Resolution of Generic Safety Issues: Task II.K: Measures to Mitigate Small-Break Loss-Of-Coolant Accidents and Loss-Of-Feedwater Accidents ( 2) ( NUREG-0933, Main Report with Supplements 1–35 )
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The objectives of this task were to perform systems reliability analyses and to effect changes in emergency operating procedures and operator training to improve the capability of plants to mitigate the consequences of the small-break LOCAs and loss-of-feedwater events.
ITEM II.K.1: IE BULLETINS
Between April 1, 1979 and July 26, 1979, OIE issued 9 bulletins to various operating plants, depending on their reactor design, and a review of the affected licensee responses was conducted by the NRR Bulletins and Orders Task Force (BOTF). The responses were determined to be acceptable and separate evaluation reports were prepared and issued to some licensees. Thus, prior to the publication of NUREG-0660,48 several parts of this item were either com-pleted or found to be covered in other TMI Action Plan items. This status was reported in Table C.1 of NUREG-0660.48 The following is a summary of the 28 parts of this item.
ITEM II.K.1(1): REVIEW TMI-2 PNS AND DETAILED CHRONOLOGY OF THE TMI-2 ACCIDENT
DESCRIPTION
This NUREG-066048 item affected all OLs and was originated to effect short-term changes in emergency operating procedures and operator training in order to improve the capability of plants to mitigate the likelihood and consequences of SBLOCAs and loss-of-feedwater events. For all OL applicants, this item was determined to be covered by Items I.A.2.2 and I.A.3.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(2): REVIEW TRANSIENTS SIMILAR TO TMI-2 THAT HAVE OCCURRED AT OTHER FACILITIES AND NRC EVALUATION OF DAVIS-BESSE EVENT
DESCRIPTION
This NUREG-066048 item affected all B&W operating plants. For OL applicants with B&W reactors, this item was determined to be covered by Items I.A.2.2 and I.A.3.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(3): REVIEW OPERATING PROCEDURES FOR RECOGNIZING, PREVENTING, AND MITIGATING VOID FORMATION IN TRANSIENTS AND ACCIDENTS
DESCRIPTION
This NUREG-066048 item affected all operating PWRs. For OL applicants with PWRs, it was determined that the issue was covered by Item I.C.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(4): REVIEW OPERATING PROCEDURES AND TRAINING INSTRUCTIONS
DESCRIPTION
This NUREG-066048 item was divided into 4 parts to ensure: (a) that operators do not override ESF actions unless continued operation is unsafe; (b) HPI system operation; (c) RCP operation; and (d) that operators are instructed not to rely on level indication alone in evaluating plant conditions.
- Part (a) affected all operating plants. However, for all OL applicants it was determined that this part was covered by Items I.C.1, I.C.7, I.G.1, and I.C.8.
- Part (b) affected all W, CE and B&W operating plants with specific requirements issued to ANO-1; Davis-Besse 1; Oconee 1, 2, and 3; Crystal River 3; and Rancho Seco. For OL applicants with W, CE, or B&W reactors, it was determined that this part was covered by Item I.C.1.
- Part (c) affected all PWRs and was completed by OLs prior to the publication of NUREG-0660.48 For OL applicants with PWRs, it was determined that this part was covered by Items I.C.1 and I.A.1.3.
- Part (d) affected all plants and was completed by OLs prior to the publication of NUREG-0660.48 For all OL applicants, it was determined that this part was covered by Items I.C.1, I.A.3.1, and II.F.2.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(5): SAFETY-RELATED VALVE POSITION DESCRIPTION
DESCRIPTION
This NUREG-066048 item was divided into 2 parts and required plants to: (a) review all valve positions and positioning requirements and positive controls along with all related test and and maintenance procedures to assure proper ESF functioning, if required; and (b) verify that AFW valves are in the open position.
- Part (a) affected all operating plants. For all OL applicants, it was determined that this part was covered by Items I.C.2 and I.C.6.
- Part (b) affected all B&W operating plants. For OL applicants with B&W reactors, this part was also determined to be covered by Items I.C.2 and I.C.6.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(6): REVIEW CONTAINMENT ISOLATION INITIATION DESIGN AND PROCEDURES
DESCRIPTION
This NUREG-066048 item affected all operating plants and was initiated to assure isolation of all lines that do not degrade safety features or cooling capability upon automatic initiation of SI. For all OL applicants, it was determined that this issue was covered by Item II.E.4.2.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(7): IMPLEMENT POSITIVE POSITION CONTROLS ON VALVES THAT COULD COMPROMISE OR DEFEAT AFW FLOW
DESCRIPTION
This NUREG-066048 item affected all B&W operating plants. For OL applicants with B&W reactors, this issue was determined to be covered by Item II.E.1.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(8): IMPLEMENT PROCEDURES THAT ASSURE TWO INDEPENDENT 100% AFW FLOW PATHS
DESCRIPTION
This NUREG-066048 item required all operating B&W plants to immediately implement procedures that assure two independent 100% AFW flow paths or specify explicitly LCO with reduced AFW capacity. For OL applicants with B&W reactors, this issue was determined to be covered by Item II.E.1.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(9): REVIEW PROCEDURES TO ASSURE THAT RADIOACTIVE LIQUIDS AND GASES ARE NOT TRANSFERRED OUT OF CONTAINMENT INADVERTENTLY
DESCRIPTION
This NUREG-066048 item required all operating plants to review their procedures to assure that radioactive liquids and gases are not transferred out of containment inadvertently, especially upon ESF reset. All applicable systems and interlocks were required to be listed. For OL applicants, this item was determined to be covered by Items II.E.4.2 and I.C.6.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(10): REVIEW AND MODIFY PROCEDURES FOR REMOVING SAFETY-RELATED SYSTEMS FROM SERVICE
DESCRIPTION
This NUREG-066048 item required all operating plants to review and modify (as required) their procedures for removing safety-related systems from service (and restoring to service) to assure operability status is known. For OL applicants, the issue was determined to be covered by Items I.C.2 and I.C.6.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM 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
DESCRIPTION
This NUREG-066048 item affected all operating plants. For OL applicants, the issue was determined to be covered by Items I.A.2.2 and I.A.3.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(12): ONE HOUR NOTIFICATION REQUIREMENT AND CONTINUOUS COMMUNICATIONS CHANNELS
DESCRIPTION
This NUREG-066048 item affected all operating plants. For OL applicants, the issue was determined to be covered by Items I.E.6 and III.A.3.3.
