ML20039G874
| ML20039G874 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/28/1981 |
| From: | Miller L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039G873 | List: |
| References | |
| 50-206-81-40, NUDOCS 8201190250 | |
| Download: ML20039G874 (2) | |
Text
,
APPENDIX A NOTICE OF VIOLATION t
Southern California Edison Company Docket No. 50-206/81-40 San Onofre Nuclear Generating Station.
License DPR-13 Unit l '
As a result of the inspection conducted on !!ovember 2 to flovember 24, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754
{
(October 7,1980) the following violations were identified.
1.
Technical Specification 6.8.1 requires that written procedures be established, implemented and maintained that meet or exceed the requirements and recem.cndations of Section 5.1 and 5.3 of ANSI N18.7-1976, " Administrative Controls for Nuclear Power Plants."
a.
ANSI N18.7-1976, Paragraph 5.3.7, " Calibration and Test Procedures,"
states that " Procedures shall be provided for periodic calibra-tion and testing of safety related instrumentation and control systems...The procedures shall provide for... assuring measure-ment accuracy adequate to keep safety related paramenters l
within operational and safety limits."
\\
I Contrary to this requirement, procedures were not provided for I
periodic calibration of the hydraulic accumulator and manifold pressure indicators for the safety injection system hydraulic valve actuators since their installation in 1977.
This is a Severity Level V violation.
b.
AliSI N18.7-1976, Paragraph 5.3.4.4, " Process Monitoring Procedures" states that " Procedures for monitoring performance of plant l-systems shall be required to assure that... engineered safety features and emergency equipment are in a state of readiness i
to maintain the plant in a safe condition if needed. The i
l limits (maximum and minimum) for significant process parameters l
shall be identified."
l Contrary to this requirement, on November 18, 1981, while in Mode 1. no procedures identified nitrogen battle pressure as a significant process parameter (as a backup power source) for the air-operated auxiliary feedwater system valves, pressurizer power operated relief valves and relief valve block valves.
Further, no procedures identified measures to ensure that the nitrogen bottle pressure was in an appropriate state of readiness for operation in Mode 1.
I This is a Severity Level V Violation.
i i
S201190250 811231
~
PDR ADOCK 05000206 G
N i
. l Pursuant to the provisions of 10 CFR 2.201, the Southern California I
Edison Company is hereby required to submit to this office within twenty-five days of the date of this flotice, a written statement or explanation in reply, including; (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further itens 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 l
submitted under cath or affirmation.
DEC 311981 l3/12 /Ri
)f/m n,
Dates
//1.. F.' R111er v Sr. Reactor Inspector i
l l
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