requirements for Maintenance | J. Pittman | OIE/DQASIP/ QUAB | DROP | 5 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| of "As-Built" Documentation | |||||||
| I.F.2(11) | Define Role of QA in Design and Analysis Activities | J. Pittman | OIE/DQASIP/ QUAB | DROP | 5 | 9/30/11 | NA |
| I.G | PREOPERATIONAL AND LOW-POWER TESTING | ||||||
| I.G.1 | Training Requirements | - | NRR/DHFS/ PSRB | I | 3 | 12/31/97 | |
| I.G.2 | Scope of Test Program | H. Vandermolen | NRR/DHFS/ PSRB | NOTE 3(a) | 3 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.A | SITING | ||||||
| II.A.1 | Siting Policy Reformulation | H. Vandermolen | NRR/DE/SAB | NOTE 3(b) | 2 | 12/31/97 | NA |
| II.A.2 | Site Evaluation of Existing Facilities | H. Vandermolen | NRR/DE/SAB | V.A.1 | 2 | 12/31/97 | NA |
| II.B | CONSIDERATION OF DEGRADED OR MELTED CORES IN SAFETY REVIEW | ||||||
| II.B.1 | Reactor Coolant System Vents | - | NRR/DL | I | 5 | 9/30/11 | F-10 |
| II.B.2 | Plant Shielding to Provide Access to Vital Areas and Protect Safety Equipment for Post- Accident Operation | - | NRR/DL | I | 5 | 9/30/11 | F-11 |
| II.B.3 | Post-Accident Sampling | - | NRR/DL | I | 5 | 9/30/11 | F-12 |
| II.B.4 | Training for Mitigating Core Damage | - | NRR/DL | I | 5 | 9/30/11 | F-13 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.B.5 | Research on Phenomena Associated with Core Degradation and Fuel Melting | ||||||
| II.B.5(1) | Behavior of Severely Damaged Fuel | H. Vandermolen | RES/DSR/AEB | LI (NOTE 5) | 5 | 9/30/11 | NA |
| II.B.5(2) | Behavior of Core- Melt | H. Vandermolen | RES/DSR/AEB | LI (NOTE 5) | 5 | 9/30/11 | NA |
| II.B.5(3) | Effect of Hydrogen Burning and Explosions on Containment Structure | H. Vandermolen | RES/DSR/AEB | LI (NOTE 5) | 5 | 9/30/11 | NA |
| II.B.6 | Risk Reduction for Operating Reactors at Sites with High Population Densities | J. Pittman | NRR/DST/RRAB | NOTE 3(a) | 5 | 9/30/11 | |
| II.B.7 | Analysis of Hydrogen Control | P. Matthews | NRR/DSI/CSB | II.B.8 | 5 | 9/30/11 | |
| II.B.8 | Rulemaking Proceeding on Degraded Core Accidents | H. Vandermolen | RES/DRAO/ RAMR | NOTE 3(a) | 5 | 9/30/11 | |
| II.C | RELIABILITY ENGINEERING AND RISK ASSESSMENT | ||||||
| II.C.1 | Interim Reliability Evaluation Program | J. Pittman | RES/DRAO/RRB | NOTE 3(b) | 3 | 12/31/97 | NA |
| II.C.2 | Continuation of Interim Reliability Evaluation Program | J. Pittman | NRR/DST/RRAB | NOTE 3(b) | 3 | 12/31/97 | NA |
| II.C.3 | Systems Interaction | J. Pittman | NRR/DST/GIB | A-17 | 3 | 12/31/97 | NA |
| II.C.4 | Reliability Engineering | J. Pittman | RES/DRPS/ RHFB | NOTE 3(b) | 3 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.D | REACTOR COOLANT SYSTEM RELIEF AND SAFETY VALVES | ||||||
| II.D.1 | Testing Requirements | - | NRR/DL | I | 3 | 12/31/98 | F-14 |
| II.D.2 | Research on Relief and Safety Valve Test Requirements | R. Riggs | RES | DROP | 3 | 12/31/98 | NA |
| II.D.3 | Relief and Safety Valve Position Indication | - | NRR | I | 3 | 12/31/98 | |
| II.E | SYSTEM DESIGN | ||||||
| II.E.1 | Auxiliary Feedwater System | ||||||
| II.E.1.1 | Auxiliary Feedwater System Evaluation | - | NRR/DL | I | 2 | 12/31/97 | F-15 |
| II.E.1.2 | Auxiliary Feedwater System Automatic Initiation and Flow Indication | R. Riggs | NRR/DL | I | 2 | 12/31/98 | F-16, F-17 |
| II.E.2 | Emergency Core Cooling System | ||||||
| II.E.2.1 | Reliance on ECCS | R. Riggs | NRR/DSI/RSB | II.K.3(17) | 3 | 12/31/98 | NA |
| II.E.2.2 | Research on Small Break LOCAs and Anomalous Transients | R. Riggs | RES/DAE/ RSRB | NOTE 3(b) | 3 | 12/31/98 | NA |
| II.E.2.3 | Uncertainties in Performance Predictions | H. Vandermolen | NRR/DSI/RSB | DROP | 3 | 12/31/98 | NA |
| II.E.3 | Decay Heat Removal | ||||||
| II.E.3.1 | Reliability of Power Supplies for Natural Circulation | - | NRR/DL | I | 2 | 12/31/97 | |
| II.E.3.2 | Systems Reliability | H. Vandermolen | NRR/DST/GIB | A-45 | 2 | 12/31/97 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.E.3.3 | Coordinated Study of Shutdown Heat Removal Requirements | H. Vandermolen | NRR/DST/GIB | A-45 | 2 | 12/31/97 | NA |
| II.E.3.4 | Alternate Concepts Research | R. Riggs | RES/DAE/ FBRB | NOTE 3(b) | 2 | 12/31/97 | NA |
| II.E.3.5 | Regulatory Guide | R. Riggs | NRR/DST/GIB | A-45 | 2 | 12/31/97 | NA |
| II.E.4 | Containment Design | ||||||
| II.E.4.1 | Dedicated Penetrations | - | NRR/DL | I | 2 | 12/31/97 | F-18 |
| II.E.4.2 | Isolation Dependability | - | NRR/DL | I | 2 | 12/31/97 | F-19 |
| II.E.4.3 | Integrity Check | W. Milstead | RES/DRPS/ RPSI | NOTE 3(b) | 2 | 12/31/97 | NA |
| II.E.4.4 | Purging | ||||||
| II.E.4.4(1) | Issue Letter to Licensees Requesting Limited Purging | W. Milstead | NRR/DSI/CSB | NOTE 3(a) | 2 | 12/31/97 | |
| II.E.4.4(2) | Issue Letter to Licensees Requesting Information on Isolation Letter | W. Milstead | NRR/DSI/CSB | NOTE 3(a) | 2 | 12/31/97 | |
| II.E.4.4(3) | Issue Letter to Licensees on Valve Operability | W. Milstead | NRR/DSI/CSB | NOTE 3(a) | 2 | 12/31/97 | |
| II.E.4.4(4) | Evaluate Purging and Venting during Normal Operation | W. Milstead | NRR/DSI/CSB | NOTE 3(b) | 2 | 12/31/97 | NA |
| II.E.4.4(5) | Issue Modified Purging and Venting Requirement | W. Milstead | NRR/DSI/CSB | NOTE 3(b) | 2 | 12/31/97 | NA |
| II.E.5 | Design Sensitivity of B&W Reactors | ||||||
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.E.5.1 | Design Evaluation | D. Thatcher | NRR/DSI/RSB | NOTE 3(a) | 2 | 12/31/98 | |
| II.E.5.2 | B&W Reactor Transient Response Task Force | D. Thatcher | NRR/DL/ ORAB | NOTE 3(a) | 2 | 12/31/98 | |
| II.E.6 | In Situ Testing of Valves | ||||||
| II.E.6.1 | Test Adequacy Study | D. Thatcher | RES/DE/EIB | NOTE 3(a) | 2 | 12/31/98 | |
| II.F | INSTRUMENTATION AND CONTROLS | ||||||
| II.F.1 | Additional Accident Monitoring Instrumentation | - | NRR/DL | I | 3 | 12/31/98 | F-20, F-21 F-22, F-23, F-24, F-25 |
| II.F.2 | Identification of and Recovery from Conditions Leading to Inadequate Core Cooling | - | NRR/DL | I | 3 | 12/31/98 | F-26 |
| II.F.3 | Instruments for Monitoring Accident Conditions | H. Vandermolen | RES/DFO/ ICBR | NOTE 3(a) | 3 | 12/31/98 | |
| II.F.4 | Study of Control and Protective Action Design Requirements | D. Thatcher | NRR/DSI/ICSB | DROP | 3 | 12/31/98 | NA |
| II.F.5 | Classification of Instrumentation, Control, and Electrical Equipment | D. Thatcher | RES/DE | LI (NOTE 3) | 3 | 12/31/98 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.G | ELECTRICAL POWER | ||||||
| II.G.1 | Power Supplies for Pressurizer Relief Valves, Block Valves, and Level Indicators | - | NRR | I | 1 | 12/31/98 | NA |
| II.H | TMI-2 CLEANUP AND EXAMINATION | ||||||
| II.H.1 | Maintain Safety of TMI-2 and Minimize Environmental Impact | P. Matthews | NRR/TMIPO | NOTE 3(b) | 3 | 12/31/98 | NA |
| II.H.2 | Obtain Technical Data on the Conditions Inside the TMI-2 Containment Structure | W. Milstead | RES/DRAA/ AEB | NOTE 3(b) | 3 | 12/31/98 | NA |
| II.H.3 | Evaluate and Feed Back Information Obtained from TMI | W. Milstead | NRR/TMIPO | II.H.2 | 3 | 12/31/98 | NA |
| II.H.4 | Determine Impact of TMI on Socioeconomic and Real Property Values | W. Milstead | RES/DHSWM/ SEBR | LI (NOTE 3) | 3 | 12/31/98 | NA |
| II.J | GENERAL IMPLICATIONS OF TMI FOR DESIGN AND CONSTRUCTION ACTIVITIES | ||||||
| II.J.1 | Vendor Inspection Program | ||||||
| II.J.1.1 | Establish a Priority System for Conducting Vendor Inspections | L. Riani | OIE/DQASIP | LI (NOTE 3) | 1 | 12/31/98 | NA |
| II.J.1.2 | Modify Existing Vendor Inspection Program | L. Riani | OIE/DQASIP | LI (NOTE 3) | 1 | 12/31/98 | NA |
| II.J.1.3 | Increase Regulatory Control Over | L. Riani | OIE/DQASIP | LI (NOTE 3) | 1 | 12/31/98 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Present Non- Licensees | |||||||
| II.J.1.4 | Assign Resident Inspectors to Reactor Vendors and Architect- Engineers | L. Riani | OIE/DQASIP | LI (NOTE 3) | 1 | 12/31/98 | NA |
| II.J.2 | Construction Inspection Program | ||||||
| II.J.2.1 | Reorient Construction Inspection Program | L. Riani | OIE/DQASIP | LI (NOTE 3) | 1 | 12/31/98 | NA |
| II.J.2.2 | Increase Emphasis on Independent Measurement in Construction Inspection Program | L. Riani | OIE/DQASIP | LI (NOTE 3) | 1 | 12/31/98 | NA |
| II.J.2.3 | Assign Resident Inspectors to All Construction Sites | L. Riani | OIE/DQASIP | LI (NOTE 3) | 1 | 12/31/98 | NA |
| II.J.3 | Management for Design and Construction | ||||||
| II.J.3.1 | Organization and Staffing to Oversee Design and Construction | J. Pittman | NRR/DHFS/ LQB | I.B.1.1 | 1 | 12/31/98 | NA |
| II.J.3.2 | Issue Regulatory Guide | J. Pittman | NRR/DHFS/ LQB | I.B.1.1 | 1 | 12/31/98 | NA |
| II.J.4 | Revise Deficiency Reporting Requirements | ||||||
| II.J.4.1 | Revise Deficiency Reporting Requirements | L. Riani | AEOD/DSP/ ROAB | NOTE 3(a) | 3 | 12/31/98 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K | |||||||
| II.K.1 | IE Bulletins | ||||||
| II.K.1(1) | Review TMI-2 PNs and Detailed Chronology of the TMI-2 Accident | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(2) | Review Transients Similar to TMI-2 That Have Occurred at Other Facilities and NRC Evaluation of Davis-Besse Event | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(3) | Review Operating Procedures for Recognizing, Preventing, and Mitigating Void Formation in Transients and Accidents | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(4) | Review Operating Procedures and Training Instructions | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(5) | Safety-Related Valve Position Description | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(6) | Review Containment Isolation Initiation Design and Procedures | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(7) | Implement Positive Position Controls on Valves That Could Compromise or Defeat AFW Flow | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(8) | Implement Procedures That Assure Two Independent 100% AFW Flow Paths | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.1(9) | Review Procedures to Assure That Radioactive Liquids and Gases Are Not Transferred Out of Containment Inadvertently | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(10) | Review and Modify Procedures for Removing Safety- Related Systems from Service | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(11) | Make All Operating and Maintenance Personnel Aware of the Seriousness and Consequences of the Erroneous Actions Leading up to, and in Early Phases of, the TMI-2 Accident | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(12) | One-Hour Notification Requirement and Continuous Communications Channels | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(13) | Propose Technical Specification Changes Reflecting Implementation of All Bulletin Items | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(14) | Review Operating Modes and Procedures to Deal with Significant Amounts of Hydrogen | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(15) | For Facilities with Non-Automatic AFW Initiation, Provide Dedicated Operator in Continuous | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Communication with CR to Operate AFW | |||||||