CONCLUSION
This item was RESOLVED and requirements were issued.
Item II.K.1(13): Propose Technical Specification Changes Reflecting Implementation of All Bulletin Items
DESCRIPTION
This NUREG-066048 item required all operating plants to propose TS changes reflecting implementation of all Bulletin items, as required.
CONCLUSION
This item was RESOLVED and requirements were issued.
Item II.K.1(14): Review Operating Modes and Procedures to Deal with Significant Amounts of Hydrogen
DESCRIPTION
This NUREG-066048 item affected all operating plants with W, CE, and GE reactors.
For OL applicants with W, CE and GE reactors, it was determined that the issue was covered by Items II.B.4, II.B.7, II.E.4.1, and II.F.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
Item II.K.1(15): For Facilities with Non-automatic AFW Initiation, Provide Dedicated Operator in Continuous Communication with CR to Operate AFW
DESCRIPTION
This NUREG-066048 item affected all operating plants with W and CE reactors. However, prior to the publication of NUREG-0660,48 all necessary action was completed by the affected OLs. For OL applicants with W and CE reactors, it was determined that the issue was covered by Item II.E.1.2.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(16): IMPLEMENT PROCEDURES THAT IDENTIFY PRZPORV "OPEN" INDICATIONS AND THAT DIRECT OPERATOR TO CLOSE MANUALLY AT "RESET" SETPOINT
DESCRIPTION
This NUREG-066048 item affected all operating plants with W and CE reactors. However, prior to the publication of NUREG-0660,48 all necessary action was completed by the affected OLs. For OL applicants with W and CE reactors, it was determined that the issue was covered by Items I.C.1 and II.D.3.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(17): TRIP PZR LEVEL BISTABLE SO THAT PZR LOW PRESSURE WILL INITIATE SAFETY INJECTION
DESCRIPTION
This NUREG-066048 item required all OLs and OL applicants with W reactors to trip the pressurizer level bistable so that the pressurizer low pressure (rather than the pressurizer low pressure and pressurizer low level coincidence) would initiate safety injection. For testing, the plants were required to reset the low level bistable. However, prior to the publication of NUREG-0660,48 all necessary action was completed by the affected OLs.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(18): DEVELOP PROCEDURES AND TRAIN OPERATORS ON METHODS OF ESTABLISHING AND MAINTAINING NATURAL CIRCULATION
DESCRIPTION
This NUREG-066048 item affected all operating B&W plants. However, prior to the publication of NUREG-0660,48 all necessary action was completed by the affected plants. For OL applicants with B&W reactors, it was determined that the issue was covered by Items I.C.1 and I.G.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(19): DESCRIBE DESIGN AND PROCEDURE MODIFICATIONS TO REDUCE LIKELIHOOD OF AUTOMATIC PZR PORV ACTUATION IN TRANSIENTS
DESCRIPTION
This NUREG-066048 item required all operating B&W plants to describe their design and procedure modifications (based on analysis) to reduce the likelihood of automatic pressurizer PORV actuation in transients. For OL applicants with B&W reactors, it was determined that the issue was covered by Item II.E.5.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM 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
DESCRIPTION
This NUREG-066048 item affected all OLs and OL applicants with B&W reactors.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(21): PROVIDE AUTOMATIC SAFETY-GRADE ANTICIPATORY REACTOR TRIP FOR LOFW, TT, OR SIGNIFICANT DECREASE IN SG LEVEL
DESCRIPTION
This NUREG-066048 item affected all OLs and OL applicants with B&W reactors.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(22): DESCRIBE AUTOMATIC AND MANUAL ACTIONS FOR PROPER FUNCTIONING OF AUXILIARY HEAT REMOVAL SYSTEMS WHEN FW SYSTEM NOT OPERABLE
DESCRIPTION
This NUREG-066048 item affected all OLs and OL applicants with BWRs.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(23): DESCRIBE USES AND TYPES OF RV LEVEL INDICATION FOR AUTOMATIC AND MANUAL INITIATION SAFETY SYSTEMS
DESCRIPTION
This NUREG-066048 item required all OLs and OL applicants with BWRs to describe their uses and types of reactor vessel indication for automatic and manual initiation safety systems. The affected plants were also required to describe their alternative instrumentation.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM 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
DESCRIPTION
This NUREG-066048 item affected all operating PWRs. However, prior to the publication of NUREG-0660,48 all necessary action was completed by the affected OLs. For OL applicants with PWRs, the issue was determined to be covered by Item I.C.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(25): DEVELOP OPERATOR ACTION GUIDELINES
DESCRIPTION
This NUREG-066048 item required all operating PWRs to develop operator action guidelines, based on the analyses performed in response to Item II.K.1(24). However, prior to the publication of NUREG-0660,48 it was determined that all necessary action was completed by the affected plants. For OL applicants with PWRs, the issue was determined to be covered by Item I.C.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(26): REVISE EMERGENCY PROCEDURES AND TRAIN ROs AND SROs
DESCRIPTION
This NUREG-066048 item required all operating PWRs to revise their emergency procedures and train ROs and SROs, based on guidelines developed in response to Item II.K.1(25). However, prior to the publication of NUREG-0660,48 all necessary action was completed by the affected OLs. For OL applicants with PWRs, it was determined that the issue was covered by Items I.A.3.1, I.C.1, and I.G.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(27): PROVIDE ANALYSES AND DEVELOP GUIDELINES AND PROCEDURES FOR INADEQUATE CORE COOLING CONDITIONS
DESCRIPTION
This NUREG-066048 item required all operating PWRs to provide analyses and develop guidelines and procedures for inadequate core cooling conditions. The affected plants were also required to define their RCP restart criteria. However, prior to the publication of NUREG-0660,48 all necessary action was completed by the affected OLs. For OL applicants with PWRs, it was determined that the issue was covered by Items I.C.1 and II.F.2.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.1(28): PROVIDE DESIGN THAT WILL ASSURE AUTOMATIC RCP TRIP FOR ALL CIRCUMSTANCES WHERE REQUIRED
DESCRIPTION
This NUREG-066048 item affected all operating PWRs. For OL applicants with PWRs, it was determined that the issue was covered by Item II.K.3(5).
