| TRAINING: |
TTC course G-200 is required for implementing the inspection requirements of the revised reactor oversight process.
This training course has been held in all the regional offices and the training center at TTC, and will continue to be
offered at the technical training center. |
| REMARKS: |
The following procedures comprise the risk-informed baseline inspection program. The baseline inspection program
provides the minimum inspection oversight for determining, along with performance indicators, the safety performance
of operating nuclear power reactors. |
|
Major changes from the draft procedures that were used during the pilot program are: |
|
IP 71111: |
Attachment 3 (emergent work) was removed and its
requirements added to Attachment 13; Attachments 9
(inservice testing) and 10 (large containment isolation
valves) were removed and some of their requirements
added to other attachments. The scope of Attachment 2
(changes to license conditions) was changed to cover only
10 CFR 50.59 evaluations, the requirements for emergency
and security plan changes were added to their respective
cornerstone procedures, and the title changed to reflect the
new scope. |
|
IP 71114: |
Two new attachments were added to better clarify the
scope and requirements for this procedure; Attachment 5
(correction of weaknesses and deficiencies) and
Attachment 6 (drill evaluation). Attachment 4 (action level
and plan changes) was changed to incorporate the
emergency preparedness requirements from 71111.02. |
|
IP 71121: |
The frequency for Attachment 2 (ALARA) was changed to
biennially to give the regions flexibility in scheduling the
procedure's requirements during periods of higher risk and
opportunities for inspection. |
|
IP 71130: |
Attachment 04 (Security Plan Changes) was added to
include the security requirements for plan changes that
were in 71111.02. |
|
IP 71150: |
Plant status requirements and guidance for resident
inspectors have been moved to Appendix D of IMC 2515
and the procedure has been removed from the baseline
inspection program. This change reflects the policies that
residents have functions beyond inspection and plant status
is used for preparing the resident inspectors in conducting
the other baseline inspection procedures. |
|
IP 71153: |
Event follow up requirements for the baseline inspection
program were changed to reflect risk informing the
agency's criteria for determining those events that need
additional follow up by the agency. |
|
BASELINE INSPECTION PROGRAM PROCEDURES |
|
IP 71111 |
(Reactor Safety-Initiating Events, Mitigating Systems,
Barrier Integrity) |
|
IP 71111.01 |
(Adverse Weather Protection) |
|
IP 71111.02 |
(Evaluation of Changes, Tests, or Experiments) |
|
IP 71111.04 |
(Equipment Alignment) |
|
IP 71111.05 |
(Fire Protection) |
|
IP 71111.06 |
(Flood Protection Measures) |
|
IP 71111.07 |
(Heat Sink Performance) |
|
IP 71111.08 |
(Inservice Inspection Activities) |
|
IP 71111.11 |
(Licensed Operator Requalification) |
|
IP 71111.12 |
(Maintenance Rule Implementation) |
|
IP 71111.13 |
(Maintenance Risk Assessments and Emergent Work
Evaluation) |
|
IP 71111.14 |
(Personnel Performance During Nonroutine Plant
Evolutions) |
|
IP 71111.15 |
(Operability Evaluations) |
|
IP 71111.16 |
(Operator Workarounds) |
|
IP 71111.17 |
(Permanent Plant Modifications) |
|
IP 71111.19 |
(Post Maintenance Testing) |
|
IP 71111.20 |
(Refueling and Outage Activities) |
|
IP 71111.21 |
(Safety System Design and Performance Capability) |
|
IP 71111.22 |
(Surveillance Testing) |
|
IP 71111.23 |
(Temporary Plant Modifications) |
|
IP 71114 |
(Reactor Safety-Emergency Preparedness) |
|
IP 71114.01 |
(Exercise Evaluation) |
|
IP 71114.02 |
(Alert and Notification System Testing) |
|
IP 71114.03 |
(Emergency Response Organization Augmentation
Testing) |
|
IP 71114.04 |
(Emergency Action Level and Emergency Plan Changes) |
|
IP 71114.05 |
(Correction of Emergency Preparedness Weaknesses and
Deficiencies) |
|
IP 71114.06 |
(Drill Evaluation) |
|
IP 71121 |
(Occupational Radiation Safety) |
|
IP 71121.01 |
(Access Control To Radiologically Significant Areas) |
|
IP 71121.02 |
(ALARA Planning and Controls) |
|
IP 71121.03 |
(Radiation monitoring Instrumentation) |
|
IP 71122 |
(Public Radiation Safety) |
|
IP 71122.01 |
(Radioactive Gaseous and Liquid Effluent Treatment and
Monitoring Systems |
|
IP 71122.02 |
(Radioactive Material Processing and Transportation) |
|
IP 71122.03 |
(Radiological Environmental Monitoring Program
(REMP)) |
|
IP 71130 |
(Physical Protection) |
|
IP 71130.01 |
(Access Authorization (AA) Program (Behavior
Observation Only)) |
|
IP 71130.02 |
(Access Control (Search of Personnel, Packages, and
Vehicles: Identification and Authorization)) |
|
IP 71130.03 |
(Response to Contingency Events (Protective Strategy and
Implementation of Protective Strategy)) |
|
IP 71130.04 |
(Security Plan Changes) |
|
IP 71151 |
(Performance Indicator Verification) |
|
IP 71152 |
(Identification and Resolution of Problems) |
|
IP 71153 |
(Event Followup) |
|
SUPPLEMENTAL PROCEDURES |
|
The following inspection procedures are to be used to assess performance issues that have been identified as being risk
significant by the Significance Determination Process or when a performance indicator exceeds the "licensee response
band" threshold. The specific procedures chosen for implementation will be based upon guidance contained in the
NRC's assessment Action Matrix and the Supplemental Inspection Table included in Appendix B to IMC 2515. |
|
IP 93800 |
(Augmented Inspection Procedure) |
| IP 93812 |
(Special Inspection) |
| IP 95001 |
(Inspection For One Or Two White Inputs In A Strategic
Performance Area) |
| IP 95002 |
(Inspection For One Degraded Cornerstone Or Any Three
White Inputs In A Strategic Performance Area) |
| IP 95003 |
(Inspection For Repetitive Degraded Cornerstones,
Multiple Degraded Cornerstones, Multiple Yellow Inputs,
Or One Red Input) |
| DISTRIBUTION: |
Standard |
|