ML20212H129

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Partially Withheld Ltr Discussing Recipient Allegation Re Pipe Support Hangers &/Or Components within Supports at Plant W/O Heat Numbers Marked at Time of Exam.W/O Insp Repts Encl
ML20212H129
Person / Time
Site: Wolf Creek, 05000000
Issue date: 04/01/1985
From: Nash T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
AFFILIATION NOT ASSIGNED
Shared Package
ML20212G491 List:
References
FOIA-85-594 NUDOCS 8608130664
Download: ML20212H129 (8)
v • d • e


Text

-  ;. r eff'A UNITED cTATES NUCLEAR REGULATORY COMMISSION ,

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5' REGION IV

< 11 RY OR V U 10 e n [. ARUNGTON. TEXAS 78011 In latel . , ,,s your concerns with certain aspects of work being done at%1f Creek Generating Station were shown through allegations to the Kansas Gas and Electric Company (KG&E). These allegations involved not only the Wolf Creek site, but also those ofil

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As a result, KG&E informed NRC

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Region IV of this information'on! ..

The allegation, as understood by Region IV, was that pipe support hangers and/or components within supports at Wolf Creek did not, in many instances, have " heat numbers" marked on them at the time of your examination and that these numbers were later added or post-applied. 01:RIV interviewed you onl. . ., .... i and you reiterated your concern about finding " numerous" hangers without heat numbers and also stated that you believed the missing numbers were added later but had no specific knowledge that this was true and could provide no specific-information about the hangers involved.

The NRC inspector has reviewed the KG&E Quality First team investigation file

pertaining to the allegations as originally received. Two of the four documented 9 " concerns" were found to be similar in context to Region IV's understanding of the allegation. The Quality First file indicates that there was a followup on your concerns using your hanger walkdown logbook wherein you recorded specific observations that led to your conclusions and concerns.

The report on eagh logbook reflects the chs.etvations and a date of the observation which range from'  ! The KG&E followup was initiated not earlier than and was concluded;inl~~  ! In every instance, the followup revealed that your specific observations were no longer valid in many instances with material changes or engineering actions which clearly took place after the original observations by you and apparently prior to the Quality First followup. The Quality First team concl.usion was that the allegation was not substantiated because they did not confirm [ . . observations. The NRC inspector, however, would conclude that your concerns were substantiated but taken in the context of today's time.frama. has little. technical merit. Following the initial walkdown performed byl 4 craft personnel that you were involved in, there have been aPleast two more major walkdowns. One was by KG&E QC and.the other by Bechtel personnel for the purposes of. satisfying IEB 79-14. Each found problems with various aspects of traceability of components that were resolved ,on 8608130664 860723 PDR FOIA STEPHEN 85-S94 PDR i

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a case basis. A similar allegation case (4-84-A-98) was inspected as documented in Inspection Report 50-482/84-58 with the same conclusion. It is thus apparent that there were many instances of failure to follow detailed QA/QC procedures during the fabrication and installation process. After identification of the problem it is also apparent that KG&E instituted an effective corrective action program as indicated by paragraph 8A of Inspection Report 50-482/84-23. The above identified case is considered closed.

Your responsibility and genuine interest in these items of inspection are truly appreciated by the NRC and we appreciate your concerns in the safety of the activities at the Wolf Creek Generating Station.

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Sincerely, T. A. Nash Investigations / Allegations Coordinator, RIV

Enclosures:

Appendix - NRC Inspection Reports 50-482/84-23 and 50-482/84-58

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Rbaso:n for Reportability:

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A. Tnis desicn or construction deficiency, were it to have remained uncorrect~3, could have affected adversely the safety of op2 rations of the nuclear power plant at any ti;ne throughout the eYp?cted lifetime of the plant. '

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_OR C. Tnis deficiency represents a sicnificant d,eficiency in final desien as ap? rove 3 and released for constructica such tnat the design does not confotu to the criteria bases stated in the safety analysis report or construction parmit.

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