ML20151F253

Notice of Violation from Insp on 880608-0706.Violation Noted:Neither Deficiency Rept Nor Nonconformance Rept Issued to Identify & Correct Discrepancies Re Setpoints of Protective Relays & Installation of Incorrect Gaskets

ML20151F253
Person / Time
Site:	Comanche Peak
Issue date:	07/22/1988
From:	Warnick R NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20151F243	List: ML20151F241 ML20151F253 ML20151F267
References
50-445-88-44, 50-446-88-40, NUDOCS 8807270004
Download: ML20151F253 (2)

Text

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APPENDIX A NOTICE OF VIOLATION TU Electric Dockets: 50-445/88-44 50-446/88-40 Comancho Peak Steam Electric Station Permits: CPPR-126 Units 1 and 2, Glen Rose, Texas CPPR-127 During an NRC inspection conducted on June 8 through July 6, 1988, one violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violation is listed below:

A. 10 CFR Part 50, Appendix B, Criterica XVI, requires, in part, that measures be established to assure that conditions adverse to quality are promptly identified and corrected.

The Operations Administrative Control and Quality Assurance Plan, Section 3.9, paragraph 2.0, specifies that conditions adverse to quality be proraptly identified and dispositioned.

Paragra,7h 3.0 specifies that measures governing the control of nonconformances and deficiencies be contained in the appropriate procedures manuals as implementing procedures established by the Nuclear Engineering and Operations (NEO)

Policies and Procedures Manuals.

In the CPSES Station Administration Manual (the appropriate procedures manual), Procedure STA-404 contains the instructions for the use of deficiency reports (DRs) and Procedure STA-405 contains the instructions or use of nonconformance reports (NCRs).

Contrary to the above:

1. Neither a DR nor a NCR was issued te promptly identify and correct discrepancies (a condition adverse to quality) between issued field drawings (associated with setpoints of various protective relays) and actual equipment configuration.

2. Neither a DR nor a NCR-was used to promptly identify and correct the root cause of installing an incorrect gasket (a condition adverse to quality) during an overhaul of the steam-driven auxiliary feedwater (AFW) pump.

8807270004 880722 PDR Q ADOCK 05000445 PDC

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3. Neither a DR nor a NCR was used to promptly identify and )

correct the root cause of a missing tag that was required '

to be attached to the Temporary Modification 85-0573 (a condition adverse to quality). l Thi.s is a Severity Level IV violation (Supplement II)

(445/8844-V-01). -

Pursuant to the provisions of 10 CFR 2.201, TU Electric is hereby required to submit a written statement or explanation to the U. S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC, 20555, with a copy to the Assistant Director for ,

Inspection Programs, Comanche Peak Project Division, Office of j Special Projects, within 30 days of the date of the letter i transmitting this Notice. . This reply should be clearly marked cui a l "Reply to a Notice of Violation" and should include for each  !

violation: (1) the reason for the violation if admitted, (2) the I ccrrective steps that have been taken and the results achieved, I (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the licenrse should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION l

0 b. / ,

Dated at Comanche eak Site O ' U AbhlC K this ;;;L day of (

)1988 1

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