| II.K.1(16) | Implement Procedures That Identify PRZ PORV "Open" Indications and That Direct Operator to Close Manually at "Reset" Setpoint | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(17) | Trip PZR Level Bistable So That PZR Low Pressure Will Initiate Safety Injection | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(18) | Develop Procedures and Train Operators on Methods of Establishing and Maintaining Natural Circulation | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(19) | Describe Design and Procedure Modifications to Reduce Likelihood of Automatic PZR PORV Actuation in Transients | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(20) | Provide Procedures and Training to Operators for Prompt Manual Reactor Trip for LOFW, TT, MSIV Closure, LOOP, LOSG Level, and LO PZR Level | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(21) | Provide Automatic Safety-Grade Anticipatory Reactor Trip for LOFW, TT, or Significant Decrease in SG Level | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.1(22) | Describe Automatic and Manual Actions for Proper Functioning of Auxiliary Heat Removal Systems When FW System Not Operable | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(23) | Describe Uses and Types of RV Level Indication for Automatic and Manual Initiation Safety Systems | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(24) | Perform LOCA Analyses for a Range of Small-Break Sizes and a Range of Time Lapses between Reactor Trip and RCP Trip | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(25) | Develop Operator Action Guidelines | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(26) | Revise Emergency Procedures and Train ROs and SROs | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(27) | Provide Analyses and Develop Guidelines and Procedures for Inadequate Core Cooling Conditions | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.1(28) | Provide Design That Will Assure Automatic RCP Trip for All Circumstances Where Required | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.2 | Commission Orders on B&W Plants | ||||||
| II.K.2(1) | Upgrade Timeliness and Reliability of AFW System | R. Emrit | NRR/DSI | NOTE 3(a) | - | 12/31/84 | |
| II.K.2(2) | Procedures and Training to Initiate and Control AFW Independent of Integrated Control System | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.2(3) | Hard-Wired Control- Grade Anticipatory Reactor Trips | R. Emrit | NRR/DSI | NOTE 3(a) | - | 12/31/84 | |
| II.K.2(4) | Small-Break LOCA Analysis, Procedures and Operator Training | R. Emrit | NRR/DHFS/ OLB | NOTE 3(a) | - | 12/31/84 | |
| II.K.2(5) | Complete TMI-2 Simulator Training for All Operators | R. Emrit | NRR | NOTE 3(a) | - | 12/31/84 | |
| II.K.2(6) | Reevaluate Analysis for Dual-Level Setpoint Control | R. Emrit | NRR/DSI | NOTE 3(a) | - | 12/31/84 | |
| II.K.2(7) | Reevaluate Transient of September 24, 1977 | R. Emrit | NRR/DSI | NOTE 3(a) | - | 12/31/84 | |
| II.K.2(8) | Continued Upgrading of AFW System | R. Emrit | NRR | II.E.1.1, II.E.1.2 | - | 12/31/84 | NA |
| II.K.2(9) | Analysis and Upgrading of Integrated Control System | R. Emrit | NRR | I | - | 12/31/84 | F-27 |
| II.K.2(10) | Hard-Wired Safety- Grade Anticipatory Reactor Trips | R. Emrit | NRR | I | - | 12/31/84 | F-28 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.2(11) | Operator Training and Drilling | R. Emrit | NRR | I | - | 12/31/84 | F-29 |
| II.K.2(12) | Transient Analysis and Procedures for Management of Small Breaks | R. Emrit | NRR | I.C.1(3) | - | 12/31/84 | NA |
| II.K.2(13) | Thermal-Mechanical Report on Effect of HPI on Vessel Integrity for Small- Break LOCA with No AFW | R. Emrit | NRR | I | - | 12/31/84 | F-30 |
| II.K.2(14) | Demonstrate That Predicted Lift Frequency of PORVs and SVs Is Acceptable | R. Emrit | NRR | I | - | 12/31/84 | F-31 |
| II.K.2(15) | Analysis of Effects of Slug Flow on Once-Through Steam Generator Tubes after Primary System Voiding | R. Emrit | NRR | I | - | 12/31/84 | |
| II.K.2(16) | Impact of RCP Seal Damage Following Small-Break LOCA with Loss of Offsite Power | R. Emrit | NRR | I | - | 12/31/84 | F-32 |
| II.K.2(17) | Analysis of Potential Voiding in RCS during Anticipated Transients | R. Emrit | NRR | I | - | 12/31/84 | F-33 |
| II.K.2(18) | Analysis of Loss of Feedwater and Other Anticipated Transients | R. Emrit | NRR | I.C.1(3) | - | 12/31/84 | NA |
| II.K.2(19) | Benchmark Analysis of Sequential AFW Flow to Once- | R. Emrit | NRR | I | - | 12/31/84 | F-34 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Through Steam Generator | |||||||
| II.K.2(20) | Analysis of Steam Response to Small- Break LOCA That Causes System Pressure to Exceed PORV Setpoint | R. Emrit | NRR | I | - | 12/31/84 | F-35 |
| II.K.2(21) | LOFT L3-1 Predictions | R. Emrit | NRR/DSI | NOTE 3(a) | - | 12/31/84 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.3 | Final Recommendations of Bulletins and Orders Task Force | ||||||
| II.K.3(1) | Install Automatic PORV Isolation System and Perform Operational Test | R. Emrit | NRR | I | 12/31/84 | F-36 | |
| II.K.3(2) | Report on Overall Safety Effect of PORV Isolation System | R. Emrit | NRR | I | 12/31/84 | F-37 | |
| II.K.3(3) | Report Safety and Relief Valve Failures Promptly and Challenges Annually | R. Emrit | NRR | I | 12/31/84 | F-38 | |
| II.K.3(4) | Review and Upgrade Reliability and Redundancy of Non- Safety Equipment for Small-Break LOCA Mitigation | R. Emrit | NRR | II.C.1, II.C.2, II.C.3 | 12/31/84 | NA | |
| II.K.3(5) | Automatic Trip of Reactor Coolant Pumps | R. Emrit | NRR | I | 12/31/84 | F-39, G-01 | |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.3(6) | Instrumentation to Verify Natural Circulation | R. Emrit | NRR/DSI | I.C.1(3), II.F.2, II.F.3 | 12/31/84 | NA | |
| II.K.3(7) | Evaluation of PORV Opening Probability during Overpressure Transient | R. Emrit | NRR | I | 12/31/84 | ||
| II.K.3(8) | Further Staff Consideration of Need for Diverse Decay Heat Removal Method Independent of SGs | R. Emrit | NRR/DST/ GIB | II.C.1, II.E.3.3 | 12/31/84 | NA | |
| II.K.3(9) | Proportional Integral Derivative Controller Modification | R. Emrit | NRR | I | 12/31/84 | F-40 | |
| II.K.3(10) | Anticipatory Trip Modification Proposed by Some Licensees to Confine Range of Use to High Power Levels | R. Emrit | NRR | I | 12/31/84 | F-41 | |
| II.K.3(11) | Control Use of PORV Supplied by Control Components, Inc., Until Further Review Complete | R. Emrit | NRR | I | 12/31/84 | ||
| II.K.3(12) | Confirm Existence of Anticipatory Trip Upon Turbine Trip | R. Emrit | NRR | I | 12/31/84 | F-42 | |
| II.K.3(13) | Separation of HPCI and RCIC System Initiation Levels | R. Emrit | NRR | I | 12/31/84 | F-43 | |
| II.K.3(14) | Isolation of Isolation Condensers on High Radiation | R. Emrit | NRR | I | 12/31/84 | F-44 | |
| II.K.3(15) | Modify Break Detection Logic to Prevent Spurious | R. Emrit | NRR | I | 12/31/84 | F-45 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Isolation of HPCI and RCIC Systems | |||||||
| II.K.3(16) | Reduction of Challenges and Failures of Relief ValvesFeasibility Study and System Modification | R. Emrit | NRR | I | 12/31/84 | F-46 | |
| II.K.3(17) | Report on Outage of ECC Systems Licensee and Technical Specification Changes Report | R. Emrit | NRR | I | 12/31/84 | F-47 | |
| II.K.3(18) | Modification of ADS Logic Feasibility Study and Modification for Increased Diversity for Some Event Sequences | R. Emrit | NRR | I | 12/31/84 | F-48 | |
| II.K.3(19) | Interlock on Recirculation Pump Loops | R. Emrit | NRR | I | 12/31/84 | F-49 | |
| II.K.3(20) | Loss of Service Water for Big Rock Point | R. Emrit | NRR | I | 12/31/84 | ||
| II.K.3(21) | Restart of Core Spray and LPCI Systems on Low LevelDesign and Modification | R. Emrit | NRR | I | 12/31/84 | F-50 | |
| II.K.3(22) | Automatic Switchover of RCIC System Suction Verify Procedures and Modify Design | R. Emrit | NRR | I | 12/31/84 | F-51 | |
| II.K.3(23) | Central Water Level Recording | R. Emrit | NRR | I.D.2, III.A.1.2(1), III.A.3.4 | 12/31/84 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.3(24) | Confirm Adequacy of Space Cooling for HPCI and RCIC Systems | R. Emrit | NRR | I | 12/31/84 | F-52 | |
| II.K.3(25) | Effect of Loss of AC Power on Pump Seals | R. Emrit | NRR | I | 12/31/84 | F-53 | |
| II.K.3(26) | Study Effect on RHR Reliability of Its Use for Fuel Pool Cooling | R. Emrit | NRR/DSI | II.E.2.1 | 12/31/84 | NA | |
| II.K.3(27) | Provide Common Reference Level for Vessel Level Instrumentation | R. Emrit | NRR | I | 12/31/84 | F-54 | |
| II.K.3(28) | Study and Verify Qualification of Accumulators on ADS Valves | R. Emrit | NRR | I | 12/31/84 | F-55 | |
| II.K.3(29) | Study to Demonstrate Performance of Isolation Condensers with Non-Condensibles | R. Emrit | NRR | I | 12/31/84 | F-56 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.3(30) | Revised Small-Break LOCA Methods to Show Compliance with 10 CFR 50, Appendix K | R. Emrit | NRR | I | 12/31/84 | F-57 | |
| II.K.3(31) | Plant-Specific Calculations to Show | R. Emrit | NRR | I | 12/31/84 | F-58 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Compliance 10 CFR 50.46 with | |||||||
| II.K.3(32) | Provide Experimental Verification of Two- Phase Natural Circulation Models | R. Emrit | NRR/DSI | II.E.2.2 | 12/31/84 | NA | |
| II.K.3(33) | Evaluate Elimination of PORV Function | R. Emrit | NRR | II.C.1 | 12/31/84 | NA | |
| II.K.3(34) | Relap-4 Model Development | R. Emrit | NRR/DSI | II.E.2.2 | 12/31/84 | NA | |
| II.K.3(35) | Evaluation of Effects of Core Flood Tank Injection on Small- Break LOCAs | R. Emrit | NRR | I.C.1(3) | 12/31/84 | NA | |
| II.K.3(36) | Additional Staff Audit Calculations of B&W Small-Break LOCA Analyses | R. Emrit | NRR | I.C.1(3) | 12/31/84 | NA | |
| II.K.3(37) | Analysis of B&W Response to Isolated Small-Break LOCA | R. Emrit | NRR | I.C.1(3) | 12/31/84 | NA | |
| II.K.3(38) | Analysis of Plant Response to a Small-Break LOCA in the Pressurizer Spray Line | R. Emrit | NRR | I.C.1(3) | 12/31/84 | NA | |
| II.K.3(39) | Evaluation of Effects of Water Slugs in Piping Caused by HPI and CFT Flows | R. Emrit | NRR | I.C.1(3) | 12/31/84 | NA | |
| II.K.3(40) | Evaluation of RCP Seal Damage and Leakage during a Small-Break LOCA | R. Emrit | NRR | II.K.2(16) | 12/31/84 | NA | |
| II.K.3(41) | Submit Predictions for LOFT Test L3-6 with RCPs Running | R. Emrit | NRR | I.C.1(3) | 12/31/84 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.3(42) | Submit Requested Information on the Effects of Non- Condensible Gases | R. Emrit | NRR | I.C.1(3) | 12/31/84 | NA | |
| II.K.3(43) | Evaluation of Mechanical Effects of Slug Flow on Steam Generator Tubes | R. Emrit | NRR | II.K.2(15) | 12/31/84 | NA | |
| II.K.3(44) | Evaluation of Anticipated Transients with Single Failure to Verify No Significant Fuel Failure | R. Emrit | NRR | I | 12/31/84 | F-59 | |
| II.K.3(45) | Evaluate Depressurization with Other Than Full ADS | R. Emrit | NRR | I | 12/31/84 | F-60 | |
| II.K.3(46) | Response to List of Concerns from ACRS Consultant | R. Emrit | NRR | I | 12/31/84 | F-61 | |
| II.K.3(47) | Test Program for Small-Break LOCA Model Verification Pretest Prediction, Test Program, and Model Verification | R. Emrit | NRR | I.C.1(3), II.E.2.2 | 12/31/84 | NA | |
| II.K.3(48) | Assess Change in Safety Reliability as a Result of | R. Emrit Implementing B&OTF Recommendatio | NRR ns | II.C.1, II.C.2 | 12/31/84 | NA | |
| II.K.3(49) | Review of Procedures (NRC) | R. Emrit | NRR/DHFS/ PSRB | I.C.8, I.C.9 | 12/31/84 | NA | |
| II.K.3(50) | Review of Procedures (NSSS Vendors) | R. Emrit | NRR/DHFS/ PSRB | I.C.7, I.C.9 | 12/31/84 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| II.K.3(51) | Symptom-Based Emergency Procedures | R. Emrit | NRR/DHFS/ PSRB | I.C.9 | 12/31/84 | NA | |
| II.K.3(52) | Operator Awareness of Revised Emergency Procedures | R. Emrit | NRR | I.B.1.1, I.C.2, I.C.5 | 12/31/84 | NA | |
| II.K.3(53) | Two Operators in Control Room | R. Emrit | NRR | I.A.1.3 | 12/31/84 | NA | |
| II.K.3(54) | Simulator Upgrade for Small-Break LOCAs | R. Emrit | NRR | I.A.4.1(2) | 12/31/84 | NA | |
| II.K.3(55) | Operator Monitoring of Control Board | R. Emrit | NRR | I.C.1(3), I.D.2, I.D.3 | 12/31/84 | NA | |
| II.K.3(56) | Simulator Training Requirements | R. Emrit | NRR/DHFS/ OLB | I.A.2.6(3), I.A.3.1 | 12/31/84 | NA | |
| II.K.3(57) | Identify Water Sources Prior to Manual Activation of ADS | R. Emrit | NRR | I | 12/31/84 | F-62 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.A | EMERGENCY PREPAREDNESS AND RADIATION EFFECTS | ||||||
| III.A.1 | Improve Licensee Emergency PreparednessShort-Term | ||||||
| III.A.1.1 | Upgrade Emergency Preparedness | ||||||
| III.A.1.1(1) | Implement Action Plan Requirements for Promptly Improving Licensee Emergency Preparedness | - | OIE/DEPER/ EPB | I | 2 | 6/30/91 | |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.A.1.1(2) | Perform an Integrated Assessment of the Implementation | - | OIE/DEPER/ EPB | NOTE 3(b) | 2 | 6/30/91 | NA |
| III.A.1.2 | Upgrade Licensee Emergency Support Facilities | ||||||
| III.A.1.2( | 1T) echnical Support Center | - | OIE/DEPER/ EPB | I | 2 | 6/30/91 | F-63 |
