TXX-4031, Responds to NRC Re Violations Noted in IE Insp Rept 50-445/83-23.Corrective Actions:Five Loose Jam Nuts on Large Bore ASME Pipe Supports Reworked & Verified Snug Tight.Extension of Due Date Until 830901 Granted by NRC

Responds to NRC Re Violations Noted in IE Insp Rept 50-445/83-23.Corrective Actions:Five Loose Jam Nuts on Large Bore ASME Pipe Supports Reworked & Verified Snug Tight.Extension of Due Date Until 830901 Granted by NRC

ML20080S764
Person / Time
Site:	Comanche Peak
Issue date:	08/24/1983
From:	Gary R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20080S751	List: TXX-4031, Responds to NRC Re Violations Noted in IE Insp Rept 50-445/83-23.Corrective Actions:Five Loose Jam Nuts on Large Bore ASME Pipe Supports Reworked & Verified Snug Tight.Extension of Due Date Until 830901 Granted by NRC TXX-4037, Responds to NRC Re Violations Noted in IE Insp Rept 50-445/83-23.Corrective Actions:Engineering Evaluation Concluded That Plant Safety Would Not Have Been Affected. Mods Made to Insp Procedures
References
TXX-4031, NUDOCS 8310180484
Download: ML20080S764 (2)

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TEXAS UTILITIES GENERATING COMPANY m,i imm mun .n,ms.n.um 2.mio, ,

R. J. GARY August 24, 1983

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Mr. G. L. Madsen, Chief S. AUG 2 61983 ij j Reactor Project Branch 1 U. S. Nuclear Regulatory Commission

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611 Ryan Plaza Drive, Suite 1000 Docket Nos.: 50-445 Arlington, TX 76012 50-446 COMANCHE PEAK STEAM ELECTRIC STATION RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT N0. 83-23, FINDING N0. 2 FILE N0.: 10130

Dear Mr. Madsen:

We have reviewed your letter dated July 27, 1983 on the Special Fuel.

Building inspection of activities authorized by NRC Construction Permit CPPR-126 for Comanche Peak, Unit 1. The enclosed report is provided as our response to Finding No. 2 contained in Appendix A of that letter.

This letter will also serve to document our telephone conversation with T. F. Westerman on August 23, 1983, wherein we requested an extension of the due date for responding to Finding No.1 of Appendix A. An extension of two weeks, until September 1, 1983 was granted.

To aid in the understanding of our response, we have repeated the requirement and Finding No. 2 followed by our corrective action. We feel the enclosed information to be responsive to the Inspector's finding. If you have any questions, please advise.

Very truly yours, RJG:ln Encolsures cc: NRC Region IV - (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, DC 20555 r310180484 831013 PDR ADOCK 05000445 O PDR

TXX-4031 August 24, 1983

. . Page 2 APPENDIX A NOTICE OF VIOLATION Texas Utilities Generating Company Docket No. 50-445/83-23 Comanche Peak Steam Electric Station, Unit 1 License No. CPPR-126 Based on the results of an NRC inspection conducted during the period of May 23 through June 10, 1983 and in accordance with the NRC Enforcement Policy (10CFR2, Appendix C) published in the Federal Register Notice (47CFR9987) dated March 9,1982, the following violations were identified.

1, As stated in the cover letter, a response to this item will be provided no later than September 1, 1983.

2. Instructions 10CFR50, Appendix B, Criterion V states that, " activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings." The Final Safety Analysis Report, Section 17.1.5 states that, " appropriate requirements have been established in the TUGC0/

TUSI Quality Assurance Program to assure that quality-related activities for CPSES are accomplished in accordance with such documents; and that approved acceptance criteria are met."

Contrary to the above, procedures for the installation and inspection of the "NPSI" seismic sway strut jam nuts do not appear adequate to insure snugness as required by QI-QP-11,1-78, Revision 20, and as evidenced by the finding of five loose jam nuts on the following large bore ASME pipe supports:

SF-X-011-019-F43K CC-X-040-004-F43K SF-X-024-010-F43R SF-X-002-018-F43R SF-X-006-027-F53R This is a Severity Level IV Violation. (Supplement II.e) (445/8323-02).

CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED The five loose jam nuts on the large bore ASME pipe supports identified were reworked and verified by QC to be " snug tight" per QI-QAP-11.1-28, paragraph G.3.1.1.(c).

CORRECTIVE STEPS WHICH HAVE BEEN TAKRt TO AVOID FURTHER NONCOMPLIANCE Inspection checklists as implemented by procedure CP-QAP-12.1 have been revised to add specific inspection criteria relative to " snug tight" conditions of sway-strut jam nuts. These checklists are utilized by QC to verify the correctness and integrity of installation of systems prior to N-5 Certification.

THE DATE WHEN FULL COMPLIANCE WILL BE ACHIVED The checklists were revised immediately after identification of the nonconforming condition. Procedure CP-QAP-12.1 was formally approved August 3, 1983.

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