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2: COMMISSION ORDERS ON BABCOCK AND WILCOX PLANTS
This item contained 21 requirements for 7 operating plants with B&W reactors that were issued confirmatory shutdown orders shortly after the TMI-2 accident. Some of these requirements were also applicable to OL applicants with B&W reactors. These requirements were divided into two groups: short-term actions and long-term actions. The short-term actions were essentially those that were listed in Table 2-1 of NUREG-0645580 while the long-term actions were also dilineated in NUREG-0645.580
However, prior to the publication of NUREG-0660,48 10 of these requirements were either completed or found to be covered by other TMI Action Plan items. This status was reported in Table C.2 of NUREG-0660.48 Since that time, some of the remaining items have been clarified in NUREG-073798 and others have been completed. The status of the MPAs established for implementation can be found in NUREG-0748.578 The following is a summary of the 21 parts of this item.
ITEM II.K.2(1): UPGRADE TIMELINESS AND RELIABILITY OF AFW SYSTEM
DESCRIPTION
All 7 B&W plants with OLs completed this short-term NUREG-066048 action before they were permitted to restart. These accomplishments were made in July 1979, prior to the publication of NUREG-0660.48 For OL applicants with B&W reactors, it was determined that the issue was being addressed by Items II.E.1.1 and II.E.1.2.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2(2): PROCEDURES AND TRAINING TO INITIATE AND CONTROL AFW INDEPENDENT OF INTEGRATED CONTROL SYSTEM
DESCRIPTION
All 7 B&W plants with OLs completed this short-term NUREG-066048 action before they were permitted to restart. These accomplishments were made prior to the publication of NUREG-0660.48 This requirement was also applicable to OL applicants with B&W reactors and was clarified in NUREG-0737.98
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2(3): HARD-WIRED CONTROL-GRADE ANTICIPATORY REACTOR TRIPS
DESCRIPTION
All 7 B&W plants with OLs completed this short-term NUREG-066048 action before they were permitted to restart. These accomplishments were made in July 1979, prior to the publication of NUREG-0660.48 This requirement was not applicable to OL applicants with B&W reactors.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2(4): SMALL-BREAK LOCA ANALYSIS, PROCEDURES AND OPERATOR TRAINING
DESCRIPTION
All 7 B&W plants with OLs completed this short-term NUREG-066048 action before they were permitted to restart. These accomplishments were made in September 1979, prior to the publication of NUREG-0660.48 For OL applicants with B&W reactors, it was determined that the issue was being addressed by Items I.A.3.1 and I.C.1.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2(5): COMPLETE TMI-2 SIMULATOR TRAINING FOR ALL OPERATORS
DESCRIPTION
All 7 B&W plants with OLs completed this short-term NUREG-066048 action before they were permitted to restart. These accomplishments were made prior to the publication of NUREG-0660.48 For OL applicants with B&W reactors, it was determined that the issue was being addressed by Item I.A.2.6.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2(6): REEVALUATE ANALYSIS FOR DUAL-LEVEL SETPOINT CONTROL
DESCRIPTION
Prior to the TMI-2 accident, Toledo Edison Company (TECO) was authorized by the NRC (pending incorporation of permanent design modifications to provide automatic dual setpoint steam generator level control) to manually control steam generator level at 35 in. for all events requiring auxiliary feedwater, unless a safety feature actuation system Level 2 signal occurred. Following the TMI-2 accident, the staff required additional information to verify that the effects of manually controlling steam generator level at 35 in. was adequate for the Davis-Besse plant, in light of the revised small-break LOCA analyses that were performed by B&W after the TMI-2 accident.
The only operating plant affected by this item, Davis-Besse 1, completed this short-term NUREG-066048 action before it was permitted to restart. This accomplishment was made in July 1979, prior to the publication of NUREG-0660.48 This requirement was not applicable to OL applicants with B&W reactors.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2(7): REEVALUATE TRANSIENT OF SEPTEMBER 24, 1977
DESCRIPTION
In September 1977, Davis-Besse 1 experienced an event which started out very similar to the one that occurred at TMI-2. In light of the information gained from the TMI-2 accident, the staff felt it was necessary to review the previous evaluation prepared by Toledo Edison Company for the Davis-Besse 1 event which involved equipment problems and depressurization of the primary system.
The only plant affected by this item, Davis-Besse 1, completed this short-term NUREG-066048 action before it was permitted to restart. This accomplishment was made in July 1979, prior to the publication of NUREG-0660.48 This require-ment was not applicable to OL applicants with B&W reactors.
CONCLUSION
The item was RESOLVED and requirements were issued.
ITEM II.K.2(8): CONTINUED UPGRADING OF AFW SYSTEM
DESCRIPTION
All 7 B&W plants with OLs were initially required to complete this long-term NUREG-066048 action. However, a clarification was issued in NUREG-073798 which superseded this item with Items II.E.1.1 and II.E.1.2. For OL applicants with B&W reactors, it was determined that the issue was being addressed by Items II.E.1.1 and II.E.1.2.
CONCLUSION
This item is covered in Items II.E.1.1 and II.E.1.2.