| III.A.1.2( | 2O) n-Site Operational Support Center | - | OIE/DEPER/ EPB | I | 2 | 6/30/91 | F-64 |
| III.A.1.2( | 3N) ear-Site Emergency Operations Facility | - | OIE/DEPER/ EPB | I | 2 | 6/30/91 | F-65 |
| III.A.1.3 | Maintain Supplies of Thyroid-Blocking Agent | ||||||
| III.A.1.3( | 1W) orkers | R. Riggs | OIE/DEPER/ EPB | NOTE 3(b) | 2 | 6/30/91 | NA |
| III.A.1.3( | 2P) ublic | R. Riggs | OIE/DEPER/ EPB | NOTE 3(b) | 2 | 6/30/91 | NA |
| III.A.2 | Improving Licensee Emergency PreparednessLong-Term | ||||||
| III.A.2.1 | Amend 10 CFR 50 and 10 CFR 50, Appendix E | ||||||
| III.A.2.1( | 1P) ublish Proposed Amendments to the Rules | - | RES | NOTE 3(a) | - | 12/31/94 | NA |
| III.A.2.1( | 2C) onduct Public Regional Meetings | - | RES | NOTE 3(b) | - | 12/31/94 | NA |
| III.A.2.1( | 3P) repare Final Commission Paper Recommending Adoption of Rules | - | RES | NOTE 3(b) | - | 12/31/94 | NA |
| III.A.2.1( | 4R) evise Inspection Program to Cover Upgraded Requirements | - | OIE | I | - | F-67 | |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.A.2.2 | Development of Guidance and Criteria | - | NRR/DL | I | - | F-68 | |
| III.A.3 | Improving NRC Emergency Preparedness | ||||||
| III.A.3.1 | NRC Role in Responding to Nuclear Emergencies | ||||||
| III.A.3.1( | 1D) efine NRC Role in Emergency Situations | R. Riggs | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.1( | 2R) evise and Upgrade Plans and Procedures for the NRC Emergency Operations Center | R. Riggs | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.1( | 3R) evise Manual Chapter 0502, Other Agency Procedures, and NUREG-0610 | R. Riggs | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.1( | 4P) repare Commission Paper | R. Riggs | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.1( | 5R) evise Implementing Procedures and Instructions for Regional Offices | R. Riggs | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.2 | Improve Operations Centers | R. Riggs | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.3 | Communications | ||||||
| III.A.3.3( | 1I)nstall Direct Dedicated Telephone Lines | J. Pittman | OIE/DEPER/ IRDB | NOTE 3(a) | 1 | 6/30/85 | NA |
| III.A.3.3( | 2O) btain Dedicated, Short-Range Radio Communication Systems | J. Pittman | OIE/DEPER/ IRDB | NOTE 3(a) | 1 | 6/30/85 | NA |
| III.A.3.4 | Nuclear Data Link | D. Thatcher | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.A.3.5 | Training, Drills, and Tests | J. Pittman | OIE/DEPER/ IRDB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.6 | Interaction of NRC and Other Agencies | ||||||
| III.A.3.6( | 1I)nternational | J. Pittman | OIE/DEPER/ EPLB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.6( | 2F) ederal | J. Pittman | OIE/DEPER/ EPLB | NOTE 3(b) | 1 | 6/30/85 | NA |
| III.A.3.6( | 3S) tate and Local | J. Pittman | OIE/DEPER/ EPLB | NOTE 3(b) | 1 | 6/30/85 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.B | EMERGENCY PREPAREDNESS OF STATE AND LOCAL GOVERNMENTS | ||||||
| III.B.1 | Transfer of Responsibilities to FEMA | W. Milstead | OIE/DEPER/ IRDB | NOTE 3(b) | - | 11/30/83 | NA |
| III.B.2 | Implementation of NRC and FEMA Responsibilities | ||||||
| III.B.2(1) | The Licensing Process | W. Milstead | OIE/DEPER/ IRDB | NOTE 3(b) | - | 11/30/83 | NA |
| III.B.2(2) | Federal Guidance | W. Milstead | OIE/DEPER/ IRDB | NOTE 3(b) | - | 11/30/83 | NA |
| III.C | PUBLIC INFORMATION | ||||||
| III.C.1 | Have Information Available for the News Media and the Public | ||||||
| III.C.1(1) | Review Publicly Available Documents | J. Pittman | PA | LI (NOTE 3) | - | 11/30/83 | NA |
| III.C.1(2) | Recommend Publication of Additional Information | J. Pittman | PA | LI (NOTE 3) | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.C.1(3) | Program of Seminars for News Media Personnel | J. Pittman | PA | LI (NOTE 3) | - | 11/30/83 | NA |
| III.C.2 | Develop Policy and Provide Training for Interfacing with the News Media | ||||||
| III.C.2(1) | Develop Policy and Procedures for Dealing with Briefing Requests | J. Pittman | PA | LI (NOTE 3) | - | 11/30/83 | NA |
| III.C.2(2) | Provide Training for Members of the Technical Staff | J. Pittman | PA | LI (NOTE 3) | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.D | RADIATION PROTECTION | ||||||
| III.D.1 | Radiation Source Control | ||||||
| III.D.1.1 | Primary Coolant Sources Outside the Containment Structure | ||||||
| III.D.1.1( | 1R) eview Information Submitted by Licensees Pertaining to Reducing Leakage from Operating Systems | - | NRR | I | 1 | 12/31/88 | |
| III.D.1.1( | 2R) eview Information on Provisions for Leak Detection | R. Emrit | RES/DRA/ ARGIB | DROP | 1 | 12/31/88 | |
| III.D.1.1( | 3D) evelop Proposed System Acceptance Criteria | R. Emrit | RES/DRA/ ARGIB | DROP | 1 | 12/31/88 | |
| III.D.1.2 | Radioactive Gas Management | R. Emrit | NRR/DSI/ METB | DROP | 1 | 12/31/88 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.D.1.3 | Ventilation System and Radioiodine Adsorber Criteria | - | - | - | |||
| III.D.1.3( | 1D) ecide Whether Licensees Should Perform Studies and Make Modifications | R. Emrit | NRR/DSI/ METB | DROP | 1 | 12/31/88 | NA |
| III.D.1.3( | 2R) eview and Revise SRP | R. Emrit | NRR/DSI/ METB | DROP | 1 | 12/31/88 | NA |
| III.D.1.3( | 3R) equire Licensees to Upgrade Filtration Systems | R. Emrit | NRR/DSI/ METB | DROP | 1 | 12/31/88 | NA |
| III.D.1.3( | 4S) ponsor Studies to Evaluate Charcoal Adsorber | R. Emrit | NRR/DSI/ METB | NOTE 3(b) | 1 | 12/31/88 | NA |
| III.D.1.4 | Radwaste System Design Features to Aid in Accident Recovery and Decontamination | R. Emrit | NRR/DSI/ METB | DROP | 1 | 12/31/88 | NA |
| III.D.2 | Public Radiation Protection Improvement | ||||||
| III.D.2.1 | Radiological Monitoring of Effluents | ||||||
| III.D.2.1( | 1E) valuate the Feasibility and Perform a Value- Impact Analysis of Modifying Effluent- Monitoring Design Criteria | R. Emrit | NRR/DSI/ METB | DROP | 4 | 9/30/11 | NA |
| III.D.2.1( | 2S) tudy the Feasibility of Requiring the Development of Effective Means for Monitoring and Sampling Noble Gases and Radioiodine Released to the Atmosphere | R. Emrit | NRR/DSI/ METB | DROP | 4 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.D.2.1( | 3R) evise Regulatory Guides | R. Emrit | NRR/DSI/ METB | DROP | 4 | 9/30/11 | NA |
| III.D.2.2 | Radioiodine, Carbon-14, and Tritium Pathway Dose Analysis | ||||||
| III.D.2.2( | 1P) erform Study of Radioiodine, Carbon-14, and Tritium Behavior | R. Emrit | NRR/DSI/ RAB | NOTE 3(b) | 4 | 9/30/11 | NA |
| III.D.2.2( | 2E) valuate Data Collected at Quad Cities | R. Emrit | NRR/DSI/ RAB | III.D.2.5 | 4 | 9/30/11 | NA |
| III.D.2.2( | 3D) etermine the Distribution of the Chemical Species of Radioiodine in Air-Water-Steam Mixtures | R. Emrit | NRR/DSI/ RAB | III.D.2.5 | 4 | 9/30/11 | NA |
| III.D.2.2( | 4R) evise SRP and Regulatory Guides | R. Emrit | NRR/DSI/ RAB | III.D.2.5 | 4 | 9/30/11 | NA |
| III.D.2.3 | Liquid Pathway Radiological Control | ||||||
| III.D.2.3( | 1D) evelop Procedures to Discriminate Between Sites/Plants | R. Emrit | NRR/DE/ EHEB | NOTE 3(b) | 4 | 9/30/11 | NA |
| III.D.2.3( | 2D) iscriminate Between Sites and Plants That Require Consideration of Liquid Pathway Interdiction Techniques | R. Emrit | NRR/DE/ EHEB | NOTE 3(b) | 4 | 9/30/11 | NA |
| III.D.2.3( | 3E) stablish Feasible Method of Pathway Interdiction | R. Emrit | NRR/DE/ EHEB | NOTE 3(b) | 4 | 9/30/11 | NA |
| III.D.2.3( | 4P) repare a Summary Assessment | R. Emrit | NRR/DE/ EHEB | NOTE 3(b) | 4 | 9/30/11 | NA |
| III.D.2.4 | Offsite Dose Measurements | ||||||
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.D.2.4( | 1S) tudy Feasibility of Environmental Monitors | H. Vandermolen | NRR/DSI/ RAB | NOTE 3(b) | 4 | 9/30/11 | NA |
| III.D.2.4( | 2P) lace 50 TLDs Around Each Site | H. Vandermolen | OIE/DRP/ ORPB | LI (NOTE 3) | 4 | 9/30/11 | NA |
| III.D.2.5 | Offsite Dose Calculation Manual | H. Vandermolen | NRR/DSI/ RAB | NOTE 3(b) | 4 | 9/30/11 | NA |
| III.D.2.6 | Independent Radiological Measurements | H. Vandermolen | OIE/DRP/ ORPB | LI (NOTE 3) | 4 | 9/30/11 | NA |
| III.D.3 | Worker Radiation Protection Improvement | ||||||
| III.D.3.1 | Radiation Protection Plans | H. Vandermolen | NRR/DSI/ RAB | NOTE 3(b) | 3 | 12/31/87 | NA |
| III.D.3.2 | Health Physics Improvements | ||||||
| III.D.3.2( | 1A) mend 10 CFR 20 | H. Vandermolen | RES/DFO/ ORPBR | LI (NOTE 3) | 3 | 12/31/87 | NA |
| III.D.3.2( | 2I)ssue a Regulatory Guide | H. Vandermolen | RES/DFO/ ORPBR | LI (NOTE 3) | 3 | 12/31/87 | NA |
| III.D.3.2( | 3D) evelop Standard Performance Criteria | H. Vandermolen | RES/DFO/ ORPBR | LI (NOTE 3) | 3 | 12/31/87 | NA |
| III.D.3.2( | 4D) evelop Method for Testing and Certifying Air- Purifying Respirators | H. Vandermolen | RES/DFO/ ORPBR | LI (NOTE 3) | 3 | 12/31/87 | NA |
| III.D.3.3 | In-plant Radiation Monitoring | ||||||
| III.D.3.3( | 1I)ssue Letter Requiring Improved Radiation Sampling Instrumentation | - | NRR/DL | I | 2 | 12/31/86 | F-69 |
| III.D.3.3( | 2S) et Criteria Requiring Licensees to Evaluate Need for Additional Survey Equipment | - | NRR | NOTE 3(a) | 2 | 12/31/86 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| III.D.3.3( | 3I)ssue a Rule Change Providing Acceptable Methods for Calibration of Radiation-Monitoring Instruments | - | RES | NOTE 3(a) | 2 | 12/31/86 | NA |
| III.D.3.3( | 4I)ssue a Regulatory Guide | - | RES | NOTE 3(a) | 2 | 12/31/86 | NA |
| III.D.3.4 | Control Room Habitability | - | NRR/DL | I | 2 | 12/31/86 | F-70 |
| III.D.3.5 | Radiation Worker Exposure | ||||||
| III.D.3.5( | 1D) evelop Format for Data To Be Collected by Utilities Regarding Total Radiation Exposure to Workers | H. Vandermolen | DFO/ORPBR | LI (NOTE 3) | 2 | 12/31/86 | NA |
| III.D.3.5( | 2I)nvestigative Methods of Obtaining Employee Health Data by Nonlegislative Means | H. Vandermolen | DFO/ORPBR | LI (NOTE 3) | 2 | 12/31/86 | NA |
| III.D.3.5( | 3R) evise 10 CFR 20 | H. Vandermolen | DFO/ORPBR | LI (NOTE 3) | 2 | 12/31/86 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| IV.A | STRENGTHEN ENFORCEMENT PROCESS | ||||||
| IV.A.1 | Seek Legislative Authority | R. Emrit | GC | LI (NOTE 3) | - | 11/30/83 | NA |
| IV.A.2 | Revise Enforcement Policy | R. Emrit | OIE/ES | LI (NOTE 3) | - | 11/30/83 | NA |
| IV.B | ISSUANCE OF INSTRUCTIONS AND INFORMATION TO LICENSEES | ||||||
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| IV.B.1 | Revise Practices for Issuance of Instructions and Information to Licensees | R. Emrit | OIE/DEPER | LI (NOTE 3) | - | 11/30/83 | NA |
| IV.C | EXTEND LESSONS LEARNED TO LICENSED ACTIVITIES OTHER THAN POWER REACTORS | ||||||
| IV.C.1 | Extend Lessons Learned from TMI to Other NRC Programs | R. Emrit | NMSS/WM | NOTE 3(b) | - | 11/30/83 | NA |
| IV.D | NRC STAFF TRAINING | ||||||
| IV.D.1 | NRC Staff Training | R. Emrit | ADM/MDTS | LI (NOTE 3) | - | 11/30/83 | NA |
| IV.E | SAFETY DECISION-MAKING | ||||||
| IV.E.1 | Expand Research on Quantification of Safety Decisionmaking | R. Colmar | RES/DRA/ RABR | LI (NOTE 3) | 3 | 9/30/11 | NA |
| IV.E.2 | Plan for Early Resolution of Safety Issues | R. Emrit | NRR/DST/ SPEB | LI (NOTE 3) | 3 | 9/30/11 | NA |
| IV.E.3 | Plan for Resolving Issues at the CP Stage | R. Colmar | RES/DRA/ RABR | LI (NOTE 5) | 3 | 9/30/11 | NA |
| IV.E.4 | Resolve Generic Issues by Rulemaking | R. Colmar | RES/DRA/ RABR | LI (NOTE 3) | 3 | 9/30/11 | NA |
| IV.E.5 | Assess Currently Operating Reactors | P. Matthews | NRR/DL/ SEPB | NOTE 3(b) | 3 | 9/30/11 | NA |
| IV.F | FINANCIAL DISINCENTIVES TO SAFETY | ||||||
| IV.F.1 | Increased OIE Scrutiny of the Power-Ascension Test Program | D. Thatcher | OIE/DQASIP | NOTE 3(b) | 1 | 12/31/86 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| IV.F.2 | Evaluate the Impacts of Financial Disincentives to the Safety of Nuclear Power Plants | P. Matthews | SP | NOTE 3(b) | 1 | 12/31/86 | NA |
| IV.G | IMPROVE SAFETY RULEMAKING PROCEDURES | ||||||
| IV.G.1 | Develop a Public Agenda for Rulemaking | R. Emrit | ADM/RPB | LI (NOTE 3) | 1 | 12/31/86 | NA |
| IV.G.2 | Periodic and Systematic Reevaluation of Existing Rules | W. Milstead | RES/DRA/ RABR | LI (NOTE 3) | 1 | 12/31/86 | NA |
