ML20054C308
| ML20054C308 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/26/1982 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20054C304 | List: |
| References | |
| IP-JAS-554, NUDOCS 8204200336 | |
| Download: ML20054C308 (2) | |
Text
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'N POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. BOX 215 BUCHANAN, N. Y.10511 T EL E PH O N E: 914 739-8200 S
March 26, 1982 IP-JAS-554 Docket No. 50-286 License No. DPR-64 Mr.
R. W. Starostecki, Director Division of Resident and Project Inspection U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
Inspection 50-286/82-01
Dear Mr. Starostecki:
This letter responds to your Inspection Report No. 50-286/
82-01 dated February 24, 1982 and received at this office on March 2, 1982.
Attachment I to this letter responds to Appendix A of your letter.
Very truly yours, n
Yi
- John C. Brons
' Resident Manager JAS/bam Attachment cc: Acting Chief Indian Point, W. Baunack Resident Inspector, T. Kenny SUBSCRIBED AND SWOR TO BEFORE ME IS T AY
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w e-Attachment.1 Violation 10 CFR 50.59 permits the' licensee to make changes to the facility as described in the Safety Analysis Report without prior Com-mission approval, provided the licensee maintains records of the changes.
These records _shall include a written safety evaluation which provides'the' basis for the determination that the change does not involve an unreviewed safety question.
Contrary to the above, on February 9,.1982, changes to the facility, as' described in the Safety Analysis Report, were identified for which no written safety evaluation was prepared.
These changes were the addition of a valve in line with the nitrogen. regulator which supplies the -isolation valve seal water system (IVSWS), a technical specification required system, and the addition of a 3/8 inch line which connects the IVSWS to the main nitrogen header.
Response
'The IVSWS was restored to the condition described in the FSAR. A design change (MOD 82-03-036N ) and safety evaluation 2
(NSE 82-03-036N ) were written to address the change.
The Plant 2
Operating Review Committee (PORC) reviewed the design change and concurred that it does not constitute any unreviewed safety ques--
tions. The design change was approved and subsequently installed l.
in the IVSWS.
To prevent further violations, appropriate plant personnel have been counseled on the importance and necessity of following administrative requirements concerning plant modifications.
In i
addition, department superintendents have been instructed to i
reemphasize the importance of adherence to station administrative l
procedures to all members of-their departments.
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