ITEM II.K.2(9): ANALYSIS AND UPGRADING OF INTEGRATED CONTROL SYSTEM
DESCRIPTION
This NUREG-066048 item called for licensees with B&W reactors to provide a failure mode effects analysis on the integrated control system. All 7 B&W plants with OLs as well as OL applicants with B&W reactors were required to complete this long-term action. A clarification that affected both groups of plants was issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-27 was established by DL for implementation purposes.
ITEM II.K.2(10): HARD-WIRED SAFETY-GRADE ANTICIPATORY REACTOR TRIPS
DESCRIPTION
This NUREG-066048 item called for licensees with B&W reactors to provide a design and schedule for implementation of a safety-grade reactor trip upon loss of feedwater, turbine trip, and significant reduction in steam generator level. These requirements were listed as Item 5 of IE Bulletin 79-05B which was issued on April 21, 1979. All 7 B&W plants with OLs as well as OL applicants with B&W reactors were required to complete this long-term action. Clarifications that affected both groups of plants were issued in NUREG-073798 and OL applicants with B&W reactors were given the option of complying with Item II.K.1 (Part C.1.21) of NUREG-0694579 to satisfy this requirement.
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-28 was established by DL for implementation purposes.
ITEM II.K.2(11): OPERATOR TRAINING AND DRILLING
DESCRIPTION
All 7 B&W plants with OLs were required to complete this long-term NUREG-066048 item which called for continued operator training and drilling to assure a high state of preparedness. For the affected OLs, a clarification to the requirement was issued in NUREG-0737.98 For OL applicants with B&W reac-tors, this item was determined to be covered Items I.A.2.2, I.A.2.5, I.A.3.1, and I.G.1 prior to the publication of NUREG-0660.48
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-29 was established by DL for implementation purposes.
ITEM II.K.2(12): TRANSIENT ANALYSIS AND PROCEDURES FOR MANAGEMENT OF SMALL BREAKS
DESCRIPTION
The only operating B&W plant affected by this NUREG-066048 item was Davis-Besse 1. However, prior to the publication of NUREG-0660,48 it was determined that the issue was covered by Item I.C.1 for Davis-Besse 1 and all OL applicants with B&W reactors.
CONCLUSION
This item is covered in Item I.C.1.
ITEM II.K.2(13): THERMAL-MECHANICAL REPORT ON EFFECT OF HPI ON VESSEL INTEGRITY FOR SMALL-BREAK LOCA WITH NO AFW
DESCRIPTION
This item required the affected plants to demonstrate that sufficient mixing of the high pressure injection water would occur with the reactor coolant so that significant thermal shock effects to the reactor vessel would be precluded. All 7 B&W plants with OLs and all OL applicants with B&W reactors were required to comply with this NUREG-066048 item. A clarification was issued in NUREG-073798 to include all PWRs (OLs and OL applicants).
CONCLUSION
This item was RESOLVED, requirements were issed, and MPA F-30 was established by DL for implementation purposes.
ITEM II.K.2(14): DEMONSTRATE THAT PREDICTED LIFT FREQUENCY OF PORVs AND SVs IS ACCEPTABLE
DESCRIPTION
All 7 B&W plants with OLs and all OL applicants with B&W reactors were required to comply with this NUREG-066048 item. A clarification affecting both groups of plants was issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-31 was established by DL for implementation purposes.
ITEM II.K.2(15): ANALYSIS OF EFFECTS OF SLUG FLOW ON ONCE-THROUGH STEAM GENERATOR TUBES AFTER PRIMARY SYSTEM VOIDING
DESCRIPTION
All 7 B&W plants with OLs and all OL applicants with B&W reactors were required to comply with this NUREG-066048 item which called for the affected plants to assess the loading on steam generator tube sheets induced from slug flow during natural circulation cooldown. A clarification affecting both groups of plants was issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.2(16): IMPACT OF RCP SEAL DAMAGE FOLLOWING SMALL-BREAK LOCA WITH LOSS OF OFFSITE POWER
DESCRIPTION
All 7 B&W plants with OLs and all OL applicants with B&W reactors were required to comply with this NUREG-066048 item which called for the investigation of the consequences of losing coolant to the seals of the reactor coolant pumps during loss of offsite power. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-32 was established by DL for implementation purposes.
ITEM II.K.2(17): ANALYSIS OF POTENTIAL VOIDING IN RCS DURING ANTICIPATED TRANSIENTS
DESCRIPTION
All 7 B&W plants with OLs were required to comply with this NUREG-066048 item which called for the plants to determine the consequence of voiding in the reactor vessel and the hot legs during normal anticipated transients. For OL applicants with B&W reactors, it was determined that the issue was being addressed by Item I.C.1. Clarifications were issued in NUREG-073798 to include all PWRs (OLs and OL applicants).
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-33 was established by DL for implementation purposes.
ITEM II.K.2(18): ANALYSIS OF LOSS OF FEEDWATER AND OTHER ANTICIPATED TRANSIENTS
DESCRIPTION
All 7 B&W plants with OLs and all OL applicants with B&W reactors plants were affected by this NUREG-066048 item. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.1.
CONCLUSION
This item is covered in by Item I.C.1.
ITEM II.K.2(19): BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE-THROUGH STEAM GENERATOR
DESCRIPTION
All 7 B&W plants with OLs were required to comply with this NUREG-066048 item which called for the evaluation of the steam generator model in the small-break licensing code (CRAFT-2) by predicting the Crystal River asymmetric cooldown start-up test. For OL applicants with B&W reactors, it was determined that the issue was being addressed by Item I.C.1. Clarifications were issued in NUREG-073798 to include all PWRs (OLs and OL applicants).
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-34 was established by DL for implementation purposes.