| IV.G.3 | Improve Rulemaking Procedures | W. Milstead | RES/DRA/ RABR | LI (NOTE 3) | 1 | 12/31/86 | NA |
| IV.G.4 | Study Alternatives for Improved Rulemaking Process | W. Milstead | RES/DRA/ RABR | LI (NOTE 3) | 1 | 12/31/86 | NA |
| IV.H | NRC PARTICIPATION IN THE RADIATION POLICY COUNCIL | ||||||
| IV.H.1 | NRC Participation in the Radiation Policy Council | G. Sege | RES/ DHSWM/ HEBR | LI (NOTE 3) | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| V.A | DEVELOPMENT OF SAFETY POLICY | ||||||
| V.A.1 | Develop NRC Policy Statement on Safety | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.B | POSSIBLE ELIMINATION OF NONSAFETY RESPONSIBILITIES | ||||||
| V.B.1 | Study and Recommend, as Appropriate, Elimination | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| of Nonsafety Responsibilities | |||||||
| V.C | ADVISORY COMMITTEES | ||||||
| V.C.1 | Strengthen the Role of Advisory Committee on Reactor Safeguards | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.C.2 | Study Need for Additional Advisory Committees | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.C.3 | Study the Need to Establish an Independent Nuclear Safety Board | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.D | LICENSING PROCESS | ||||||
| V.D.1 | Improve Public and Intervenor Participation in the Hearing Process | R. Emrit | GC | LI (NOTE 3) | 1 | 9/30/11 | NA |
| V.D.2 | Study Construction- during-Adjudication Rules | R. Emrit | GC | LI (NOTE 5) | 1 | 9/30/11 | NA |
| V.D.3 | Reexamine Commission Role in Adjudication | R. Emrit | GC | LI (NOTE 5) | 1 | 9/30/11 | NA |
| V.D.4 | Study the Reform of the Licensing Process | R. Emrit | GC | LI (NOTE 5) | 1 | 9/30/11 | NA |
| V.E | LEGISLATIVE NEEDS | ||||||
| V.E.1 | Study the Need for TMI-Related Legislation | R. Emrit | GC | LI (NOTE 5) | 1 | 9/30/11 | NA |
| V.F | ORGANIZATION AND MANAGEMENT | ||||||
| V.F.1 | Study NRC Top Management | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Structure and Process | |||||||
| V.F.2 | Reexamine Organization and Functions of the NRC Offices | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.F.3 | Revise Delegations of Authority to Staff | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.F.4 | Clarify and Strengthen the Respective Roles of Chairman, Commission, and Executive Director for Operations | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.F.5 | Authority to Delegate Emergency Response Functions to a Single Commissioner | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.G | CONSOLIDATION OF NRC LOCATIONS | ||||||
| V.G.1 | Achieve Single Location, Long-Term | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| V.G.2 | Achieve Single Location, Interim | R. Emrit | GC | LI (NOTE 3) | - | 12/31/86 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| TASK ACTION PLAN ITEMS | |||||||
| A-1 | Water Hammer (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | NA |
| A-2 | Asymmetric Blowdown Loads on Reactor Primary | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | D-10 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Coolant Systems (former USI) | |||||||
| A-3 | Westinghouse Steam Generator Tube Integrity (former USI) | R. Emrit | NRR/DEST/ EMTB | NOTE 3(a) | 1 | 12/31/88 | |
| A-4 | CE Steam Generator Tube Integrity (former USI) | R. Emrit | NRR/DEST/ EMTB | NOTE 3(a) | 1 | 12/31/88 | |
| A-5 | B&W Steam Generator Tube Integrity (former USI) | R. Emrit | NRR/DEST/ EMTB | NOTE 3(a) | 1 | 12/31/88 | |
| A-6 | Mark I Short-Term Program (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | |
| A-7 | Mark I Long-Term Program (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | D-01 |
| A-8 | Mark II Containment Pool Dynamic Loads Long-Term Program (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | NA |
| A-9 | ATWS (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | |
| A-10 | BWR Feedwater Nozzle Cracking (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | B-25 |
| A-11 | Reactor Vessel Materials Toughness (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | |
| A-12 | Fracture Toughness of Steam Generator and Reactor Coolant Pump Supports (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | NA |
| A-13 | Snubber Operability Assurance | R. Emrit | NRR/DE/ MEB | NOTE 3(a) | 1 | 6/30/91 | B-17, B-22 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| A-14 | Flaw Detection | P. Matthews | NRR/DE/ MTEB | DROP | - | 11/30/83 | NA |
| A-15 | Primary Coolant System Decontamination and Steam Generator Chemical Cleaning | J. Pittman | NRR/DE/ CHEB | NOTE 3(b) | - | 11/30/83 | NA |
| A-16 | Steam Effects on BWR Core Spray Distribution | R. Emrit | NRR/DSI/ CPB | NOTE 3(a) | - | 11/30/83 | D-12 |
| A-17 | Systems Interactions in Nuclear Power Plants (former USI) | R. Emrit | RES/DSIR/ EIB | NOTE 3(b) | 1 | 12/31/89 | NA |
| A-18 | Pipe Rupture Design Criteria | R. Emrit | NRR/DE/ MEB | DROP | - | 11/30/83 | NA |
| A-19 | Digital Computer Protection System | W. Milstead | RES/DSR/ HFB | LI (NOTE 5) | 3 | 9/30/11 | NA |
| A-20 | Impacts of the Coal Fuel Cycle | - | NRR/DE/ EHEB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| A-21 | Main Steamline Break Inside Containment Evaluation of Environmental Conditions for Equipment Qualification | H. Vandermolen | NRR/DSI/ CSB | DROP | 1 | 12/31/98 | NA |
| A-22 | PWR Main Steamline Break Core, Reactor Vessel, and Containment Building Response | H. Vandermolen | NRR/DSI/ CSB | DROP | - | 11/30/83 | NA |
| A-23 | Containment Leak Testing | P. Matthews | NRR/DSI/ CSB | RI (NOTE 5) | 1 | 9/30/11 | |
| A-24 | Qualification of Class 1E Safety-Related | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | B-60 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Equipment (former USI) | |||||||
| A-25 | Non-Safety Loads on Class 1E Power Sources | D. Thatcher | NRR/DSI/ PSB | NOTE 3(a) | - | 11/30/83 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| A-26 | Reactor Vessel Pressure Transient Protection (former (USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | B-04 |
| A-27 | Reload Applications | - | NRR/DSI/ CPB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| A-28 | Increase in Spent Fuel Pool Storage Capacity | R. Colmar | NRR/DE/ SGEB | NOTE 3(a) | - | 11/30/83 | |
| A-29 | Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage | R. Colmar | RES/DRPS/ RPSI | NOTE 3(b) | 1 | 12/31/89 | NA |
| A-30 | Adequacy of Safety- Related DC Power Supplies | G. Sege | NRR/DSI/ PSB | 128 | 1 | 12/31/86 | NA |
| A-31 | RHR Shutdown Requirements (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | |
| A-32 | Missile Effects | J. Pittman | NRR/DE/ MTEB | A-37, A-38, B-68 | - | 11/30/83 | NA |
| A-33 | NEPA Review of Accident Risks | - | NRR/DSI/ AEB | EI (NOTE 3) | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| A-34 | Instruments for Monitoring Radiation and Process Variables during Accidents | H. Vandermolen | NRR/DSI/ ICSB | II.F.3 | - | 11/30/83 | NA |
| A-35 | Adequacy of Offsite Power Systems | R. Emrit | NRR/DSI/ PSB | NOTE 3(a) | 1 | 12/31/94 | B-23 |
| A-36 | Control of Heavy Loads Near Spent Fuel (former USI) | R. Emrit | NRR/DSI/ GIB | NOTE 3(a) | 2 | 6/30/04 | C-10, C-15 |
| A-37 | Turbine Missiles | J. Pittman | NRR/DE/ MTEB | DROP | - | 11/30/83 | NA |
| A-38 | Tornado Missiles | G. Sege | NRR/DSI/ ASB | DROP | 3 | 6/30/00 | NA |
| A-39 | Determination of Safety Relief Valve Pool Dynamic Loads and Temperature Limits (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | |
| A-40 | Seismic Design Criteria (former USI) | R. Emrit | RES/DSIR/ EIB | NOTE 3(a) | 1 | 12/31/89 | NA |
| A-41 | Long-Term Seismic Program | L. Riani | NRR/DE/ MEB | NOTE 3(b) | 1 | 12/31/84 | NA |
| A-42 | Pipe Cracks in Boiling Water Reactors (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 6/30/85 | B-05 |
| A-43 | Containment Emergency Sump Performance (former USI) | R. Emrit | NRR/DST/ GIB | NOTE 3(a) | 1 | 12/31/87 | |
| A-44 | Station Blackout (former USI) | R. Emrit | RES/DRPS/ RPSI | NOTE 3(a) | 1 | 6/30/88 | |
| A-45 | Shutdown Decay Heat Removal Requirements (former USI) | R. Emrit | RES/DRPS/ RPSI | NOTE 3(b) | 1 | 12/31/88 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| A-46 | Seismic Qualification of Equipment in Operating Plants (former USI) | R. Emrit | NRR/DSRO/ EIB | NOTE 3(a) | 2 | 6/30/00 | |
| A-47 | Safety Implications of Control Systems (former USI) | R. Emrit | RES/DSIR/ EIB | NOTE 3(a) | 1 | 12/31/89 | |
| A-48 | Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment | R. Emrit | NRR/DSIR/ SAIB | NOTE 3(a) | 1 | 6/30/89 | |
| A-49 | Pressurized Thermal Shock (former USI) | R. Emrit | NRR/DSRO/ RSIB | NOTE 3(a) | 1 | 12/31/87 | A-21 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| B-1 | Environmental Technical Specifications | - | NRR/DE/ EHEB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-2 | Forecasting Electricity Demand | - | NRR | EI (NOTE 3) | - | 11/30/83 | NA |
| B-3 | Event Categorization | - | NRR/DSI/ RSB | LI (NOTE 3) | - | 11/30/83 | NA |
| B-4 | ECCS Reliability | R. Emrit | NRR/DSI/ RSB | II.E.3.2 | - | 11/30/83 | NA |
| B-5 | Ductility of Two-Way Slabs and Shells and Buckling Behavior of Steel Containments | D. Thatcher | RES/DE/EIB | NOTE 3(b) | 1 | 6/30/88 | NA |
| B-6 | Loads, Load Combinations, Stress Limits | J. Pittman | NRR/DSRO/ EIB | 119.1 | - | 12/31/87 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| B-7 | Secondary Accident Consequence Modeling | - | NRR/DSI/ AEB | LI (NOTE 3) | - | 11/30/83 | NA |
| B-8 | Locking Out of ECCS Power Operated Valves | R. Riggs | NRR/DSI/ RSB | DROP | 1 | 12/31/94 | NA |
| B-9 | Electrical Cable Penetrations of Containment | R. Emrit | NRR/DSI/ PSB | NOTE 3(b) | - | 11/30/83 | NA |
| B-10 | Behavior of BWR Mark III Containments | H. Vandermolen | NRR/DSI/ CSB | NOTE 3(a) | 1 | 12/31/84 | NA |
| B-11 | Subcompartment Standard Problems | - | NRR/DSI/ CSB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| B-12 | Containment Cooling Requirements (Non- LOCA) | R. Emrit | NRR/DSI/ CSB | NOTE 3(b) | 1 | 12/31/86 | NA |
| B-13 | Marviken Test Data Evaluation | - | NRR/DSI/ CSB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| B-14 | Study of Hydrogen Mixing Capability in Containment Post- LOCA | R. Emrit | NRR/DST/ GIB | A-48 | - | 11/30/83 | NA |
| B-15 | CONTEMPT Computer Code Maintenance | - | NRR/DSI/ CSB | LI (NOTE 3) | - | 11/30/83 | NA |
| B-16 | Protection against Postulated Piping Failures in Fluid Systems Outside Containment | R. Emrit | NRR/DE/ MEB | A-18 | - | 11/30/83 | NA |
| B-17 | Criteria for Safety- Related Operator Actions | W. Milstead | RES/DST/ CIHFB | NOTE 3(b) | 3 | 6/30/00 | |
| B-18 | Vortex Suppression Requirements for Containment Sumps | R. Emrit | NRR/DST/ GIB | A-43 | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| B-19 | Thermal-Hydraulic Stability | L. Riani | NRR/DSI/ CPB | NOTE 3(b) | - | 6/30/85 | NA |
| B-20 | Standard Problem Analysis | RES/DAE/ AMBR | LI (NOTE 5) | - | 9/30/11 | NA | |
| B-21 | Core Physics | - | NRR/DSI/ CPB | LI (NOTE 3) | - | 11/30/83 | NA |
| B-22 | LWR Fuel | R. Emrit | RES/DSIR/ RPSIB | DROP | 2 | 6/30/95 | NA |
| B-23 | LMFBR Fuel | - | NRR/DSI/ CPB | LI (NOTE 3) | - | 11/30/83 | NA |
| B-24 | Seismic Qualification of Electrical and Mechanical Equipment | R. Emrit | NRR | A-46 | - | 11/30/83 | NA |
| B-25 | Piping Benchmark Problems | NRR/DE/ MEB | LI (NOTE 5) | 1/1/00 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| B-26 | Structural Integrity of Containment Penetrations | R. Riggs | NRR/DE/ MTEB | NOTE 3(b) | 1 | 12/31/84 | NA |
| B-27 | Implementation and Use of Subsection NF | - | NRR/DE/ MEB | LI (NOTE 5) | 1 | 9/30/11 | |
| B-28 | Radionuclide/ Sediment Transport Program | - | NRR/DE/ EHEB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-29 | Effectiveness of Ultimate Heat Sinks | J. Pittman | NRR/DE/ EHEB | LI (NOTE 3) | 1 | 6/30/91 | NA |
| B-30 | Design Basis Floods and Probability | - | NRR/DE/ EHEB | LI (NOTE 5) | 1 | 9/30/11 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| B-31 | Dam Failure Model | W. Milstead | NRR/DE/ SGEB | LI (NOTE 3) | 1 | 6/30/89 | NA |
