NRC Generic Letter 80-61, TMI-2 Lessons Learned
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GL80061
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555
July 2, 1980
TO ALL PRESSURIZED WATER REACTOR LICENSEES
The staff has completed its evaluation of the actions you have taken to satisfy the Category "A" items of our recommendations resulting from TMI-2 Lessons Learned. Our evaluation was previously forwarded.
Under the provisions of 10 CFR Part 50.36(d)(3) and in order to provide reasonable assurance that your facility operation is maintained within the limits determined acceptable following the implementation of the TMI-1 Lessons Learned Category "A" item, we have prepared the enclosed model Technical Specifications (TSs). These model specifications are intended to provide guidance in the scope and types of required specifications for each facility in the areas of equipment and administrative requirements including actions we consider appropriate if a limiting condition for operation cannot be met.
The proposed specifications for your facility involve:
- (1) Emergency Power Supply Requirements
The pressurizer water level indicators, pressurizer relief and block valves, and pressurizer heaters are important in a post-accident situation. Adequate emergency power supplies ensure post-accident functioning of these components. The enclosed specifications will satisfy our requirements.
- (2) Valve Position Indication
The installed system for indication of valve position is a diagnostic aid to the operator. Although the indicating system provides no automatic action, we believe that this system should be operable and that periodic surveillance should be performed.
- (3) Instrumentation for Inadequate Core Cooling
- (4) Containment Isolation
We believe your specifications should include a Table of Containment Isolation Valves which reflect the diverse isolation signals which your design currently provides. Sample specifications and associated surveillance are included.
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- (5) Auxiliary Feedwater Systems
These specifications treat both initiation and indication of auxiliary feedwater flow.
- (6) Shift Technical Advisor
The specification related to minimum shift manning should be revised to reflect the augmentation of a Shift Technical Advisor.
Enclosure
- (1) uses the Standard TS format with blanks or parentheses appearing where the information is plant specific. It includes appropriate pages as background information for facilities that do not have Standard TS.
In addition to the specifications discussed above, we believe that your license should be amended by adding license conditions related to a System Integrity Measurements Program and Improved Iodine Measurements capability. Proposed wording of these conditions is enclosed as Enclosure 2.
We request that you submit a license amendment application to incorporate the applicable specifications of the enclosed guidance into your Appendix "A" TSs within 60 dAys following receipt of this letter. The staff has determined that such an amendment is in the public interest and is exempt from fee per 10 CFR 170.11, provided the application is consistent with the enclosed guidance.
If you have any questions on this matter please contact your Operating Reactors Project Manager.
Sincerely,
Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
Enclosures:
- 1. Model TSs
- 2. Proposed Wording of Conditions
cc w/enclosures:
service lists
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Enclosure 2
MODEL LICENSE CONDITIONS FOR NUREG-0578 TMI-2 LESSONS LEARNED
CATEGORY "A" ITEMS
Systems Integrity
The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactivity fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
1. Provisions establishing preventive maintenance and periodic visual inspection requirements, and
2. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
Iodine Monitoring
The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions, This program shall include the following:
1. Training of personnel,
2. Procedures for monitoring, and
3. Provisions for maintenance of sampling and analysis equipment.
Backup Method for Determining Subcooling Margin (OPTIONAL)
The licensee shall implement a program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall include the following:
1. Training of personnel, and
2. Procedures for monitoring.
LL/STS - PWR