ITEM II.K.2(20): ANALYSIS OF STEAM RESPONSE TO SMALL-BREAK LOCA THAT CAUSES SYSTEM PRESSURE TO EXCEED PORV SETPOINT
DESCRIPTION
All 7 B&W plants with OLs were required to comply with this NUREG-066048 item which called for the assessment of small-break LOCAs which result in pressurization of the primary system to the PORV setpoint. For OL applicants with B&W reactors, it was determined that the issue was being addressed by Item I.C.1.
A clarification affecting the 7 OLs was issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-35 was established by DL for implementation purposes.
ITEM II.K.2(21): LOFT 3-1 PREDICTIONS DESCRIPTION
DESCRIPTION
The adequacy of B&W's small-break LOCA model needed to be benchmarked against integral systems test data. By performing this pretest prediction of LOFT L3-1, the staff was able to determine this information. All 7 B&W plants were affected by this NUREG-066048 item which was completed in December 1979, prior to the publication of NUREG-0660.48 OL applicants with B&W reactors were not affected by this item.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.3: FINAL RECOMMENDATIONS OF BULLETINS AND ORDERS TASK FORCE
This item contained 57 requirements that affected OLs and OL applicants. These requirements were based on recommendations that were developed by the staff and issued in the following reports: NUREG-056596 (B&W reactors), NUREG-061193 (W reactors), NUREG-062694 (GE reactors), NUREG-063595 (CE reactors), and NUREG-0623.97 However, prior to the publication of NUREG-0660,48 some of these requirements were superseded by other TMI Action Plan items. This status was reported in Table C.3 of NUREG-0660.48 Since that time, some of the remaining items have been clarified in NUREG-073798 and others have been completed. The status of the MPAs established for implementation can be found in NUREG-0748.578 The following is a summary of the 57 parts of this item.
ITEM II.K.3(1): INSTALL AUTOMATIC PORV ISOLATION SYSTEM AND PERFORM OPERATIONAL TEST
DESCRIPTION
This NUREG-066048 item required all operating PWRs to provide a system that uses the PORV block valve to protect against a small-break LOCA. This system will automatically cause the block valve to close when the reactor coolant system pressure decays after the PORV has opened. OL applicants with PWRs were also required to complete this item. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-36 was established by DL for implementation purposes.
ITEM II.K.3(2): REPORT ON OVERALL SAFETY EFFECT OF PORV ISOLATION SYSTEM
DESCRIPTION
This NUREG-066048 item required all operating PWRs to document the action to be taken to decrease the probability of a small-break LOCA caused by a stuck-open PORV. OL applicants with PWRs were also required to complete this item. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-37 was established by DL for implementation purposes.
ITEM II.K.3(3): REPORT SAFETY AND RELIEF VALVE FAILURES PROMPTLY AND CHALLENGES ANNUALLY
DESCRIPTION
This NUREG-066048 item required all operating plants to report safety and relief valve failures promptly and challenges annually. All OL applicants were also required to complete this item. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-38 was established by DL for implementation purposes.
ITEM II.K.3(4): REVIEW AND UPGRADE RELIABILITY AND REDUNDANCY OF NON-SAFETY EQUIPMENT FOR SMALL-BREAK LOCA MITIGATION
DESCRIPTION
This NUREG-066048 item only affected OL applicants. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items II.C.1, II.C.2, and II.C.3.
CONCLUSION
This item is covered in Items II.C.1, II.C.2, and II.C.3.
ITEM II.K.3(5): AUTOMATIC TRIP OF REACTOR COOLANT PUMPS
DESCRIPTION
This NUREG-066048 item required all PWR operating plants to study the need for automatic trip of RCPs and to modify procedures or designs, as appropriate. OL applicants with PWRs were also required to complete this item. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-39 was established by DL for implementation purposes.
ITEM II.K.3(6): INSTRUMENTATION TO VERIFY NATURAL CIRCULATION
DESCRIPTION
This NUREG-066048 item affected all PWRs (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items I.C.1, II.F.2, and II.F.3.
CONCLUSION
This item is covered in Items I.C.1, II.F.2, and II.F.3.
ITEM II.K.3(7): EVALUATION OF PORV OPENING PROBABILITY DURING OVERPRESSURE TRANSIENT
DESCRIPTION
This NUREG-066048 item required all B&W operating plants (OLs and OL applicants)
to document that their PORVs would open in less than 5% of all anticipated overpressure transients. Clarifications were issued in NUREG-073798 to include all PWRs.
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.3(8): FURTHER STAFF CONSIDERATION OF NEED FOR DIVERSE DECAY HEAT REMOVAL METHOD INDEPENDENT OF SGs
DESCRIPTION
This NUREG-066048 item affected all PWRs (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items II.C.1 and II.E.3.3.
CONCLUSION
This item is covered in Items II.C.1 and II.E.3.3.
ITEM II.K.3(9): PROPORTIONAL INTEGRAL DERIVATIVE CONTROLLER MODIFICATION
DESCRIPTION
This NUREG-066048 item required all W plants (OLs and OL applicants) to raise the interlock bistable trip setting to preclude derivative action from opening the PORVs. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-40 was established by DL for implementation purposes.
ITEM II.K.3(10): ANTICIPATORY TRIP MODIFICATION PROPOSED BY SOME LICENSEES TO CONFINE RANGE OF USE TO HIGH POWER LEVELS
DESCRIPTION
This NUREG-066048 item required that the anticipatory trip modification proposed
by some licensees to confine the range of use of high-power levels not be made until it could be shown that the probability of a small-break LOCA resulting from a stuck-open PORV was substantially unaffected by the modification. The applicability of the item to W operating plants and OL applicants with W reactors was to be determined on a plant-by-plant basis. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-41 was established by DL for implementation purposes.
ITEM II.K.3(11): CONTROL USE OF PORV SUPPLIED BY CONTROL COMPONENTS, INC. UNTIL FURTHER REVIEW COMPLETE
DESCRIPTION
This NUREG-066048 item required plants to justify the use of PORVs that had failed during testing. The applicability of the item to all operating plants and OL applicants was to be determined on a case-by-case basis. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.3(12): CONFIRM EXISTENCE OF ANTICIPATORY TRIP UPON TURBINE TRIP
DESCRIPTION
This NUREG-066048 item required all W plants (OLs and OL applicants) to confirm that their plants have an anticipatory reactor trip upon turbine trip. Plants that did not have this trip were required to provide a conceptual design and evaluation for the installation of the trip. Clarifications affecting both groups of plants were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-42 was established by DL for implementation purposes.