| B-32 | Ice Effects on Safety- Related Water Supplies | J. Pittman | NRR/DE/ EHEB | 153 | 1 | 6/30/91 | NA |
| B-33 | Dose Assessment Methodology | - | NRR/DSI/ RAB | LI (NOTE 3) | - | 11/30/83 | NA |
| B-34 | Occupational Radiation Exposure Reduction | R. Emrit | NRR/DSI/ RAB | III.D.3.1 | - | 11/30/83 | NA |
| B-35 | Confirmation of Appendix I Models for Calculations of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors | - | NRR/DSI/ METB | LI (NOTE 5) | 1 | 9/30/11 | |
| B-36 | Develop Design, Testing, and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Feature Systems and for Normal Ventilation Systems | R. Emrit | NRR/DSI/ METB | NOTE 3(a) | - | 11/30/83 | |
| B-37 | Chemical Discharges to Receiving Waters | - | NRR/DE/ EHEB | EI (NOTE 3) | 1 | 9/30/14 | NA |
| B-38 | Reconnaissance- Level Investigations | - | NRR/DE/ EHEB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-39 | Transmission Lines | - | NRR/DE/ EHEB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-40 | Effects of Power Plant Entrainment on Plankton | - | NRR/DE/ EHEB | EI (NOTE 3) | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| B-41 | Impacts on Fisheries | - | NRR/DE/ EHEB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-42 | Socioeconomic Environmental Impacts | - | NRR/DE/SAB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-43 | Value of Aerial Photographs for Site Evaluation | - | NRR/DE/ EHEB | EI (NOTE 3) | 1 | 9/30/14 | NA |
| B-44 | Forecasts of Generating Costs of Coal and Nuclear Plants | - | NRR/DE/SAB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-45 | Need for Power Energy Conservation | - | NRR/DE/SAB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-46 | Cost of Alternatives in Environmental Design | - | NRR/DE/SAB | EI (NOTE 3) | - | 11/30/83 | NA |
| B-47 | Inservice Inspection of Supports Classes 1, 2, 3, and MC Components | L. Riani | NRR/DE/ MTEB | DROP | - | 11/30/83 | NA |
| B-48 | BWR Control Rod Drive Mechanical Failures | R. Emrit | NRR/DE/ MTEB | NOTE 3(b) | - | 11/30/83 | |
| B-49 | Inservice Inspection Criteria and Corrosion Prevention Criteria for Containments | - | NRR | LI (NOTE 5) | 1 | 9/30/11 | |
| B-50 | Post-Operating Basis Earthquake Inspection | L. Riani | NRR/DE/ SGEB | RI (NOTE 3) | 1 | 6/30/85 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| B-51 | Assessment of Inelastic Analysis Techniques for Equipment and Components | R. Emrit | NRR/DE/MEB | A-40 | - | 11/30/83 | NA |
| B-52 | Fuel Assembly Seismic and LOCA Responses | R. Emrit | NRR/DST/ GIB | A-2 | - | 11/30/83 | NA |
| B-53 | Load Break Switch | G. Sege | NRR/DSI/ PSB | RI (NOTE 3) | - | 11/30/83 | |
| B-54 | Ice Condenser Containments | W. Milstead | NRR/DSI/ CSB | NOTE 3(b) | 1 | 12/31/84 | NA |
| B-55 | Improved Reliability of Target Rock Safety Relief Valves | H. Vandermolen | NRR/DE/ EMEB | NOTE 3(b) | 1 | 6/30/00 | |
| B-56 | Diesel Reliability | W. Milstead | RES/DRPS/ RPSI | NOTE 3(a) | 2 | 6/30/95 | D-19 |
| B-57 | Station Blackout | R. Emrit | NRR/DST/ GIB | A-44 | - | 11/30/83 | |
| B-58 | Passive Mechanical Failures | L. Riani | NRR/DE/EQB | NOTE 3(b) | 1 | 12/31/85 | NA |
| B-59 | (N-1) Loop Operation in BWRs and PWRs | L. Riani | NRR/DSI/ RSB | RI (NOTE 3) | 1 | 6/30/85 | E-04, E-05 |
| B-60 | Loose Parts Monitoring Systems | R. Emrit | NRR/DSI/ CPB | NOTE 3(b) | 1 | 12/31/84 | NA |
| B-61 | Allowable ECCS Equipment Outage Periods | J. Pittman | RES/DST/ PRAB | NOTE 3(b) | 1 | 6/30/00 | |
| B-62 | Reexamination of Technical Bases for Establishing SLs, LSSSs, and Reactor Protection System Trip Functions | - | NRR/DSI/ CPB | LI (NOTE 3) | - | 11/30/83 | NA |
| B-63 | Isolation of Low- Pressure Systems | R. Emrit | NRR/DE/MEB | NOTE 3(a) | - | 11/30/83 | B-45 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Connected to the Reactor Coolant Pressure Boundary | |||||||
| B-64 | Decommissioning of Reactors | L. Riani | RES/DE/MEB | NOTE 3(a) | 2 | 6/30/95 | NA |
| B-65 | Iodine Spiking | W. Milstead | NRR/DSI/ AEB | DROP | 2 | 12/31/84 | NA |
| B-66 | Control Room Infiltration Measurements | P. Matthews | NRR/DSI/ AEB | NOTE 3(a) | - | 11/30/83 | |
| B-67 | Effluent and Process Monitoring Instrumentation | L. Riani | NRR/DSI/ METB | III.D.2.1 | - | 11/30/83 | NA |
| B-68 | Pump Overspeed during LOCA | L. Riani | NRR/DSI/ ASB | DROP | - | 11/30/83 | NA |
| B-69 | ECCS Leakage Ex- Containment | L. Riani | NRR/DSI/ METB | III.D.1.1(1) | - | 11/30/83 | NA |
| B-70 | Power Grid Frequency Degradation and Effect on Primary Coolant Pumps | R. Emrit | NRR/DSI/ PSB | NOTE 3(b) | - | 11/30/83 | |
| B-71 | Incident Response | L. Riani | NRR | III.A.3.1 | - | 11/30/83 | NA |
| B-72 | Health Effects and Life Shortening from Uranium and Coal Fuel Cycles | - | NRR/DSI/ RAB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| B-73 | Monitoring for Excessive Vibration Inside the Reactor Pressure Vessel | D. Thatcher | NRR/DE/MEB | C-12 | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| C-1 | Assurance of Continuous Long- Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment | W. Milstead | NRR/DE/EQB | NOTE 3(a) | - | 11/30/83 | |
| C-2 | Study of Containment Depressurization by Inadvertent Spray Operation to Determine Adequacy of Containment External Design Pressure | R. Emrit | NRR/DSI/ CSB | NOTE 3(b) | - | 11/30/83 | NA |
| C-3 | Insulation Usage within Containment | R. Emrit | NRR/DST/ GIB | A-43 | 1 | 6/30/91 | NA |
| C-4 | Statistical Methods for ECCS Analysis | R. Riggs | NRR/DSRO/ SPEB | RI (NOTE 3) | 1 | 6/30/86 | NA |
| C-5 | Decay Heat Update | R. Riggs | NRR/DSRO/ SPEB | RI (NOTE 3) | 1 | 6/30/86 | NA |
| C-6 | LOCA Heat Sources | R. Riggs | NRR/DSRO/ SPEB | RI (NOTE 3) | 1 | 6/30/86 | NA |
| C-7 | PWR System Piping | R. Emrit | NRR/DE/ MTEB | NOTE 3(b) | - | 11/30/83 | NA |
| C-8 | Main Steam Line Leakage Control Systems | W. Milstead | RES/DRPS/ RPSI | NOTE 3(b) | 1 | 6/30/90 | NA |
| C-9 | RHR Heat Exchanger Tube Failures | H. Vandermolen | NRR/DSI/ RSB | DROP | - | 11/30/83 | NA |
| C-10 | Effective Operation of Containment Sprays in a LOCA | R. Emrit | NRR/DSI/ AEB | NOTE 3(a) | - | 11/30/83 | NA |
| C-11 | Assessment of Failure and Reliability of Pumps and Valves | R. Emrit | NRR/DE/MEB | NOTE 3(b) | - | 12/31/85 | NA |
| C-12 | Primary System Vibration Assessment | D. Thatcher | NRR/DE/MEB | NOTE 3(b) | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| C-13 | Non-Random Failures | R. Emrit | NRR/DST/ GIB | A-17 | 1 | 6/30/91 | NA |
| C-14 | Storm Surge Model for Coastal Sites | R. Emrit | NRR/DE/ EHEB | LI (NOTE 3) | 2 | 9/30/11 | NA |
| C-15 | NUREG Report for Liquid Tank Failure Analysis | - | NRR/DE/ EHEB | LI (NOTE 3) | - | 11/30/83 | NA |
| C-16 | Assessment of Agricultural Land in Relation to Power Plant Siting and Cooling System Selection | - | NRR/DE/ EHEB | EI (NOTE 3) | - | 11/30/83 | NA |
| C-17 | Interim Acceptance Criteria for Solidification Agents for Radioactive Solid Wastes | R. Emrit | NRR/DSI/ METB | NOTE 3(a) | - | 11/30/83 | NA |
| D-1 | Advisability of a Seismic Scram | D. Thatcher | RES/DET/ MSEB | DROP | 1 | 12/31/98 | NA |
| D-2 | Emergency Core Cooling System Capability for Future Plants | R. Emrit | RES/DRA/ ARGIB | DROP | - | 12/31/88 | NA |
| D-3 | Control Rod Drop Accident | R. Emrit | NRR/DSI/ CPB | NOTE 3(b) | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| NEW GENERIC ISSUES | |||||||
| 1 | Failures in Air- Monitoring, Air- Cleaning, and Ventilating Systems | R. Emrit | NRR/DSI/ METB | DROP | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 2 | Failure of Protective Devices on Essential Equipment | S. Diab | RES/DSIR/ EIB | DROP | 2 | 6/30/95 | NA |
| 3 | Set Point Drift in Instrumentation | R. Emrit | NRR/DSIR/ RPSIB | NOTE 3(b) | 1 | 6/30/86 | NA |
| 4 | End-of-Life and Maintenance Criteria | D. Thatcher | NRR/DE/EQB | NOTE 3(b) | - | 11/30/83 | NA |
| 5 | Design Check and Audit of Balance-of- Plant Equipment | J. Pittman | NRR/DSI/ ASB | I.F.1 | - | 11/30/83 | NA |
| 6 | Separation of Control Rod from Its Drive and BWR High Rod Worth Events | H. Vandermolen | NRR/DSI/ CPB | NOTE 3(b) | 1 | 12/31/94 | NA |
| 7 | Failures Due to Flow- Induced Vibrations | H. Vandermolen | NRR/DSI/ RSB | DROP | 1 | 6/30/91 | NA |
| 8 | Inadvertent Actuation of Safety Injection in PWRs | L. Riani | NRR/DSI/ RSB | I.C.1 | - | 11/30/83 | NA |
| 9 | Reevaluation of Reactor Coolant Pump Trip Criteria | R. Emrit | NRR/DSI/ RSB | II.K.3(5) | - | 11/30/83 | NA |
| 10 | Surveillance and Maintenance of TIP Isolation Valves and Squib Charges | R. Riggs | NRR/DSI/ ICSB | DROP | - | 11/30/83 | NA |
| 11 | Turbine Disc Cracking | J. Pittman | NRR/DE/ MTEB | A-37 | - | 11/30/83 | NA |
| 12 | BWR Jet Pump Integrity | G. Sege | NRR/DE/ MTEB, MEB | NOTE 3(b) | 1 | 12/31/84 | NA |
| 13 | Small-Break LOCA from Extended Overheating of Pressurizer Heaters | L. Riani | NRR/DSI/ RSB | DROP | - | 11/30/83 | NA |
| 14 | PWR Pipe Cracks | R. Emrit | NRR/DE/ MTEB | NOTE 3(b) | 2 | 12/31/94 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 15 | Radiation Effects on Reactor Vessel Supports | R. Emrit | RES/DET/ EMMEB | NOTE 3(b) | 3 | 6/30/96 | NA |
| 16 | BWR Main Steam Isolation Valve Leakage Control Systems | W. Milstead | NRR/DSI/ ASB | C-8 | - | 11/30/83 | NA |
| 17 | Loss of Offsite Power Subsequent to a LOCA | L. Riani | NRR/DSI/ PSB, ICSB | DROP | - | 11/30/83 | NA |
| 18 | Steam Line Break with Consequential Small LOCA | R. Riggs | NRR/DSI/ RSB | I.C.1 | - | 11/30/83 | NA |
| 19 | Safety Implications of Nonsafety Instrument and Control Power Supply Bus | G. Sege | NRR/DST/ GIB | A-47 | - | 11/30/83 | NA |
| 20 | Effects of Electromagnetic Pulse on Nuclear Power Plants | D. Thatcher | NRR/DSI/ ICSB | NOTE 3(b) | 1 | 6/30/84 | NA |
| 21 | Vibration Qualification of Equipment | R. Riggs | NRR/DE/EIB | DROP | 2 | 6/30/91 | NA |
| 22 | Inadvertent Boron Dilution Events | H. Vandermolen | NRR/DSI/ RSB | NOTE 3(b) | 2 | 12/31/94 | NA |
| 23 | Reactor Coolant Pump Seal Failures | R. Riggs | RES/DET/ GSIB | NOTE 3(b) | 1 | 6/30/00 | NA |
| 24 | Automatic ECCS Switchover to Recirculation | W. Milstead | RES/DET/ GSIB | NOTE 3(b) | 3 | 12/31/95 | NA |
| 25 | Automatic Air Header Dump on BWR Scram System | W. Milstead | NRR/DSI/ RSB | NOTE 3(a) | - | 11/30/83 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 26 | Diesel Generator Loading Problems Related to SIS Reset on Loss of Offsite Power | R. Emrit | NRR/DSI/ASB | 17 | - | 11/30/83 | NA |
| 27 | Manual vs. Automated Actions | J. Pittman | NRR/DSI/RSB | B-17 | - | 11/30/83 | NA |
| 28 | Pressurized Thermal Shock | R. Emrit | NRR/DST/GIB | A-49 | - | 11/30/83 | NA |
| 29 | Bolting Degradation or Failure in Nuclear Power Plants | H. Vandermolen | RES/DSIR/ EIB | NOTE 3(b) | 2 | 6/30/95 | NA |
| 30 | Potential Generator MissilesGenerator Rotor Retaining Rings | J. Pittman | NRR/DE/MEB | DROP | 1 | 12/31/85 | NA |
| 31 | Natural Circulation Cooldown | R. Riggs | NRR/DSI/RSB | I.C.1 | - | 11/30/83 | NA |
| 32 | Flow Blockage in Essential Equipment Caused by Corbicula | R. Emrit | NRR/DSI/ASB | 51 | - | 11/30/83 | NA |
| 33 | Correcting Atmospheric Dump Valve Opening Upon Loss of Integrated Control System Power | J. Pittman | NRR/DSI/ ICSB | A-47 | - | 11/30/83 | NA |
| 34 | RCS Leak | R. Riggs | NRR/DHFS/ PSRB | DROP | 1 | 6/30/84 | NA |
| 35 | Degradation of Internal Appurtenances in LWRs | H. Vandermolen | NRR/DSI/ CPB, RSB | DROP | 2 | 12/31/98 | NA |
| 36 | Loss of Service Water | L. Riani | NRR/DSI/ ASB, AEB, RSB | NOTE 3(b) | 3 | 6/30/91 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 37 | Steam Generator Overfill and Combined Primary and Secondary Blowdown | L. Riani | NRR/DST/ GIB, NRR/ DSI/RSB | A-47, I.C.1(2) | 1 | 6/30/85 | NA |
| 38 | Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris | R. Emrit | RES/DSIR/ RPSIB | DROP | 2 | 6/30/95 | NA |
| 39 | Potential for Unacceptable Interaction between the CRD System and Non-Essential Control Air System | J. Pittman | NRR/DSI/ASB | 25 | 1 | 6/30/95 | NA |
| 40 | Safety Concerns Associated with Pipe Breaks in the BWR Scram System | L. Riani | NRR/DSI/ASB | NOTE 3(a) | 1 | 6/30/84 | B-65 |
