Protecting People and the EnvironmentUNITED STATES NUCLEAR REGULATORY COMMISSION
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.
.
-2-
(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
.
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