IR 05000206/1985013

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-206/85-13

ML20132C561
Person / Time
Site:	San Onofre
Issue date:	07/26/1985
From:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Baskin K SOUTHERN CALIFORNIA EDISON CO.
References
NUDOCS 8507300365
Download: ML20132C561 (1)

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OUL . o USS Docket No. 50-206 S. C. E. Company P. O. Box 800 Rosemead, California 91770 Attention: Kenneth P. Baskin Vice President Nuclear Gentlemen:

l Thank you for your letter date July 8, 1985, informing us of the stepsi you l have taken to correct the items which we brought to your attention in our letter dated July 7, 1985. Your corrective actions will be verified during a future inspection.

Your cooperation with us is appreciated.

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Sincerely,

/,l,l D. F. Kirsch, Acting Director Division of Reactor Safety & Projects bcct RSB/ Document Control Desk'(RIDS)

Mr. Eartin 4 Resident Inspector

J rm Chaffee Kirich Narbt[/85 7/24 7/ 7(,/85 7/QIf/85 7g/85 0507300365 0507P6

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NRC Southern Calhkenia Edison CompenY $ E ~0 ?H 3 I7.5CE P. Q. BOX 800 2244 WALNUT GROVE AVENUE REGION WM ROSEMEAD.CALeroRNIA 91770 MENNETH P. BASMIN TELEPHONE m. . *'* ~ '

July 8, 1985 U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. J. B. Martin, Regional Administrator

Dear Sir:

Subject: Docket No. 50-206 IE Inspection Report 50-206/85-13 Response to Notice of Violation San Onofre Nuclear Generating Station, Unit 1 Mr. D. F. Kirsch's letter of June 7,1985, issued IE Inspection Report 50-206/85-13 and forwarded a Notice of Violation resulting from the April 1 through 19,1985,* inspection conducted by Mr. P. P. Narbut, of activities authorized by NRC License No. DPR-13. The enclosure to this letter provides our response to the Notice of Violation contained in Appendix A to Mr. D. F. Kirsch's letter of June 7,1985.

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If you require any additional information, please so advise.

Sincerely,

. $dL, Enclosure cc: F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)

A. J. D'Angelo (USNRC Resident Inspector, Unit 1)

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ENCLOSURE Response to the Notice of Violation contained in Appendix A to Mr. D. F. Kirsch's letter of June 7,1985.

Appendix A to Mr. D. F. Kirsch's letter states:

"10 CFR 50 Appendix 8 Criterion III states in part that:

' Design changes including field changes shall be subject to design control measures commensurate with those applied to the original design.'

'The licensee's design control measures for repair and replacement activities are specified in the SCE Topical Quality Assurance Manual, Appendix IV 'ASME Code Section XI Repair and Replacement Program' which states in part ' Repairs and replacements performed at Unit I will implement the requirements of ASME Code Section XI,1977 Edition through Summer 1978 Addenda....'

"ASME Section XI, IW8 7600 states in part ' Materials shall ccmply with the requirements to which the original component or part was constructed.' IWA 7210 allows for replacement material provided,

' Modified or altered designs are reconciled with the Owner's Specification through the Stress Analysis Report, Design Report or other suitable method which demonstrates satisfactory use for the specified design and operating conditions....'

" Contrary to the above, on May 16, May 18 and May 20, 1984, respectively, ASTM-A-193 Grade B7 carbon steel body-to-bonnet studs were replaced with significantly weaker ASTM-A-193 Grade 88 stainless steel studs on RHR valves MOV 814, 833 and 813 without performing a design reconciliation to demonstrate satisfactory use for the specified conditions.

"This is a Severity Level IV Violation (Supplement II)."

Resp 0NSE Corrective Steps Which Have Been Taken_and the Results Achieved The deficiency noted regarding RHR valves MOV 814, 833 ard 813 was caused by failure to implement our existing design change process Procedure 50123-V-4.20,

" Preparation and Review of Drawings," which meets the intent of IWA-7210

" Construction Codes." Procedure 50123-V-4.20 requires the performance of an engineering analysis and reconciliation of the change with the component design specifications.

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-2-ENCLOSURE (Continued)

Resp 0NSE (Continued)

This procedure was not adhered to on Maintenance Work Orders 307501, 307503 and 306819 which replaced the original carbon steel studs, which had begun exhibiting signs of corrosion, with the stainless steel studs. This error was a result of an oversight. During the ASME Section XI Traveler planning process, it was not recognized that a material substitution was involved, in that it was not itemized on the traveler; therefore, an engineering analysis, in accordance with IAW 7210, was not performed.

When this situation was recognized, during the week of April 15, 1985, an investigation was immediately initiated to identify all components in which the ASTM-A-193 Grade 08M stainless steel studs had been installed during the Unit 1 Return-To-Service (RTS) ef fort. Eleven components, in addition to those noted in Appendix A to Mr. Kirsch's letter of June 7, 1985, were identified as not having the required design review verification prior to bolting replacement. An analysis was immediately performed to determine the bolt load stresses on all affected components. The analysis was based on SCE established critoria which was developed using " good engineering practice,"

since the ASME Boiler and Pressure Vessel Code and ANSI B31.1 do not provide critoria for bolting operational stresses. Several bolts were identified as not meeting the SCE established criteria and were immediately replaced.

Since the stress calculations were based on maximum design stresses, the ASTM-8-193 Grade B8M stainless steel bolts did not affect the operability of the components in question.

As corrective action, the subject bolts were replaced with carbon steel bolts on May 10, 1985. To improve * procedural compliance, SCE Management has had an ongoing program, since the bolting installation, to emphasize the importance of adherence to the established design change process and for verbatim compliance with procedures.

Corrective Steps Which Will be Taken to_ Avoid Further Items of Noncompliance Formal maintenance planner training will be developed to include the interaction between maintenance activities and Station design change procedures. This training will reinforce the need for adherence to the established design change process and for all plant design changes to be reviewed by Engineering.

The ASME Section XI Traveler review process will be enhanced to include drawing reviews to assure that no material substitution occurs without appropriate design authorization. Several components in which the ASTM-A-193 Grade 88M stainless steel studs had boon installed during the Unit 1 RTS effort were not subsequently replaced, since they met the SCE estabitshed stress criteria. These components have been evaluated to identify any existing design document conflicts which will then be dispositioned as appropriate.

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. I-3- l ENCLOSURE (Continued)

Corrective Steps Which Will be Taken to Avoid Further Items of Noncompliance ;

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This condition is considered an isolated occurrence; however, Quality Assurance will perform selective examinations of SONGS Units 1, 2  ;

and 3 appropriate maintenance orders to ensure material changes were properly processed. l l

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Date When Full Compliance Will be Achieved ',

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Full compliance was achieved on May 10, 1985, when the body-to-bonnet stainless steel studs for MOV-814 HOV-833 and MOV-813 were replaced with the original carbon steel bolting.

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