| 41 | BWR Scram Discharge Volume Systems | H. Vandermolen | NRR/DSI/RSB | NOTE 3(a) | - | 11/30/83 | B-58 |
| 42 | Combination Primary/ Secondary System LOCA | R. Riggs | NRR/DSI/RSB | I.C.1 | 1 | 6/30/85 | NA |
| 43 | Reliability of Air Systems | W. Milstead | RES/DSIR/ RPSI | NOTE 3(a) | 2 | 12/31/88 | B-107 |
| 44 | Failure of Saltwater Cooling System | W. Milstead | NRR/DSI/ASB | 43 | 1 | 12/31/88 | NA |
| 45 | Inoperability of Instrumentation Due to Extreme Cold Weather | W. Milstead | NRR/DSI/ ICSB | NOTE 3(a) | 2 | 6/30/91 | |
| 46 | Loss of 125 Volt DC Bus | G. Sege | NRR/DSI/PSB | 76 | - | 11/30/83 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 47 | Loss of Offsite Power | D. Thatcher | NRR/DSI/ RSB, ASB | NOTE 3(b) | - | 11/30/83 | |
| 48 | LCO for Class 1E Vital Instrument Buses in Operating Reactors | G. Sege | NRR/DSI/PSB | 128 | 1 | 12/31/86 | NA |
| 49 | Interlocks and LCOs for Redundant Class 1E Tie-Breakers | G. Sege | NRR/DSI/PSB | 128 | 3 | 6/30/91 | NA |
| 50 | Reactor Vessel Level Instrumentation in BWRs | D. Thatcher | NRR/DSI/ RSB, ICSB | NOTE 3(b) | 1 | 12/31/84 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 51 | Proposed Requirements for Improving the Reliability of Open Cycle Service Water Systems | R. Emrit | RES/DE/EIB | NOTE 3(a) | 1 | 12/31/89 | L-913 |
| 52 | SSW Flow Blockage by Blue Mussels | R. Emrit | NRR/DSI/ASB | 51 | - | 11/30/83 | NA |
| 53 | Consequences of a Postulated Flow Blockage Incident in a BWR | H. Vandermolen | NRR/DSI/ CPB, RSB | DROP | 1 | 12/31/84 | NA |
| 54 | Valve Operator- Related Events Occurring during 1978, 1979, and 1980 | L. Riani | NRR/DE/MEB | II.E.6.1 | 1 | 6/30/85 | NA |
| 55 | Failure of Class 1E Safety-Related Switchgear Circuit | R. Emrit | NRR/DSI/PSB | DROP | 2 | 6/30/91 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Breakers to Close on Demand | |||||||
| 56 | Abnormal Transient Operating Guidelines as Applied to a Steam Generator Overfill Event | L. Riani | NRR/DHFS/ HFEB | A-47, I.D.1 | - | 11/30/83 | NA |
| 57 | Effects of Fire Protection System Actuation on Safety- Related Equipment | W. Milstead | RES/DRA/ ARGIB | NOTE 3(b) | 3 | 6/30/95 | NA |
| 58 | Inadvertent Containment Flooding | G. Sege | NRR/DSI/ ASB, CSB | DROP | - | 11/30/83 | |
| 59 | Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown is Degraded or Inoperable | R. Emrit | NRR/DST/ TSIP | RI (NOTE 5) | 2 | 9/30/11 | NA |
| 60 | Lamellar Tearing of Reactor Systems Structural Supports | L. Riani | NRR/DST/ GIB | A-12 | - | 11/30/83 | NA |
| 61 | SRV Line Break Inside the BWR Wetwell Airspace of Mark I and II Containments | W. Milstead | NRR/DSI/ CSB | NOTE 3(b) | 2 | 12/31/86 | NA |
| 62 | Reactor Systems Bolting Applications | R. Riggs | RES/DSIR/ EIB | 29 | 1 | 12/31/88 | NA |
| 63 | Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis | J. Pittman | RES/DRA/ ARGIB | DROP | 1 | 6/30/90 | NA |
| 64 | Identification of Protection System | D. Thatcher | NRR/DSI/ ICSB | NOTE 3(b) | - | 11/30/83 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Instrument Sensing Lines | |||||||
| 65 | Probability of Core-Melt Due to Component Cooling Water System Failures | H. Vandermolen | NRR/DSI/ASB | 23 | 1 | 12/31/86 | NA |
| 66 | Steam Generator Requirements | R. Riggs | NRR/DEST/ EMTB | NOTE 3(b) | 2 | 12/31/88 | NA |
| 67 | Steam Generator Staff Actions | ||||||
| 67.2.1 | Integrity of Steam Generator Tube Sleeves | R. Riggs | NRR/DE/MEB | 135 | 5 | 9/30/11 | NA |
| 67.3.1 | Steam Generator Overfill | R. Riggs | NRR/DST/ GIB, NRR/ DSI/RSB | A-47, I.C.1 | 5 | 9/30/11 | NA |
| 67.3.2 | Pressurized Thermal Shock | R. Riggs | NRR/DST/ GIB | A-49 | 5 | 9/30/11 | NA |
| 67.3.3 | Improved Accident Monitoring | R. Riggs | NRR/DSI/ ICSB | NOTE 3(a) | 5 | 9/30/11 | A-17 |
| 67.3.4 | Reactor Vessel Inventory Measurement | R. Riggs | NRR/DSI/ CPB | II.F.2 | 5 | 9/30/11 | NA |
| 67.4.1 | RCP Trip | R. Riggs | NRR/DSI/ RSB | II.K.3(5) | 5 | 9/30/11 | G-01 |
| 67.4.2 | Control Room Design Review | R. Riggs | NRR/DHFS/ HFEB | I.D.1 | 5 | 9/30/11 | F-08 |
| 67.4.3 | Emergency Operating Procedures | R. Riggs | NRC/DHFS/ PSRB | I.C.1 | 5 | 9/30/11 | F-05 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 67.5.1 | Reassessment of Radiological Consequences | R. Riggs | RES/DRPS/ RPSI | LI (NOTE 3) | 5 | 9/30/11 | NA |
| 67.5.2 | Reevaluation of SGTR Design Basis | R. Riggs | RES/DRPS/ RPSI | LI (67.5.1) | 5 | 9/30/11 | NA |
| 67.5.3 | Secondary System Isolation | R. Riggs | NRR/DSI/ RSB | DROP | 5 | 9/30/11 | NA |
| 67.6.0 | Organizational Responses | R. Riggs | OIE/DEPER/ IRDB | III.A.3 | 5 | 9/30/11 | NA |
| 67.7.0 | Improved Eddy Current Tests | R. Riggs | RES/DE/EIB | 135 | 5 | 9/30/11 | NA |
| 67.8.0 | Denting Criteria | R. Riggs | NRR/DE/ MTEB | 135 | 5 | 9/30/11 | NA |
| 67.9.0 | Reactor Coolant System Pressure Control | R. Riggs | NRR/DSI/GIB, NRR/DSI/ RSB | A-45, I.C.1 (2,3) | 5 | 9/30/11 | NA |
| 67.10.0 | Supplemental Tube Inspections | R. Riggs | NRR/DL/ ORAB | LI (NOTE 5) | 5 | 9/30/11 | NA |
| 68 | Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture | J. Pittman | NRR/DSI/ASB | 124 | 3 | 6/30/91 | NA |
| 69 | Make-up Nozzle Cracking in B&W Plants | R. Colmar | NRR/DE/ MEB, MTEB | NOTE 3(b) | 1 | 12/31/84 | B43 |
| 70 | PORV and Block Valve Reliability | R. Riggs | RES/DE/EIB | NOTE 3(a) | 3 | 6/30/91 | |
| 71 | Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety | J. Pittman | RES/DRA/ ARGIB | DROP | 3 | 6/30/01 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 72 | Control Rod Drive Guide Tube Support Pin Failures | R. Riggs | RES | DROP | 1 | 6/30/91 | NA |
| 73 | Detached Thermal Sleeves | R. Emrit | RES/DSIR/ EIB | NOTE 3(a) | 3 | 6/30/95 | NA |
| 74 | Reactor Coolant Activity Limits for Operating Reactors | W. Milstead | NRR/DSI/AEB | DROP | 1 | 6/30/86 | NA |
| 75 | Generic Implications of ATWS Events at the Salem Nuclear Plant | R. Emrit | RES/DRA/ ARGIB | NOTE 3(a) | 1 | 6/30/90 | B-76, B-77, B-78, B-79, B-80, B-81, B-82, B-85 B-86, B-87, B-88, B-89, B-90, B-91, B-92, B-93 |
| 76 | Instrumentation and Control Power Interactions | R. Zimmerman | RES/DSIR/ EIB | DROP | 3 | 6/30/95 | NA |
| 77 | Flooding of Safety Equipment Compartments by Backflow Through Floor Drains | L. Riani | RES/DE/EIB | A-17 | - | 12/31/87 | NA |
| 78 | Monitoring of Fatigue Transient Limits for Reactor Coolant System | C. Rourk | RES/DET/ GSIB | NOTE 3(b) | 3 | 12/31/97 | |
| 79 | Unanalyzed Reactor Vessel Thermal Stress during Natural Convection Cooldown | L. Riani | RES/DSIR/ EIB | NOTE 3(b) | 3 | 6/30/95 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 80 | Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments | H. Vandermolen | RES/DSARE/ REAHFB | NOTE 3(b) | 4 | 6/30/06 | NA |
| 81 | Impact of Locked Doors and Barriers on Plant and Personnel Safety | C. Rourk | RES/DSIR/ EIB | DROP | 5 | 9/30/11 | NA |
| 82 | Beyond Design-Basis Accidents in Spent Fuel Pools | H. Vandermolen | RES/DRPS/ RPSI | NOTE 3(b) | 3 | 6/30/04 | NA |
| 83 | Control Room Habitability | R. Emrit | RES/DST/ AEB | NOTE 3(b) | 3 | 6/30/03 | NA |
| 84 | CE PORVs | R. Riggs | RES/DSIR/ RPSI | NOTE 3(b) | 2 | 6/30/90 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 85 | Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments | W. Milstead | NRR/DSI/ CSB | DROP | 2 | 6/30/91 | NA |
| 86 | Long-Range Plan for Dealing with Stress- Corrosion Cracking in BWR Piping | R. Emrit | NRR/DEST/ EMTB | NOTE 3(a) | 1 | 6/30/88 | B-84 |
| 87 | Failure of HPCI Steam Line without Isolation | J. Pittman | RES/DSIR/ EIB | NOTE 3(a) | 2 | 6/30/95 | |
| 88 | Earthquakes and Emergency Planning | R. Riggs | RES/DRA/ ARGIB | NOTE 3(b) | 12/31/87 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 89 | Stiff Pipe Clamps | T.Y. Chang | RES/DSIR/ EIB | MEDIUM | 2 | 6/30/95 | NA |
| 90 | Technical Specifications for Anticipatory Trips | H. Vandermolen | NRR/DSI/ RSB, ICSB | DROP | 2 | 12/31/98 | NA |
| 91 | Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators | R. Emrit | RES/DRA/ ARGIB | NOTE 3(b) | - | 12/31/87 | NA |
| 92 | Fuel Crumbling during LOCA | H. Vandermolen | NRR/DSI/ RSB, CPB | DROP | 1 | 12/31/98 | NA |
| 93 | Steam Binding of Auxiliary Feedwater Pumps | J. Pittman | RES/DRPS/ RPSI | NOTE 3(a) | - | 6/30/88 | B-98 |
| 94 | Additional Low Temperature Overpressure Protection for Light- Water Reactors | J. Pittman | RES/DSIR/ RPSI | NOTE 3(a) | - | 6/30/90 | |
| 95 | Loss of Effective Volume for Containment Recirculation Spray | W. Milstead | RES/DRA/ ARGIB | NOTE 3(b) | - | 6/30/90 | NA |
| 96 | RHR Suction Valve Testing | W. Milstead | RES/DRA/ ARGIB | 105 | - | 6/30/90 | NA |
| 97 | PWR Reactor Cavity Uncontrolled Exposures | H. Vandermolen | NRR/DSI/ RAB | III.D.3.1 | - | 6/30/85 | NA |
| 98 | CRD Accumulator Check Valve Leakage | J. Pittman | NRR/DSI/ASB | DROP | - | 6/30/85 | NA |
| 99 | RCS/RHR Suction Line Valve Interlock on PWRs | J. Pittman | RES/DRPS/ RPSI | NOTE 3(a) | 3 | 6/30/91 | L-817 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 100 | Once-Through Steam Generator Level | J. Jackson | RES/DSIR/ EIB | DROP | 1 | 6/30/95 | NA |
| 101 | BWR Water Level Redundancy | H. Vandermolen | RES/DE/EIB | NOTE 3(b) | 1 | 6/30/89 | NA |
| 102 | Human Error in Events Involving Wrong Unit or Wrong Train | R. Emrit | NRR/DLPQ/ LPEB | NOTE 3(b) | 2 | 12/31/88 | NA |
| 103 | Design for Probable Maximum Precipitation | R. Emrit | RES/DE/EIB | NOTE 3(a) | 1 | 12/31/89 | NA |
| 104 | Reduction of Boron Dilution Requirements | J. Pittman | RES/DRA/ ARGIB | DROP | - | 12/31/88 | NA |
| 105 | Interfacing Systems LOCA at LWRs | W. Milstead | RES/DE/EIB | NOTE 3(b) | 4 | 6/30/95 | NA |
| 106 | Piping and Use of Highly Combustible Gases in Vital Areas | W. Milstead | RES/DRPS | NOTE 3(b) | 2 | 6/30/95 | NA |
| 107 | Main Transformer Failures | W. Milstead | RES/DRA/ ARGIB | DROP | 3 | 6/30/00 | NA |
| 108 | BWR Suppression Pool Temperature Limits | L. Riani | NRR/DSI/ CSB | RI (NOTE 3) | - | 6/30/85 | NA |
| 109 | Reactor Vessel Closure Failure | R. Riggs | RES/DRA/ ARGIB | DROP | - | 6/30/90 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 110 | Equipment Protective Devices on Engineered Safety Features | S. Diab | RES/DSIR/ EIB | DROP | 1 | 6/30/95 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 111 | Stress-Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments | R. Riggs | NRR/DE/ MTEB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| 112 | Westinghouse RPS Surveillance Frequencies and Out-of-Service Times | J. Pittman | NRR/DSI/ ICSB | RI (NOTE 3) | - | 12/31/85 | NA |
| 113 | Dynamic Qualification Testing of Large Bore Hydraulic Snubbers | R. Riggs | RES/DSIR/ EIB | NOTE 3(b) | 2 | 6/30/95 | NA |
| 114 | Seismic-Induced Relay Chatter | R. Riggs | NRR/DSRO/ SPEB | A-46 | 1 | 6/30/91 | NA |
| 115 | Enhancement of the Reliability of Westinghouse Solid State Protection System | W. Milstead | RES/DRPS/ RPSI | NOTE 3(b) | 2 | 6/30/00 | NA |
| 116 | Accident Management | J. Pittman | RES/DRA/ ARGIB | S | - | 6/30/91 | NA |
| 117 | Allowable Time for Diverse Simultaneous Equipment Outages | J. Pittman | RES/DRA/ ARGIB | DROP | - | 6/30/90 | NA |
| 118 | Tendon Anchorage Failure | S. Shaukat | RES/DSIR/ EIB | NOTE 3(a) | 1 | 6/30/95 | NA |
| 119 | Piping Review Committee Recommendations | ||||||
| 119.1 | Piping Rupture Requirements and Decoupling of Seismic and LOCA Loads | R. Riggs | NRR/DE | RI (NOTE 3) | 4 | 9/30/11 | NA |
| 119.2 | Piping Damping Values | R. Riggs | NRR/DE | RI (DROP) | 4 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 119.3 | Decoupling the OBE from the SSE | R. Riggs | NRR/DE | RI (S) | 4 | 9/30/11 | NA |
| 119.4 | BWR Piping Materials | R. Riggs | NRR/DE | RI (NOTE 5) | 4 | 9/30/11 | NA |
| 119.5 | Leak Detection Requirements | R. Riggs | NRR/DE | RI (NOTE 5) | 4 | 9/30/11 | NA |
| 120 | On-Line Testability of Protection Systems | W. Milstead | RES/DRA/ ARGIB | NOTE 3(b) | 2 | 6/30/95 | NA |
| 121 | Hydrogen Control for Large, Dry PWR Containments | R. Emrit | RES/DSIR/ SAIB | NOTE 3(b) | 2 | 6/30/95 | NA |
| 122 | Davis-Besse Loss of All Feedwater Event of June 9, 1985: Short-Term Actions | ||||||