ITEM II.K.3(13): SEPARATION OF HPCI AND RCIC SYSTEM INITIATION LEVELS
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to analyze the benefits to be gained from separating HPCI and RCIC initiation levels and providing auto-start of RCIC on low-low level. Clarifications were issued in NUREG-073798 to include all operating BWRs and OL applicants with RCIC and HPCI systems.
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-43 was established by DL for implementation purposes.
ITEM II.K.3(14): ISOLATION OF ISOLATION CONDENSERS ON HIGH RADIATION
DESCRIPTION
This NUREG-066048 item required all operating GE plants with isolation conden-sers to increase the availability of the isolation condensers as heat sinks by providing high radiation isolation signals at the vent rather than at the steam lines. Clarifications affecting all operating BWRs with isolation condensers were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-44 was established by DL for implementation purposes.
ITEM II.K.3(15): MODIFY BREAK DETECTION LOGIC TO PREVENT SPURIOUS ISOLATION OF HPCI AND RCIC SYSTEMS
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to modify their pipe break detection circuitry to prevent isolation of system(s) due to startup pressure transient. Clarifications were issued in NUREG-073798 to address all BWRs (OLs and OL applicants) with HPCI and RCIC systems.
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-45 was established by DL for implementation purposes.
ITEM II.K.3(16): REDUCTION OF CHALLENGES AND FAILURES OF RELIEF VALVES-FEASIBILITY STUDY AND SYSTEM MODIFICATION
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to study the reduction in challenge and failure rates of relief valves to minimize the most possible cause of a small-break LOCA. Clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-46 was established by DL for implementation purposes.
ITEM II.K.3(17): REPORT ON OUTAGE OF ECC SYSTEMS - LICENSEE REPORT AND TECHNICAL SPECIFICATION CHANGES
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to review data on ECC system outages to determine if cumulative outage time limitations should be incorporated in technical specifications. Clarifications were issued in NUREG-073798 to include all operating reactors and OL applicants.
CONCLUSION
This item was RESOLVED, requirements were issued and MPA F-47 was established by DL for implementation purposes.
ITEM II.K.3(18): MODIFICATION OF ADS LOGIC - FEASIBILITY STUDY AND MODIFICATION FOR INCREASED DIVERSITY FOR SOME EVENT SEQUENCES
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to modify their ADS actuation logic to eliminate the need for manual actuation to assure adequate core cooling. A feasibility study and risk assessment study were required to determine the optimum approach. Clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-48 was established by DL for implementation purposes.
ITEM II.K.3(19): INTERLOCK ON RECIRCULATION PUMP LOOPS
DESCRIPTION
This NUREG-066048 item required all GE operating plants with non-jet pumps to install interlocks to assure that level measurements are representative of the level in the core. Clarifications were issued in NUREG-073798 to address all operating BWRs with non-jet pumps, except Humboldt Bay.
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-49 was established by DL for implementation purposes.
ITEM II.K.3(20): LOSS OF SERVICE WATER FOR BIG ROCK POINT
DESCRIPTION
This NUREG-066048 item required Big Rock Point to evaluate the acceptability or the consequences of a loss of service water. A clarification to this requirement was issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED and requirements were issued.
ITEM II.K.3(21): RESTART OF CORE SPRAY AND LPCI SYSTEMS ON LOW LEVEL - DESIGN AND MODIFICATION
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to modify their core spray and LPCI system logic so that these systems would restart, if required, to assure adequate core cooling. It was believed that the core spray and LPCI system flow may be stopped by the operator. These systems could not start automatically on loss of water level if an initiation signal were still present. Clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-50 was established by DL for implementation purposes.
ITEM II.K.3(22): AUTOMATIC SWITCHOVER OF RCIC SYSTEM SUCTION - VERIFY PROCEDURES AND MODIFY DESIGN
DESCRIPTION
This NUREG-066048 item affected all GE plants (OLs and OL applicants). The RCIC system takes suction from the condensate storage tank with manual switch-over to the suppression pool when the condensate storage tank level is low. This switchover should be made automatically. Until the automatic switchover is implemented, licensees should verify that clear and cogent procedures exist for the manual switchover of the RCIC system suction from the condensate storage tank to the suppression pool. Clarifications affecting all operating BWRs and OL applicants with RCIC systems were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-51 was established by DL for implementation purposes.
ITEM II.K.3(23): CENTRAL WATER LEVEL RECORDING
DESCRIPTION
This NUREG-066048 item was originated to address GE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items I.D.2, III.A.1.2, and III.A.3.4.
CONCLUSION
This item is covered in Items I.D.2, III.A.1.2, and III.A.3.4.
ITEM II.K.3(24): CONFIRM ADEQUACY OF SPACE COOLING FOR HPCI AND RCIC SYSTEMS
DESCRIPTION
This NUREG-066048 item required all operating GE plants (OLs and OL applicants) to verify that HPCI and RCIC are designed to withstand loss of offsite power for at least 2 hours. Clarifications affecting all BWRs (OLs and OL applicants) with HPCI and RCIC systems were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-52 was established by DL for implementation purposes.
ITEM II.K.3(25): EFFECT OF LOSS OF AC POWER ON PUMP SEALS
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to verify the adequacy of pump seals to withstand loss of cooling water due to loss of AC power for at least 2 hours. Clarifications were issued in NUREG-073798 to include all BWRs, W, and CE operating reactors, and all OL applicants.
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-53 was established by DL for implementation purposes.
