ML20049J860
| ML20049J860 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/03/1982 |
| From: | Miller L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20049J857 | List: |
| References | |
| 50-206-82-04, 50-206-82-4, NUDOCS 8203290165 | |
| Download: ML20049J860 (2) | |
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APPENDIX A NOTICE OF VIOLATION 1
Southern California Edison Company Docket No. 50-206 San Onofre Nucicar Generating Station, License No. DPR-13 Unit 1 As a result'of the inspection conducted on January 4, to January 29, 1982, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980) the following violations were identified.
?
A.
" Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." Criterion III, Design Control, requires that field changes shall be subject to design control measures commensurate with those applied to the original design; and Criterion XI, Test Control, requires testing to demonstrate that systems will perform satisfactorily in service.
The licensee's Quality Assurance Manual implements these requirements in Paragraph 5.1.1 by endorsing ANSI N 18.7-1976.
Paragraph 5.2.7 of that standard requires that means for assuring the quality of modification activities and measures to document the performance thereof shall be established.
Contrary to these requirements, the seal flushing line to each refueling water pump (line 8007 on Drawing 568776-17) was cut between April 25, 1980, and January 18, 1981, thereby creating two unmonitored potential leakage points from the recirculation loop outside of containment.
No design review or post-modifica-tion testing was performed for this modification.
This is a Severity Level 4 violation.
(Supplement I) 3 f
B.
Technical Specification 6.8.1 requires that written procedures be 4
established, implemented and maintained that meet or exceed the 1
requirements and recommendations of Section 5.1 and 5.3 of ANSI N 18.7-1976, " Administrative Controls for Nuclear Power Plants."
ANSI N 18.7-1976, Paragraph 5.3.2,
" Procedure Content," requires that procedures contain, where applicable, acceptance criteria against which the success or failure of test-type activity would be judged.
Contrary to this requirement, the reactor plant in-strument calibration procedure, S01-II-1.4, performed in May and June, 1981, did not contain acceptance criteria for instrumenta-tion trip setpoints.
This is a Severity Level 5 violation.
(Supplement I) 4 O
~l
S 1
Pursuant to the provisions of 10 CFR 2.201, the Southern California Edison Company is hereby required to submit to this office within twenty-five days of the date of this Notice, a written statement or explanation in reply, including: (1) the torrective steps which have been taken and the results achieved; (2) corrective steps 4
which will be taken to avoid further items of noncompliance; and (3) the date when full compliance will be achieved.
Under the authority of Section,182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Original signed by fiarch 3,1982 G. B. Zwetzig for (DATE)
L.
F.
Miller 1
Sr. Resident Inspector a
4 4
4 I
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