| 122.1 | Potential Inability to Remove Reactor Decay Heat | ||||||
| 122.1.a | Failure of Isolation Valves in Closed Position | H. Vandermolen | NRR/DSRO/ RSIB | 124 | 4 | 12/31/98 | NA |
| 122.1.b | Recovery of Auxiliary Feedwater | H. Vandermolen | NRR/DSRO/ RSIB | 124 | 4 | 12/31/98 | NA |
| 122.1.c. | Interruption of Auxiliary Feedwater Flow | H. Vandermolen | NRR/DSRO/ RSIB | 124 | 4 | 12/31/98 | NA |
| 122.2 | Initiating Feed-and- Bleed | H. Vandermolen | NRR/DEST/ SRXB | NOTE 3(b) | 4 | 12/31/98 | NA |
| 122.3 | Physical Security System Constraints | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 4 | 12/31/98 | NA |
| 123 | Deficiencies in the Regulations Governing DBA and Single-Failure Criteria Suggested by the Davis-Besse Event of June 9, 1985 | W. Milstead | RES/DSIR/ SAIB | DROP | 1 | 6/30/95 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 124 | Auxiliary Feedwater System Reliability | R. Emrit | NRR/DEST/ SRXB | NOTE 3(a) | 3 | 6/30/91 | |
| 125 | Davis-Besse Loss of All Feedwater Event of June 9, 1985: Long-Term Actions | ||||||
| 125.I.1 | Availability of the Shift Technical Advisor | H. Vandermolen | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.I.2 | PORV Reliability | ||||||
| 125.I.2.a | Need for a Test Program to Establish Reliability of the PORV | H. Vandermolen | NRR/DSRO/ SPEB | 70 | 7 | 12/31/98 | NA |
| 125.I.2.b | Need for PORV Surveillance Tests to Confirm Operational Readiness | H. Vandermolen | NRR/DSRO/ SPEB | 70 | 7 | 12/31/98 | NA |
| 125.I.2.c | Need for Additional Protection against PORV Failure | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 125.I.2.d | Capability of the PORV to Support Feed-and-Bleed | H. Vandermolen | NRR/DSRO/ SPEB | A-45 | 7 | 12/31/98 | NA |
| 125.I.3 | SPDS Availability | W. Milstead | RES/DRA/ ARGIB | NOTE 3(b) | 7 | 12/31/98 | NA |
| 125.I.4 | Plant-Specific Simulator | R. Riggs | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.I.5 | Safety Systems Tested in All Conditions Required by DBA | R. Riggs | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.I.6 | Valve Torque Limit and Bypass Switch Settings | H. Vandermolen | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.I.7 | Operator Training Adequacy | ||||||
| 125.I.7.a | Recover Failed Equipment | J. Pittman | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 125.I.7.b | Realistic Hands-On Training | H. Vandermolen | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.I.8 | Procedures and Staffing for Reporting to NRC Emergency Response Center | H. Vandermolen | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.1 | Need for Additional Actions on AFW Systems | ||||||
| 125.II.1.a | Two-Train AFW Unavailability | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 125.II.1.b | Review Existing AFW Systems for Single Failure | H. Vandermolen | NRR/DSRO/ SPEB | 124 | 7 | 12/31/98 | NA |
| 125.II.1.c | NUREG-0737 Reliability Improvements | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 125.II.1.d | AFW/Steam and Feedwater Rupture Control System/ICS Interactions in B&W Plants | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 125.II.2 | Adequacy of Existing Maintenance Requirements for Safety-Related Systems | R. Riggs | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.3 | Review Steam/ Feedline Break Mitigation Systems for Single Failure | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 125.II.4 | Thermal Stress of OTSG Components | R. Riggs | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 125.II.5 | Thermal-Hydraulic Effects of Loss and Restoration of Feedwater on Primary System Components | R. Riggs | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 125.II.6 | Reexamine PRA Estimates of Core Damage Risk from Loss of All Feedwater | H. Vandermolen | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.7 | Reevaluate Provision to Automatically Isolate Feedwater from Steam Generator during a Line Break | H. Vandermolen | RES/DRPS/ RPSI | NOTE 3(b) | 7 | 12/31/98 | NA |
| 125.II.8 | Reassess Criteria for Feed-and-Bleed Initiation | H. Vandermolen | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.9 | Enhanced Feed-and- Bleed Capability | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 125.II.10 | Hierarchy of Impromptu Operator Actions | R. Riggs | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.11 | Recovery of Main Feedwater as Alternative to Auxiliary Feedwater | R. Riggs | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.12 | Adequacy of Training Regarding PORV Operation | R. Riggs | RES/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.13 | Operator Job Aids | J. Pittman | NRR/DRA/ ARGIB | DROP | 7 | 12/31/98 | NA |
| 125.II.14 | Remote Operation of Equipment Which Must Now Be Operated Locally | H. Vandermolen | NRR/DSRO/ SPEB | DROP | 7 | 12/31/98 | NA |
| 126 | Reliability of PWR Main Steam Safety Valves | R. Riggs | RES/DRA/ ARGIB | LI (NOTE 3) | - | 6/30/88 | NA |
| 127 | Maintenance and Testing of Manual | J. Pittman | RES/DRA/ ARGIB | DROP | 1 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Valves in Safety- Related Systems | |||||||
| 128 | Electrical Power Reliability | R. Emrit | RES/DSIR/ EIB | NOTE 3(a) | 2 | 6/30/95 | |
| 129 | Valve Interlocks to Prevent Vessel Drainage during Shutdown Cooling | W. Milstead | RES/DRA/ ARGIB | DROP | - | 6/30/90 | NA |
| 130 | Essential Service Water Pump Failures at Multiplant Sites | R. Riggs | RES/DSIR/ RPSIB | NOTE 3(a) | 2 | 12/31/95 | |
| 131 | Potential Seismic Interaction Involving the Movable In- Core Flux Mapping System Used in Westinghouse- Designed Plants | R. Riggs | RES/DRA/ ARGIB | S | 1 | 6/30/91 | NA |
| 132 | RHR System Inside Containment | N. Su | RES/DSIR/ SAIB | DROP | 1 | 12/31/95 | NA |
| 133 | Update Policy Statement on Nuclear Plant Staff Working Hours | J. Pittman | NRR/DLPQ/ LHFB | LI (NOTE 3) | 1 | 12/31/91 | NA |
| 134 | Rule on Degree and Experience Requirement | J. Pittman | RES/DRA/ RDB | NOTE 3(b) | - | 12/31/89 | NA |
| 135 | Steam Generator and Steam Line Overfill | R. Emrit | RES/DSIR/ EIB | NOTE 3(b) | 3 | 6/30/95 | NA |
| 136 | Storage and Use of Large Quantities of Cryogenic Combustibles Onsite | W. Milstead | RES/DRA/ ARGIB | LI (NOTE 3) | - | 6/30/88 | NA |
| 137 | Refueling Cavity Seal Failure | W. Milstead | RES/DRA/ ARGIB | DROP | - | 6/30/90 | NA |
| 138 | Deinerting of BWR Mark I and II | W. Milstead | RES/DSIR/ SAIB | DROP | 2 | 12/31/98 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Containments during Power Operations upon Discovery of RCS Leakage or a Train of a Safety System Inoperable | |||||||
| 139 | Thinning of Carbon Steel Piping in LWRs | R. Riggs | RES/DRA/ ARGIB | RI (NOTE 3) | 1 | 6/30/95 | NA |
| 140 | Fission Product Removal Systems | R. Riggs | RES/DRA/ ARGIB | DROP | - | 6/30/90 | NA |
| 141 | Large-Break LOCA with Consequential SGTR | R. Riggs | RES/DRA/ ARGIB | DROP | - | 6/30/90 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 142 | Leakage through Electrical Isolators in Instrumentation Circuits | W. Milstead | RES/DSIR/ EIB | NOTE 3(b) | 4 | 12/31/97 | NA |
| 143 | Availability of Chilled Water Systems and Room Cooling | W. Milstead | RES/DRA/ ARGIB | NOTE 3(b) | 2 | 6/30/95 | NA |
| 144 | Scram without a Turbine/Generator Trip | C. Hrabal | RES/DSIR/ EIB | DROP | 2 | 12/31/98 | NA |
| 145 | Actions to Reduce Common-Cause Failures | D. Rasmuson | RES/DST/ PRAB | NOTE 3(b) | 3 | 6/30/00 | NA |
| 146 | Support Flexibility of Equipment and Components | T. Y. Chang | RES/DSIR/ EIB | NOTE 3(b) | 2 | 6/30/95 | NA |
| 147 | Fire-Induced Alternate Shutdown/ | W. Milstead | RES/DSIR/ SAIB | LI (NOTE 3) | 1 | 6/30/94 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| Control Room Panel Interactions | |||||||
| 148 | Smoke Control and Manual Fire-Fighting Effectiveness | D. Basdekas | RES/DSIR/ RPSIB | LI (NOTE 3) | 1 | 6/30/00 | NA |
| 149 | Adequacy of Fire Barriers | R. Emrit | RES/DSIR/ EIB | DROP | 2 | 12/31/98 | NA |
| 150 | Overpressurization of Containment Penetrations | W. Milstead | RES/DSIR/ SAIB | DROP | 1 | 6/30/95 | NA |
| 151 | Reliability of Anticipated Transient without SCRAM Recirculation Pump Trip in BWRs | W. Milstead | RES/DSIR/ SAIB | NOTE 3(b) | 2 | 6/30/95 | NA |
| 152 | Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads | R. Emrit | RES/DSIR/ EIB | DROP | 3 | 6/30/01 | NA |
| 153 | Loss of Essential Service Water in LWRs | R. Riggs | RES/DRA/ ARGIB | NOTE 3(b) | 2 | 12/31/95 | NA |
| 154 | Adequacy of Emergency and Essential Lighting | R. Woods | RES/DSIR/ SAIB | DROP | 2 | 12/31/98 | NA |
| 155 | Generic Concerns Arising from TMI-2 Cleanup | ||||||
| 155.1 | More Realistic Source Term Assumptions | R. Emrit | RES/DST/ AEB | NOTE 3(a) | 3 | 9/30/11 | NA |
| 155.2 | Establish Licensing Requirements for Non-Operating Facilities | R. Emrit | RES/DSIR/ EIB | RI (NOTE 5) | 3 | 9/30/11 | NA |
| 155.3 | Improve Design Requirements for Nuclear Facilities | R. Emrit | RES/DSIR/ EIB | DROP | 3 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 155.4 | Improve Criticality Calculations | R. Emrit | RES/DSIR/ EIB | DROP | 3 | 9/30/11 | NA |
| 155.5 | More Realistic Severe Reactor Accident Scenario | R. Emrit | RES/DSIR/ EIB | DROP | 3 | 9/30/11 | NA |
| 155.6 | Improve Decontamination Regulations | R. Emrit | RES/DSIR/ EIB | DROP | 3 | 9/30/11 | NA |
| 155.7 | Improve Decommissioning Regulations | R. Emrit | RES/DSIR/ EIB | DROP | 3 | 9/30/11 | NA |
| 156 | Systematic Evaluation Program | ||||||
| 156.1.1 | Settlement of Foundations and Buried Equipment | T.Y. Chang | RES/DSIR/ EIB | DROP | 8 | 6/30/08 | NA |
| 156.1.2 | Dam Integrity and Site Flooding | J. Chen | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.1.3 | Site Hydrology and Ability to Withstand Floods | J. Chen | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 156.1.4 | Industrial Hazards | C. Ferrell | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.1.5 | Tornado Missiles | J. Chen | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.1.6 | Turbine Missiles | R. Emrit | RES/DSIR/ EIB | DROP | 8 | 6/30/08 | NA |
| 156.2.1 | Severe Weather Effects on Structures | J. Chen | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 156.2.2 | Design Codes, Criteria, and Load Combinations | R. Kirkwood | RES/DSIR/ EIB | DROP | 8 | 6/30/08 | NA |
| 156.2.3 | Containment Design and Inspection | S. Shaukat | RES/DSIR/ EIB | DROP | 8 | 6/30/08 | NA |
| 156.2.4 | Seismic Design of Structures, Systems, and Components | J. Chen | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.3.1.1 | Shutdown Systems | R. Woods | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.3.1.2 | Electrical Instrumentation and Controls | R. Woods | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.3.2 | Service and Cooling Water Systems | N. Su | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.3.3 | Ventilation Systems | G. Burdick | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.3.4 | Isolation of High- and Low-Pressure Systems | G. Burdick | RES/DSIR/ SAIB | DROP | 8 | 6/30/08 | NA |
| 156.3.5 | Automatic ECCS Switchover | W. Milstead | RES/DSIR/ SAIB | 24 | 8 | 6/30/08 | NA |
| 156.3.6.1 | Emergency AC Power | R. Emrit | RES/DSIR/ EIB | DROP | 8 | 6/30/08 | NA |
| 156.3.6.2 | Emergency DC Power | C. Rourk | RES/DSIR/ EIB | DROP | 8 | 6/30/08 | NA |
| 156.3.8 | Shared Systems | R. Emrit | RES/DSIR/ EIB | DROP | 8 | 6/30/08 | NA |
| 156.4.1 | RPS and ESFS Isolation | R. Emrit | RES/DSIR/ EIB | 142 | 8 | 6/30/08 | NA |
| 156.4.2 | Testing of the RPS and ESFS | T.Y. Chang | RES/DSIR/ SAIB | 120 | 8 | 6/30/08 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 156.6.1 | Pipe Break Effects on Systems and Components | H. Vandermolen | RES/DRA/ OEGIB | NOTE 3(b) | 8 | 6/30/08 | NA |
| 157 | Containment Performance | J. Shaperow | RES/DSIR/ SAIB | NOTE 3(b) | - | 6/30/95 | NA |
| 158 | Performance of Power-Operated Valves Under Design Basis Conditions | C. Hrabal | RES/DET/ GSIB | NOTE 3(b) | 2 | 6/30/00 | NA |
| 159 | Qualification of Safety-Related Pumps While Running on Minimum Flow | N. Su | RES/DSIR/ SAIB | DROP | 1 | 6/30/95 | NA |
