ML19207A805
| ML19207A805 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/08/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19207A800 | List: |
| References | |
| 50-338-79-25, 50-339-79-34, NUDOCS 7908220412 | |
| Download: ML19207A805 (1) | |
Text
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APPENDIX A NOTICE OF VIOLATION Virginia Electric and Power Company License Nos. NPF-4 &
North Anna Units 1 & 2 CPPR-78 Based on the NRC inspection May 7-11, 1979, certain of your activities were apparently not conducted in full compliance with NRC requirements as indicated below. These items have been categorized as dercribed in correspondence to you dated December 31, 1974.
A.
As required by 10 CFR 50 Appendix B Criterion 21 which states in part; " Test results shall be documented and evaluated to assure that test requirements have been met."
This requirement is further defined in VEP-1-3A, Topi-al Report Quality Assurance Program Operations Phase, Section 17.2.11, and the Nuclear Power Station Quality Assurance Manual, Section 11, paragraph 5.1.1.d.,
which requires "The Supervisor - Engineering Services, the Joint Test Group, and the Station Nuclear Safety and Operating Committee shall be responsible for reviewing the test results and determining if the results meet the established acceptance criteria..."
Contrary to the above, 2-P0-11.1 Component Cooling System Test At Ambient Plant Conditions, reshlts approved January 12, 1979, indicated that the data obtained for pumps 2-CC-P-1A and 2-CC-P-1B met the acceptance criteria of paragraph 5.1.
The acceptance criteria required pump flow of 8000 gpm at a 200 ft. pump head.
The data indicated an unsatisfactory head of 198.7 f t. for 8000 gpm flow for each pump.
This is an infraction, and is applicable,to Unit 2.
A simi?ar item was brought to your attention in our letter dated November 14, 1978.
B.
As required by Technical Specification 6.8.3.c, temporary changes to surveil-lance procedures of safety related equipment shall be documented, reviewed by the Station Nuclear Safety and Operating Committee (SNSOC) and approved by the Station Manager within 14 days of implementation.
Contrary to the above, a temporary change to acceptance criteria step 5.3 of periodic test 1-PT-76.5 on Control Room Emergency Ventillation filter testing, conducted on March 29, 1979, was not documented, reviewed by the SNSOC, or approved by the Station Manager as of May 9,1979.
This is a deficiency, and is applicable to Unit 1.
A similar item was brought to your attention in our letter dated November 14, 1978.
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