ML20214A118

Notice of Violation from Insp on 870314-0417

ML20214A118
Person / Time
Site:	Grand Gulf
Issue date:	04/30/1987
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20214A112	List: ML20214A111 ML20214A118 ML20214A141
References
50-416-87-10, NUDOCS 8705190274
Download: ML20214A118 (2)

Text

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O ENCLOSURE 1 NOTICE OF VIOLATION System Energy Resources, Inc.

Docket No. 50-416 Grand Gulf Nuclear Station License No. NPF-29 During -the Nuclear Regulatory Commission (NRC) ir.spection conducted on

' March 14 - April 17, 1987, violations of NRC requirements were identified.

The violations involved drawing non-compliance and failure to follow proce-

-dures.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement actions," 10 CFR Part 2, Appendix C (1986), the violations are listed below:

A.

10 CFR Part 50. Appendix B, Criterion V states, in part, that activities affecting quality shall be accomplished in accordance with documented instructions and drawings of a type appropriate to circumstances.

Contrary to the above, on February 6, 1987, the inspectors found the upper left mounting fastener for reactor control rod Hydraulic Control Unit (HCU) 36-13 missing.

It appeared to have never been installed as required by General Electric drawing 10504988, Outline, Hydraulic Control Unit.

Subsequent inspections conducted by the licensee revealed loose or missing mounting fasteners on about 35 other HCUs, a condition that could have existed since.before licensing.

The HCUs were operated in an unanalyzed condition for an indeterminate length of time until discovery of-the deficient condition on February 6, 1987, and subsequent correction.

Subsequent analyses conducted by the licensee showed that the HCUs would have performed their intended safety function while they were in the as-found, unanalyzed condition noted above.

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

B.

Technical Specification 6.8.1 requires that written procedures be established, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide (RG) 1.33, Revision 2, February 1978.

RG 1.33 recommends procedures covering the bypass of safety functions and jumper control.

Administrative Procedure 01-S-06-3, Control of Temporary Alterations, requires temporary alterations to be documented and controlled.

Contrary to the above, on March 27, 1987, the installation of the Standby Service Water basin acid storage tank and related piping was found to differ from that specified by temporary alteration 86-0034.

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

C.

The Operational Quality Assurance Manual, MPL-TOPICAL-1, Revision 5, Section 16.0 as approved by the NRC requires, in part, that measures shall be established to assure that conditions adverse to quality such as G

System Energy Resources, Inc.

2 Docket No. 50-416 Grand Gulf Nuclear Stt tion License No. NPF-29 deficiencies are promptly identified and corrected.

MPL-TOPICAL-1 implements this requirement through Administrative Procedure 01-S-03-2, Quality Deficiency Reports (QDRs), which states in Section 6.1.1 that all quality deficiencies, unless identified on another deficiency document, must be documented in accordance with this procedure.

Contrary to the above on March 12, 1987, Standby liquid Control pump relief valve C41-F029A leaked profusely through the gagging screw plug when the valve was placed in service for retesting, due to deficient reassembly (the plug was left loose).

Licensee operations and QA personnel at the scene failed to identify and document the deficiency by issuing a QDR or other document.

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

Pursuant to the provisions of 10 CFR 2.201, System Energy Resources, Inc. is hereby required to submit to this office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply includino for each violation:

(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken i.o avoid further violations, and (5) the date when full compliance will be achieved.

Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION W

Li yes, Director Division of Reactor Projects Dated at Atlanta, Georgia this 30th of Agirif 1987