ML19323E844
| ML19323E844 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/29/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323E818 | List: |
| References | |
| 50-338-79-49, NUDOCS 8005270313 | |
| Download: ML19323E844 (2) | |
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h APPENDIX A NOTICE OF VIOLATION Virginia Electric and Power Company License No. NPF-4 North Anna Based on the NRC inspection December 17-21, 1979, certain of your activities were apparently not conducted in full compliance with NRC requirements as indicated below. These items have been categorized as described in correspondence to you dated December 31, 1974.
A.
As required by 10 CFR 50, Appendix B, Criterion V as implemented by the l
accepted quality assurance program, VEP-1-3A, Section 17.2.12, "A program with applicable procedures has been established in the Nuclear Power Station Quality Assurance Manual (NPSQAM) that describes control of measuring and i
test instruments which includes handling of associated documents and gives the status of all items under the calibration system such as maintenance history, calibration test data, and individual log sheets assigned to each device." The NPSQAM, Section 12, Paragraph 4.3 states that the cognizant supervisor shall establish and maintain usage information of a device in the program. Section 12.4.4 of the manual states that the supervisor of the individual performing a calibration shall maintain a maintenance history record for each device in the program.
Contrary to the above, usage information had not been established and main-tained for four torque wrenches (NQC 561, 526, 585, and 586) which were in the measuring and test equipment calibration program. A complete calibration history for each device was not maintained by the cognizant supervisor.
This is a deficiency.
B.
As required by Technical Specifications Sections 4.0.2.a. and 4.7.14.1.1.c.,
the Fire Suppression Water System shall be demonstrated operable at least once per 31 days with a maximum allowable extension not to exceed 25% of the surveillance interval by verifying that each valve in the flow path is in its correct position.
Contrary to the above, periodic test procedure PT-100.3 (Fire Suppression Water System - Valve Position Verification) was not performed between 8/12/79 and 10/13/79.
This is an infraction.
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Virginia Electric and Power Company Appendix A North Anna Notice of Violation C.
As required by 10 CFR 50, Appendix B, Criterion V as implemented by the accepted quality assurance program, VEP-1-3A, Section 17.2.11, The auth-ority and responsibilities related to the test program are delineated in the Nuclear Power Station Quality Assurance Manual (NPSQAM). NPSQAM Section 11, Paragraph 5.3.5 states that the cognizant supervisor and performance engineer are responsible for reviewing a periodic test (PT), including critique sheet and procedure, for completeness and accuracy.
Contrary to the above, various calculational mistakes were contained in the data sheets of PT-11 (Core Reactivity Balance) which was performed on 2/22/79; PT-20.2 (Axial Flux Difference) which was completed on 3/1/79; PT-31.1.1 (Delta T/T Avg Protection Channel 1 Functional Test - T412) which was performed on 6/14/79; PT-11 which was completed on 6/18/79, and PT-24 (Calorimetric) which was performed on 9/21/79. Although these documents had received two levels of review, the errors / mistakes had not been identi-fied.
This is an infraction.
D.
As required by Technical Specification 6.8.1.c, written procedures shall be established, implemented and maintained, covering the activities concerning surveillance and test of safety related equipment. Step 4.7.a of PT 75.2B (Service Water Pump, 1-SW-P-1B) states in part, "If deviations fall within the Alert Range, double the frequency of testing..."
Step 5.1 of the pro-cedure states that a flow shall be indicated in step 4.1 as an acceptance criteria.
Contrary to the above, the test results fell within the alert range when conducted on May 24, 1979, but the test frequency was not doubled.
In addition, pump flow was not recorded in Step 4.1.
This is an infraction.
b
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