| 160 | Spurious Actions of Instrumentation Upon Restoration of Power | C. Rourk | RES/DSIR/ EIB | DROP | 1 | 6/30/95 | NA |
| 161 | Use of Non-Safety- Related Power Supplies in Safety- Related Circuits | C. Rourk | RES/DSIR/ EIB | DROP | 1 | 6/30/95 | NA |
| 162 | Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit Is Shut Down | U. Cheh | RES/DSIR/ SAIB | DROP | 1 | 6/30/95 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 163 | Multiple Steam Generator Tube Leakage | E. Murphy | NRR/DCI/ CSG | NOTE 3(b) | 2 | 6/30/10 | |
| 164 | Neutron Fluence in Reactor Vessel | R. Emrit | RES/DSIR/ EIB | DROP | 1 | 6/30/95 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 165 | Safety and Safety/ Relief Valve Reliability | C. Hrabal | RES/DET/ GSIB | NOTE 3(b) | 2 | 6/30/00 | NA |
| 166 | Adequacy of Fatigue Life of Metal Components | R. Emrit | NRR/DE/ EMEB | NOTE 3(b) | 2 | 12/31/97 | NA |
| 167 | Hydrogen Storage Facility Separation | G. Burdick | RES/DSIR/ SAIB | DROP | 2 | 9/30/11 | NA |
| 168 | Environmental Qualification of Electrical Equipment | R. Emrit | NRR/DSSA/ SPLB | NOTE 3(b) | 3 | 6/30/04 | NA |
| 169 | BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure | R. Emrit | RES/DET/ GSIB | DROP | 1 | 6/30/00 | NA |
| 170 | Fuel Damage Criteria for High Burnup Fuel | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 2 | 6/30/01 | NA |
| 171 | ESF Failure from LOOP Subsequent to a LOCA | C. Rourk | RES/DET/ GSIB | NOTE 3(b) | 1 | 12/31/98 | NA |
| 172 | Multiple System Responses Program | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 2 | 6/30/02 | NA |
| 173 | Spent Fuel Storage Pool | ||||||
| 173.A | Operating Facilities | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 4 | 6/30/02 | NA |
| 173.B | Permanently Shutdown Facilities | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 4 | 6/30/02 | NA |
| 174 | Fastener Gaging Practices | ||||||
| 174.A | SONGS Employees' Concern | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 1 | 6/30/00 | NA |
| 174.B | Johnson Gage Company Concern | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 1 | 6/30/00 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 175 | Nuclear Power Plant Shift Staffing | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 1 | 6/30/00 | NA |
| 176 | Loss of Fill-Oil in Rosemount Transmitters | R. Emrit | RES/DET/ GSIB | NOTE 3(b) | 1 | 6/30/00 | NA |
| 177 | Vehicle Intrusion at TMI | R. Emrit | RES/DET/ GSIB | NOTE 3(a) | 1 | 6/30/00 | NA |
| 178 | Effect of Hurricane Andrew on Turkey Point | R. Emrit | RES/DET/ GSIB | LI (NOTE 3) | 2 | 6/30/00 | |
| 179 | Core Performance | R. Emrit | RES/DET/ GSIB | LI (NOTE 5) | 2 | 9/30/11 | |
| 180 | Notice of Enforcement Discretion | R. Emrit | RES/DET/ GSIB | LI (NOTE 3) | 1 | 6/30/00 | |
| 181 | Fire Protection | R. Emrit | RES/DET/ GSIB | LI (NOTE 5) | 2 | 9/30/11 | |
| 182 | General Electric Extended Power Uprate | R. Emrit | RES/DET/ GSIB | RI (NOTE 5) | 2 | 9/30/11 | |
| 183 | Cycle-Specific Parameter Limits in Technical | Specifications | R. Emrit | RES/DET/ GSIB | RI (NOTE 3) | 1/2/00 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 184 | Endangered Species | R. Emrit | RES/DET/ GSIB | EI (NOTE 3) | 3 | 9/30/14 | NA |
| 185 | Control of Recriticality Following Small- Break LOCA in PWRs | H. Vandermolen | RES/DSARE/ REAHFB | NOTE 3(b) | 1 | 6/30/06 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 186 | Potential Risk and Consequences of Heavy Load Drops | S. Jones | NRR/DSS/ SBP | NOTE 3(a) | 1 | 9/30/14 | NA |
| 187 | The Potential Impact of Postulated Cesium Concentration on Equipment Qualification in the Containment Sump in Nuclear Power Plants | H. Vandermolen | RES/DSARE/ REAHFB | DROP | - | 6/30/01 | NA |
| 188 | Steam Generator Tube Leaks/ Ruptures Concurrent with Containment Bypass | H. Vandermolen | RES/DSARE/ REAHFB | NOTE 3(b) | 1 | 6/30/06 | NA |
| 189 | Susceptibility of Ice Condenser Containments to Early Failure from Hydrogen Combustion during a Severe Accident | S. Jones | NRR/DSS/ SBP | NOTE 3(a) | 2 | 9/30/14 | NA |
| 190 | Fatigue Evaluation of Metal Components for 60-Year Plant Life | S. Shaukat | RES/DET/ GSIB | NOTE 3(b) | 2 | 6/30/00 | NA |
| 191 | Assessment of Debris Accumulation on PWR Sump Performance | S. Sanders | NRR/DSS/ SSIB | Note 3(a) | 3 | 9/30/14 | NA |
| 192 | Secondary Containment Drawdown Time | H. Vandermolen | RES/DSARE/ REAHFB | DROP | - | 6/30/03 | NA |
| 193 | BWR ECCS Suction Concerns | W. Krotiuk | RES/DSA/ RSAB | Note 3(b) | 1 | 9/30/14 | NA |
| 194 | Implications of Updated Probabilistic Seismic Hazard Estimates | D. Harrison | NRR/DSSA/ SPSB | DROP | - | 6/30/04 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| 195 | Hydrogen Combustion in Foreign BWR Piping | H. Vandermolen | RES/DSARE/ REAHFB | DROP | - | 6/30/04 | NA |
| 196 | Boral Degradation | H. Vandermolen | RES/DSARE/ ARREB | NOTE 3(b) | 1 | 6/30/07 | NA |
| 197 | Iodine Spiking Phenomena | H. Vandermolen | RES/DSARE/ ARREB | DROP | - | 6/30/06 | NA |
| 198 | Hydrogen Combustion in PWR Piping | H. Vandermolen | RES/DRASP/ OERA | DROP | - | 6/30/07 | NA |
| 199 | Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States | C. Munson | NRO/DSEA | Note 3(a) | 2 | 9/30/14 | |
| 200 | Tin Whiskers | C. Antonescu | RES/DRASP/ OERA | DROP | - | 6/30/07 | NA |
| 201 | Small-Break LOCA and Loss of Offsite Power Scenario | A. Salomon | RES/DRASP/ OERA | DROP | - | 6/30/07 | NA |
| 202 | Spent Fuel Pool Leakage Limits | T. Mitts | RES/DRASP/ OERA | DROP | - | 6/30/07 | NA |
| 203 | Potential Safety Issues with Cranes that Lift Spent Fuel Casks | T. Mitts | RES/DRASP/ OERA | DROP | - | 6/30/07 | NA |
| 204 | Flooding of Nuclear Power Plant Sites Following Upstream Dam Failures | C. Cook | NRO/DSEA/ RHMB | Note 3(a) | - | 9/30/14 |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| HUMAN FACTORS ISSUES | |||||||
| HF1 | STAFFING AND QUALIFICATIONS | ||||||
| HF1.1 | Shift Staffing | J. Pittman | RES/DRPS/ RHFB | NOTE 3(a) | 2 | 6/30/89 | |
| HF1.2 | Engineering Expertise on Shift | J. Pittman | NRR/DHFT/ HFIB | NOTE 3(b) | 2 | 6/30/89 | NA |
| HF1.3 | Guidance on Limits and Conditions of Shift Work | J. Pittman | NRR/DHFT/ HFIB | NOTE 3(b) | 2 | 6/30/89 | NA |
| HF2 | TRAINING | ||||||
| HF2.1 | Evaluate Industry Training | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| HF2.2 | Evaluate INPO Accreditation | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| HF2.3 | Revise SRP Section 13.2 | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| HF3 | OPERATOR LICENSING EXAMINATIONS | ||||||
| HF3.1 | Develop Job Knowledge Catalog | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 3) | 2 | 12/31/87 | NA |
| HF3.2 | Develop License Examination Handbook | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 3) | 2 | 12/31/87 | NA |
| HF3.3 | Develop Criteria for Nuclear Power Plant Simulators | J. Pittman | NRR/DHFT/ HFIB | I.A.4.2(4) | 2 | 12/31/87 | NA |
| HF3.4 | Examination Requirements | J. Pittman | NRR/DHFT/ HFIB | I.A.2.6(1) | 2 | 12/31/87 | NA |
| HF3.5 | Develop Computerized Exam System | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 3) | 2 | 12/31/87 | NA |
| HF4 | PROCEDURES | ||||||
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| HF4.1 | Inspection Procedure for Upgraded Emergency Operating Procedures | J. Pittman | NRR/DLPQ/ LHFB | NOTE 3(b) | 7 | 9/30/11 | NA |
| HF4.2 | Procedures Generation Package Effectiveness Evaluation | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 7 | 9/30/11 | NA |
| HF4.3 | Criteria for Safety- Related Operator Actions | J. Pittman | NRR/DHFT/ HFIB | B-17 | 7 | 9/30/11 | NA |
| HF4.4 | Guidelines for Upgrading Other Procedures | J. Pittman | RES/DRPS/ RHFB | NOTE 3(b) | 7 | 9/30/11 | NA |
| HF4.5 | Application of Automation and Artificial Intelligence | J. Pittman | NRR/DHFT/ HFIB | HF5.2 | 7 | 9/30/11 | NA |
| HF5 | MAN-MACHINE INTERFACE | ||||||
| HF5.1 | Local Control Stations | J. Pittman | RES/DRPS/ RHFB | NOTE 3(b) | 4 | 6/30/95 | NA |
| HF5.2 | Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation | J. Pittman | RES/DRPS/ RHFB | NOTE 3(b) | 4 | 6/30/95 | NA |
| HF5.3 | Evaluation of Operational Aid Systems | J. Pittman | NRR/DHFT/ HFIB | HF5.2 | 4 | 6/30/95 | NA |
| HF5.4 | Computers and Computer Displays | J. Pittman | NRR/DHFT/ HFIB | HF5.2 | 4 | 6/30/95 | NA |
| HF6 | MANAGEMENT AND ORGANIZATION | ||||||
| HF6.1 | Develop Regulatory Position on Management and Organization | J. Pittman | NRR/DHFT/ HFIB | I.B.1.1 | 1 (1,2,3,4) | 12/31/86 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| HF6.2 | Regulatory Position on Management and Organization at Operating Reactors | J. Pittman | NRR/DHFT/ HFIB | I.B.1.1 | 1 (1,2,3,4) | 12/31/86 | NA |
| HF7 | HUMAN RELIABILITY | ||||||
| HF7.1 | Human Error Data Acquisition | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| HF7.2 | Human Error Data Storage and Retrieval | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| HF7.3 | Reliability Evaluation Specialist Aids | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| HF7.4 | Safety Event Analysis Results Applications | J. Pittman | NRR/DHFT/ HFIB | LI (NOTE 5) | 2 | 9/30/11 | NA |
| HF8 | Maintenance and Surveillance Program | J. Pittman | NRR/DLPQ/ LPEB | NOTE 3(b) | 2 | 6/30/88 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| CHERNOBYL ISSUES | |||||||
| CH1 | ADMINISTRATIVE CONTROLS AND OPERATIONAL PRACTICES | ||||||
| CH1.1 | Administrative Controls To Ensure That Procedures Are Followed and That Procedures Are Adequate | ||||||
| CH1.1A | Symptom-Based EOPs | R. Emrit | NRR/DLPQ/ LHFB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.1B | Procedure Violations | R. Emrit | RES/DSR/ HFRB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| CH1.2 | Approval of Tests and Other Unusual Operations | ||||||
| CH1.2A | Test, Change, and Experiment Review Guidelines | R. Emrit | NRR/DOEA/ OTSB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.2B | NRC Testing Requirements | R. Emrit | RES/DSR/ HFRB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.3 | Bypassing Safety Systems | ||||||
| CH1.3A | Revise Regulatory Guide 1.47 | R. Emrit | RES/DE/ EMEB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.4 | Availability of Engineered Safety Features | ||||||
| CH1.4A | Engineered Safety Feature Availability | R. Emrit | NRR/DOEA/ OTSB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.4B | Technical Specifications Bases | R. Emrit | NRR/DOEA/ OTSB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.4C | Low Power and Shutdown | R. Emrit | RES/DSR/ PRAB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.5 | Operating Staff Attitudes Toward Safety | R. Emrit | RES/DRA/ ARGIB | LI (NOTE 3) | 1 | 9/30/11 | NA |
| CH1.6 | Management Systems | ||||||
| CH1.6A | Assessment of NRC Requirements on Management | R. Emrit | RES/DSR/ HFRB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH1.7 | Accident Management | ||||||
| CH1.7A | Accident Management | R. Emrit | RES/DSR/ HFRB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH2 | DESIGN | ||||||
| CH2.1 | Reactivity Accidents | ||||||
| CH2.1A | Reactivity Transients | R. Emrit | RES/DSR/ RPSB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| Action Plan Item/ Issue No. | Title | Responsible Project Manager | Lead Office Division/ Branch | Status/ Safety Priority Ranking | Latest Rev. | Latest Issuance Date | MPANo. |
| CH2.2 | Accidents at Low Power and at Zero Power | R. Emrit | RES/DRA/ ARGIB | CH1.4 | 1 | 9/30/11 | NA |
| CH2.3 | Multiple-Unit Protection | ||||||
| CH2.3A | Control Room Habitability | R. Emrit | RES/DRA/ ARGIB | 83 | 1 | 9/30/11 | NA |
| CH2.3B | Contamination Outside Control Room | R. Emrit | RES/DRA/ ARGIB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH2.3C | Smoke Control | R. Emrit | RES/DSIR/ SAIB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH2.3D | Shared Shutdown Systems | R. Emrit | RES/DRA/ ARGIB | LI (NOTE 5) | 1 | 9/30/11 | NA |
| CH2.4 | Fire Protection | ||||||
| CH2.4A | Firefighting with Radiation Present | R. Emrit | RES/DSIR/ SAIB | LI (NOTE 5) | 1 | 9/30/11 | NA |