ML20154B169

Notice of Violation from Insp on 880207-0319.Violations Noted:Licensee Failed to Take Prompt Corrective Action to Address Angular Misalignment of Snubber NQ-2-S8,which Exceeded Mfg & Procedural Requirements

ML20154B169
Person / Time
Site:	Oyster Creek
Issue date:	05/09/1988
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20154B164	List: IR 05000219/1988004 ML20154B160 ML20154B169
References
50-219-88-04, 50-219-88-4, NUDOCS 8805170095
Download: ML20154B169 (2)

Text

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,i APPENDIX A NOTICE OF VIOLATION GPU Nuclear Corporation Docket No. 50-219-Oyster Creek Nuclear Generating Station License No. OPR-16 As a result of the inspection conducted February 7 - March 19, 1988, and in ac-cordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), the following violations were identified:

A. Technical Specification 6.8.1 requires that written procedures shall be es-tablished, implemented, and maintained.

Station Procedure 130, Conduct of Independent Safety Reviews and Responsible Technical Reviews by Plant Review Group states, revfews are to be accomplished on a timely manner and that records of reviews are pecpared, distributed and maintained. In addition, Station Procedure 103 Station Document Control states, "The review cycle of documents should be thorough and expeditious."

Contrary to the above, a review of Station Procedure 301 Nuclear Steam Supply System, step 2.2.1, states the pressure across the main steam isolation valves will be equalized to S 200 psid prior to opening during a restart with the reactor vessel pressurized but, Station Procedure 201.2, Plant Heatup to Hot Standby, step 3.1.5, states the pressure across the isolation valves will be equalized to S 50 psid prior to opening during restart with the reactor vessel pressurized. A procedure change request to correct this discrepancy written on August 18, 1987 had .1ot been completed as of March 1, 1988.

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

B. Technical Specifications 6.8.1 requires that written procedures shall be es-tablished, implemented and maintained. Station Procedure 675.1.001, Revision 14, Inspection of Bergen-Patterson Hydraulic Snubbers, requires, in part,

...the components tested by this procedure meet Technical Specification re-quirements for operability if the following criteria are met. If any are not met consider the affected components inoperable and follow the requirements of Technical Specification section 3.5.A.8 and Procedure 104... The snubber or its mounting hardware has no defects which would affect operation of the snubber and no defects that cannot be corrected with the snubber in place."

Contrary to the above, snubbers NQZ-1-58, NQZ-1-S9, NQZ-1-S10, and NQZ-1-S12 had all been replaced and deficiencies in their mounting hardware corrected on or before February 2,1988 without declaring the snubbers inoperable as required by the station procedure during the time they were out of the system for repair.

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

OFFICIAL RECORD COPY DL50-219/88 0003.0.0 05/02/88 8805170095 880309 PDR ADOCK 05000219 Q DCD _ _ _ _ _ _ _ _ _ _ _ _

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C. 10 CFR 50, Appendix B, Criterion 16 and Section 8.0 of the Operational Quality Assurance Plan for Three Mile Island Unit 1 and Oyster Creek Nuclear Stations require, in part, that measures shall be. established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly. identified and corrected.

Contrary _to the above, the licensee has failed to take prompt corrective ac .

tion to address an angular misalignment of. snubber NQ-2-S8, which. exceeded manufacturer and procedural requirements. This nonconformance was identified on November 11, 1986 and again on December. 16, 1987 during visual snubber surveillances conducted in accordance with Station Procedure 675.1.001. As of February 23, 1988, the nonconforming condition had still.not been corrected, more than 15 months af ter initial identification.

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

Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation is hereby re-quired to submit to this office, within 30 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) cor- ,

1 rective 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.

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0FFICIAL RECORD COPY DL50-219/88 0004.0.0 i 05/02/88

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