ML20154B022

Notice of Violation from Insp on 880120-0305.Violation Noted:Implementation & Testing of Certain Mods Not Properly Preplanned & Performed in Manner to Assure Quality

ML20154B022
Person / Time
Site:	Pilgrim
Issue date:	05/06/1988
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20154B016	List: IR 05000293/1988007 ML20154B012 ML20154B022 ML20154B051
References
50-293-88-07, 50-293-88-7, NUDOCS 8805170034
Download: ML20154B022 (2)

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, APPENDIX A NOTICE OF VIOLATION Boston Edison Company Docket No. 50-293 Pilgrim Nuclear Power Station License No. DPR-35 As a result of the inspection conducted on January 20 to March 5,1988 and in accordance with the NRC Enforcement Policy (10 CFR 2, Apoendix C), the follow-ing violation was identified. In both the cited instances, prompting by the NRC inspector was required to avoid additional unplanned ESF actuations which would have resulted from continuing activities as specified in licensee-approved procedures and instructions.

Technical Specification 6.8.A, states that written procedures shall be established and implemented that meet the requirements and recommendations of sections 5.1 and 5.3 of ANSI N18.7-1972.

ANSI N18.7-1972, Section 5.1, states that policies shall be provided to control the issuance of documents, including maintenance or modification procedures. These policies shall assure that documents are reviewed for adequacy. Section 5.1.6 states that maintenance and modifications that may affect functioning of safety-related systems shall be performed in a manner to assure quality, and shall be properly preplanned and performed in accordance with detailed written procedures.

Contrary to the above, implementation and testing of certain modifications was not properly preplanned and was not performed in a manner to assure quality. Further, established policies did not assure that procedures were properly reviewed for adequacy, in that approved modifications pro-cedures were found to be technically inadequate.

1. On February 2,1988, instructions contained in approved Plant Design Change (PDC)83-510 for installation of computer point ISO 726 were inadequate. The computer signal cut-in sheet for ISO 726 did not specify adequate steps to prevent interruption of a common grouno' in the containment isolation system logic. As a result, unanticipated Engineered Safety Feature (ESF) actuations occurred during perform-ance of the cut-in.

2. On February 10, 1988, approved post-modification test Procedure TP 88-09, Electrical Plant Line-up for Blackout Diesel Generator Load Test, Revision 0, was inadequate. Performance of TP88-09 as wri t ten and approved would have resulted in an unanticipated automatic start of the "B" Emergency Diesel Generator (EDG).

Adequate steps to prevent or to prepare for the EDG start were not included.

This is a Severity Leval IV Violation (Supplement I).

0FFICIAL RECORD COPY IR PILGRIM 88 0004.0.0 05/05/88 8805170034 890506 PDR ADOCK 0500g2J3 _ _ _

C Appendix A 2 Pursuant to the provisions of 10 CFR 2.201, Boston Edison Company is hereby required to submit to this office within thirty days from the receipt of the letter win,;h transmit +.ed this Notice, a written statement or explanation d reply, including: (1) the corrective steps which have been taken and t;,

results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response ti .ie .

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! 0FFICIAL RECORD COPY IR PILGRIM 88 0005.0.0 04/14/88

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