ML20151W416

Notice of Violation from Insp on 880201-05.Violations Noted: Appropriate Qualitative & Quantitative Criteria for Removing Corrosion Byproducts Not Applied to Battery Terminals & No Procedures Written for Breakers

ML20151W416
Person / Time
Site:	Pilgrim
Issue date:	04/27/1988
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20151W397	List: IR 05000293/1988008 ML20151W394 ML20151W416
References
50-293-88-08, 50-293-88-8, NUDOCS 8805030393
Download: ML20151W416 (2)

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APPENDIX A NOTICE OF VIOLATION i Boston Edison Company Docket No. 50-293 l Pilgrim Nuclear Pow 6r Station License No. DPR-35 As a result of the inspection conducted on February 1-5, 1988, and in l accordance with the "General Statement of Policy and Procedure for NRC Enforce-ment Actions," 10 CFR Part 2, Appendix C (Enforcement Policy), the following violations were identified:

1. 10 CFR 50 Appendix B Criterion V requires that activities affecting quality shall be prescribed by documented procedures which include appropriate quantitative or qualitative acceptance criteria for '

determining that important activities have been satisfactorily accomplished.

The Pilgrim Nuclear Power Station Safety related battery ranufacturer's instruction manual 12-800 "C&D Power Systems stationary battery Instal-lation and Operating instructions manual" section 9.3 requires all corrosion by products be removed and to check torque values to be 125 inch pound at battery connections and section 3.2.3 requires seismic support side ratis be very close to the battery with a gap just enough to permit an index card to be inserted.

Contrary to be above, on February 2, 1988, the licensee Procedures 8.C14 I Revision 20, September 16, 1987 "Weekly Pilot Cell And Overall Battery Check" and 8.C16 Revision 14, October 5,1987 "Quarterly Battery Cell Surveillance" did not include the appropriate qualitative and quantitative criteria for removing corrosicn by products, specifying torque values at the battery connections, and establishing the gap between seismic support rails and the battery jars, and it was observed that the battery terminals were corroded at cells 31 through 60 and cell 3 at Battery 02, cell 43 on Battery 01, cell 40 on Battery D3, and there was an excessive gap between the seismic support rail and the battery cell at cell 91 on Battery 03.

This is a Severity Level IV violation (Supplement 1). ,

2. Licensee Technical Specification Section 6.8A requires that written I procedures be established, implemented, and maintained that meet or exceed the requirements of ANSI N18.7-1972 and Appendix A of USNRC Regulatory

, Guide 1.33, Paragraph 5.3.6 of ANSI N18.7-1972 which requires that pro-  ;

cedures be provided for the periodic calibration and testing of safety related protective circuits. RG 1.33 Appendix A Section S(2)(q) requires calibration for emergency power tests.

OFFICIAL RECORD COPY IR PILGRIM 88 0003.1.0 04/22/88 8805030393 880427 PDR ADOCK 05000293 0 DCD

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- Appendix A 2 Contrary to the above on February 2,1988, the safety related 125 and 250 Volt DC safety related circuit breakers utilized in DC Motor Control Centers 05, 06, 08, 09, 010, 017 and 037 did not have written test pro-cedures for calibration and testing of safety related protective circuits and were not tested or calibrated to demonstrate their safety related function.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Boston Edison Company is nereby required to submit to this office within thirty days of the date of the letter which transmitted this Notice, 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 violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.

OFFICIAL RECORD COPY IR PILGRIM 88 0003.2.0 04/22/88 s

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