ITEM II.K.3(26): STUDY EFFECT ON RHR RELIABILITY OF ITS USE FOR FUEL POOL COOLING
DESCRIPTION
This NUREG-066048 item was originated to affect GE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item II.E.2.1.
CONCLUSION
This item is covered in Item II.E.2.1.
ITEM II.K.3(27): PROVIDE COMMON REFERENCE LEVEL FOR VESSEL LEVEL INSTRUMENTATION
DESCRIPTION
This NUREG-066048 item affected all GE plants (OLs and OL applicants) and required all reactor vessel level instruments to be referenced to the same point. It was believed that different reference points of the various reactor vessel water level instruments could cause operator confusion. Either the bottom of the vessel or the active fuel were considered to be reasonable reference points. Clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-54 was established by DL for implementation purposes.
ITEM II.K.3(28): STUDY AND VERIFY QUALIFICATION OF ACCUMULATORS ON ADS VALVES
DESCRIPTION
This NUREG-066048 item affected all plants with GE reactors (OLs and OL applicants). These plants were required to assure that air or nitrogen accumulators for ADS valves had sufficient capacity to cycle the valves open five times at design pressure. However, clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-55 was established by DL for implementation purposes.
ITEM II.K.3(29): STUDY TO DEMONSTRATE PERFORMANCE OF ISOLATION CONDENSERS WITH NON-CONDENSIBLES
DESCRIPTION
This NUREG-066048 item affected all operating plants with GE isolation condensers. These plants were required to demonstrate the adequacy of isolation condensers with non-condensibles. Clarifications affecting all operating BWRs with isolation condensers were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-56 was established by DL for implementation purposes.
ITEM II.K.3(30): REVISED SMALL-BREAK LOCA METHODS TO SHOW COMPLIANCE WITH 10 CFR 50, APPENDIX K
DESCRIPTION
This NUREG-066048 item required all OLs and OL applicants to revise and submit for NRC approval the analyses used by NSSS vendors and/or fuel suppliers for SBLOCA analysis in compliance with 10 CFR 50, Appendix K. The revised analyses were to account for comparisons with experimental data, including data from the LOFT and semiscale test facilities. Clarifications were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-57 was established by DL for implementation purposes.
ITEM II.K.3(31): PLANT-SPECIFIC CALCULATIONS TO SHOW COMPLIANCE WITH 10 CFR 50.46
DESCRIPTION
This NUREG-066048 item required all OLs and OL applicants to submit for NRC approval plant-specific calculations using NRC-approved models for SBLOCA, to show compliance with 10 CFR 50.46. Clarifications were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-58 was established by DL for implementation purposes.
ITEM II.K.3(32): PROVIDE EXPERIMENTAL VERIFICATION OF TWO-PHASE NATURAL CIRCULATION MODELS
DESCRIPTION
This NUREG-066048 item was originated to require PWRs to provide experimental verification of two-phase natural circulation models. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item II.E.2.2.
CONCLUSION
This item is covered in Item II.E.2.2.
ITEM II.K.3(33): EVALUATE ELIMINATION OF PORV FUNCTION
DESCRIPTION
This NUREG-066048 item was originated to require PWRs (OLs and OL applicants) to evaluate elimination of the PORV function. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item II.C.1.
CONCLUSION
This item is covered in Item II.C.1.
ITEM II.K.3(34): RELAP-4 MODEL DEVELOPMENT
DESCRIPTION
This NUREG-066048 item was originated to address RELAP-4 model development in PWRs. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item II.E.2.2.
CONCLUSION
This item is covered in Item II.E.2.2.
ITEM II.K.3(35): EVALUATION OF EFFECTS OF CORE FLOOD TANK INJECTION ON SMALL BREAK LOCAs-
DESCRIPTION
This NUREG-066048 item was originated to evaluate the effects of core flood tank injection on SBLOCAs in B&W plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.1.
CONCLUSION
This item is covered in Item I.C.1.
ITEM II.K.3(36): ADDITIONAL STAFF AUDIT CALCULATIONS OF B&W SMALL-BREAK LOCA ANALYSES
DESCRIPTION
This NUREG-066048 item was originated to address B&W plants, but was determined to be covered by Item I.C.1 prior to the publication of NUREG-0660.48
CONCLUSION
This item is covered in Item I.C.1.
ITEM II.K.3(37): ANALYSIS OF B&W RESPONSE TO ISOLATED SMALL-BREAK LOCA
DESCRIPTION
This NUREG-066048 item was originated to analyze the response of B&W plants (OLs and OL applicants) to isolated SBLOCAs. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.1.
CONCLUSION
This item is covered in Item I.C.1.
ITEM II.K.3(38): ANALYSIS OF PLANT RESPONSE TO A SMALL-BREAK LOCA IN THE PRESSURIZER SPRAY LINE
DESCRIPTION
This NUREG-066048 item was originated to analyze the reponse of B&W plants (OLs and OL applicants) to a SBLOCA in the pressurizer spray line. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.1.
CONCLUSION
This item is covered in Item I.C.1.
ITEM II.K.3(39): EVALUATION OF EFFECTS OF WATER SLUGS IN PIPING CAUSED BY HPI AND CFT FLOWS
DESCRIPTION
This NUREG-066048 item was originated to evaluate the effects of water slugs caused by HPI and CFT flows in the piping of B&W plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.1.
CONCLUSION
This item is covered in Item I.C.1.
ITEM II.K.3(40): EVALUATION OF RCP SEAL DAMAGE AND LEAKAGE DURING A SMALL- BREAK LOCA
DESCRIPTION
This NUREG-066048 item was originated to evaluate RCP seal damage and leakage during a SBLOCA in B&W plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item II.K.2(16).
CONCLUSION
This item is covered in Item II.K.2(16).
ITEM II.K.3(41): SUBMIT PREDICTIONS FOR LOFT TEST L3-6 WITH RCPs RUNNING
DESCRIPTION
This NUREG-066048 item was originated to require B&W plants (OLs and OL applicants) to submit to the NRC predictions for LOFT Test L3-6 with RCPs running. However, prior to the publication of NUREG-0660,48 it was determined that the issued was being addressed by Item I.C.1.
