ML13323B082
| ML13323B082 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/27/1986 |
| From: | Chaffee A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Baskin K SOUTHERN CALIFORNIA EDISON CO. |
| Shared Package | |
| ML13323B084 | List: |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 8602130541 | |
| Download: ML13323B082 (2) | |
See also: IR 05000206/1985037
Text
'JA
JN,719 8 6
Docket Nos. 50-206,
50-361 and 50-362
Southern California Edison Company
2244 Walnut Grove Avenue
Rosemead, California 91770
Attention:
Mr. Kenneth P. Baskin, Vice President
Nuclear Engineering Safety and Licensing Department
Gentlemen:
Subject: NRC Inspection of San Onofre Units 1, 2 and '3
This refers to the inspection conducted by Mr. P. P. Narbut of this office on
November 12-15 and December 9-18, 1985, of activities authorized by NRC
License Nos. DPR-13, NPF-10 and NPF-15 and to the discussion of our findings
with Mr. Ray and other members of your staff on November 15 and December 18,
1985. Additionally,.this report describes in-office review of San Onofre
event reports conducted through December 30, 1985.
Areas examined.during this inspection are described in the enclosed inspection
report. Within these areas, the. inspection consisted of selective
examinations of procedures and representative records, interviews with
personnel, and observations by the inspector.
Based on the results of this inspection, it appears that one of your
activities was not conducted in full compliance with NRC requirements, as set
forth in the Notice of Violation,*enclosed herewith as Appendix-A.
Your response to this Notice is to be submitted in accordance with the
provisions of 10 CFR 2.201 as stated in Appendix A, Notice of Violation.
Your attention is'
also directed to two important general.areas discussed in
this report: (1) the necessity to ensure procedure compliance at the
implementation level as discussed in paragraph 3.a using an example of main
steam safety valve test documentation and (2) the necessity to ensure
maintenance personnel awareness of design issues as discussed in paragraph 5.b
using the example of pipe clamp bolting torque values. No additional response
to these issues are required since your expected response to the Unit 1
auxiliary feedwater pump violation of report 50-206/85-33 should address these
issues.
In accordance with 10 CFR 2.790(a), a copy of this letter, the enclosure, and
your response will be placed in the NRC Public Document Room.
_____54_
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Southern California Edison Company
2
Should you have any questions concerning this inspection, we will be glad to
discuss them with you.
The responses directed by this letter and the accompanying Notice are not
subject.to the clearance proceduressof the Office of Management and Budget as
required by the Paperwork Reduction Act of 1980, PL 96-511.
Sincerely,
A. E. Chaffee, Chief
Reactor Projects Branch
Enclosures:
1. Appendix A -
2. Inspection Report
Nos. 50-206/85-37,. 50-361/85-35, 50-362/85-34
cc w/enclosures:.
D. J. Fogarty, SCE
H. B. Ray, SCE (San Clemente)
H. E. Morgan, Station Manager
State of CA
bcc:
RSB/Dcoument Control Desk (RIDS)
Mr. J. Martin
Mr. B. Faulkenberry
G. Cook
Resident Inspector
Project Inspector
RV
P~rbtdh
Pohnson
Ao son
AChaffee
1/
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1/UVf86
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