CONCLUSION
This item is covered in Item I.C.1.
ITEM II.K.3(42): SUBMIT REQUESTED INFORMATION ON THE EFFECTS OF NON-CONDENSIBLE GASES
DESCRIPTION
This NUREG-066048 item was originated to require B&W plants (OLs and OL applicants) to submit to the NRC requested information on the affects of non-condensible gases. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.1.
CONCLUSION
The item is covered in Item I.C.1.
ITEM II.K.3(43): EVALUATION OF MECHANICAL EFFECTS OF SLUG FLOW ON STEAM GENERATOR TUBES
DESCRIPTION
This NUREG-066048 item was originated to evaluate the mechanical affects of slug flow on the steam generator tubes of B&W plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item II.K.2(15).
CONCLUSION
This item is covered in Item II.K.2(15).
ITEM II.K.3(44): EVALUATION OF ANTICIPATED TRANSIENTS WITH SINGLE FAILURE TO VERIFY NO SIGNIFICANT FUEL FAILURE
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to show that transients combined with the worst single failure would not result in significant fuel damage. Clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-59 was established by DL for implementation purposes.
ITEM II.K.3(45): EVALUATE DEPRESSURIZATION WITH OTHER THAN FULL ADS
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to analyze depressurization modes other than full ADS for possible inclusion in emergency procedures. Clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-60 was established by DL for implementation purposes.
ITEM II.K.3(46): RESPONSE TO LIST OF CONCERNS FROM ACRS CONSULTANT
DESCRIPTION
This NUREG-066048 item required all GE plants (OLs and OL applicants) to respond to concerns raised by ACRS consultants. Clarifications affecting all BWRs (OLs and OL applicants) were issued in NUREG-0737.98
CONCLUSION
This item is RESOLVED, requirements were issued, and MPA F-61 was established by DL for implementation purposes.
ITEM II.K.3(47): TEST PROGRAM FOR SMALL-BREAK LOCA MODEL VERIFICATION PRETEST PREDICTION, TEST PROGRAM, AND MODEL VERIFICATION
DESCRIPTION
This NUREG-066048 item was originated to require GE plants (OLs and OL applicants) to complete a test program for SBLOCA model verification. However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items I.C.1 and II.E.2.2.
CONCLUSION
This item is covered in Items I.C.1 and II.E.2.2.
ITEM II.K.3(48): ASSESS CHANGE IN SAFETY RELIABILITY AS A RESULT OF IMPLEMENTING B&OTF RECOMMENDATIONS
DESCRIPTION
This NUREG-066048 item was originated to require GE plants (OLs and OL applicants) to assess the change in safety reliability as a result of implementing the recommendations of the Bulletins and Orders Task Force (B&OTF). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items II.C.1 and II.C.2.
CONCLUSION
This item is covered in Items II.C.1 and II.C.2.
ITEM II.K.3(49): REVIEW OF PROCEDURES (NRC)
DESCRIPTION
This NUREG-066048 item was originated to address all W and CE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.9 for OLs and by Items I.C.8 and I.C.9 for OL applicants.
CONCLUSION
This item is covered in Items I.C.8 and I.C.9.
ITEM II.K.3(50): REVIEW OF PROCEDURES (NSSS VENDORS)
DESCRIPTION
This NUREG-066048 item was originated to address all W and CE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.9 for OLs and by Items I.C.7 and I.C.9 for OL applicants.
CONCLUSION
This item is covered in Items I.C.7 and I.C.9.
ITEM II.K.3(51): SYMPTOM-BASED EMERGENCY PROCEDURES
DESCRIPTION
This NUREG-066048 item was originated to address all W, CE, and GE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.C.9.
CONCLUSION
This item is covered in Item I.C.9.
ITEM II.K.3(52): OPERATOR AWARENESS OF REVISED EMERGENCY PROCEDURES
DESCRIPTION
This NUREG-066048 item was originated to address all GE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items I.B.1.1, I.C.2, and I.C.5.
CONCLUSION
This item is covered in Items I.B.1.1, I.C.2, and I.C.5.
ITEM II.K.3(53): TWO OPERATORS IN CONTROL ROOM
DESCRIPTION
This NUREG-066048 item was originated to address all GE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.A.1.3.
CONCLUSION
This item is covered in Item I.A.1.3.
ITEM II.K.3(54): SIMULATOR UPGRADE FOR SMALL-BREAK LOCAs
DESCRIPTION
This NUREG-066048 item was originated to address all plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Item I.A.4.1.
CONCLUSION
This item is covered in Item I.A.4.1.
ITEM II.K.3(55): OPERATOR MONITORING OF CONTROL BOARD
DESCRIPTION
This NUREG-066048 item was originated to address all W and CE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items I.C.1, I.D.2, and I.D.3.
CONCLUSION
This item is covered in Items I.C.1, I.D.2, and I.D.3.
ITEM II.K.3(56): SIMULATOR TRAINING REQUIREMENTS
DESCRIPTION
This NUREG-066048 item was originated to address all W and CE plants (OLs and OL applicants). However, prior to the publication of NUREG-0660,48 it was determined that the issue was being addressed by Items I.A.2.6 and I.A.3.1.
CONCLUSION
This item is covered in Items I.A.2.6 and I.A.3.1.
ITEM II.K.3(57): IDENTIFY WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS
DESCRIPTION
This NUREG-066048 item required all operating GE plants to revise their emer-gency procedures to include verification that low pressure cooling systems are available prior to manual ADS. For OL applicants, the issue was determined to be covered by Item I.C.1. Clarifications affecting all operating BWRs were issued in NUREG-0737.98
CONCLUSION
This item was RESOLVED, requirements were issued, and MPA F-62 was established by DL for implementation purposes.
REFERENCES
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