ML20085F479

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LER UE-1-75:on 750228,three Procedural Deficiencies Re Review of Design Changes & Documentation Detected During Mods to Sys Associated W/Postulated High Energy Line Breaks Outside Containment
ML20085F479
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/31/1975
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Office of Nuclear Reactor Regulation
References
LER-UE-1-75, NUDOCS 8308220122
Download: ML20085F479 (2)


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M CODSum8FS (v^'3 Q(r l power Company

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c,enerai on.cer aim west v.cn.gan Avenue, Jackson. Mic hegan 49201 e Area Code 517 7H8 0550 V

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March 31, 1975 m

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Division of Reactor Licensing 1976 rq Re: Docket 50-255 3 3 US Nuclear Regulatory Commission' ' " '

g License DPR-20 Washington, DC 20555 Palisades Plant hs

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Gentlemen.

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ir hb}e~p'\\ O The attached " Licensee ort" is submitted to report three events which occurred during the installation of equipment associ-ated with postulated high-energy line-break modifications. These three incidents were classified as reportable because as a group they may in-dicate the lack of adequate procedures for assuring that design reviews on items having safety significance are completed.

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Some difficulty was experienced in classifying these events

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with regard to required reportability. An audit of modifications being performed at the Palisades Plant by our Quality Assurance Department re-sulted in the issuance of eight nonconformance reports. Of these eight, five were classified as "NRC reportable" by the Quality Assurance Depart-ment in accordance with 10 CFR 50 55 Further review by the Operations Department and Plant Review Committee resulted in the conclusion that none were required to be reported in accordance with the operating li-cense but that three would be reportable if the reporting definitions of Regulatory Guide 1.16, Revision 3, were in effect. 10 CFR 50.55 is not applicable after issuance of an operating license.

As three would be reportable if the reporting definition con-tained in Regulatory Guide 1.16, Revision 3, were incorporated into our operating license, the Plant Review Committee deemed it desirable to report these three nonconformances as a single unusual event requiring 30-day reporting.

Yours very truly, s

Ralph B. Sewell (Signed) 30' lp

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RBS/ce Ralph B. Sewell (3

Nuclear Licensing Administrator (j

CC: JGKeppler, USNRC 35G8 8308220122 750331 PDR ADOCK 05000255 S

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( 23 COPY SENT REGION 2

O U ENSEE EVENT REPgT

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(PLEASE PRINT ALL REGUIRED INFORMATION) e 1

8 NA I LOENSE NUMBER PE TY g8 9 ull lP l A l L l 1l l

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14 15 25 28 30 31 32 CATEGORY T

R OOCMET NUMBER EVENT DATE REPORT OATE O 1 CON'T @L]

W l 0l 5l 0l-l0 l2 l 5 l S l l0 l2 l2 l8 l7 l 5 l l0 l 3131 117 l 5 l 7 8 57 58 69 60 81 68 69 74 75 80 EVENT DESCRIPTION

@ l During modifications to systems associated with postulated high-energy line breaks outd 7 89 80

@ l side containment, three procedural deficiencies involving review of design changes l

7 89 80 h land documentation were detected. At the time of these modifications the plant was l

7 89 80 SE l shut down. These items were indicative of a program deficiency rather than a specific l 7 89 80

@ l equirment deficiency.

Acceptable interim measures have been taken pending permanent l

7 89 paug 80 C E CODE COMPONENT CODE M

A VOLATON M lx l xl laj lx l x l x l xl xl xl LqJ lxlxlxlxl tr_j 7 89 10 51 12 17 43 44 47 48 CAUSE OEbCRIPTION DG l Primarily due to inadequate design change control procedures during construction l

7 89 80 UE l activity.

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STA Us

% POWER OTHER STATUS OrSCOVERY OiSCOVERY DESCRIPTON d

l0l0l0l l Shutdown l W l QA Audit l

1 7 8 9

10 12 13 44 45 46 80 RELE SED OF

(_Z_)El ASE l NA l

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AMOUNT OF ACTMTY LOCATON OF AELEASE E

W 7 8 9

10 11 44 45 80 PERSONNEL EXPOSURES NUMDER TYPE DESCRIPTON E l0l0l0l

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7 09 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTON E l 0l0 l0 l l NA l

7 89 11 12 80 OFFSITE CONSEQUENCES DE l None - Inadequate procedures did not result in defective equipment.

l 7 89 80 LOSS OR OAMAGE TO FACILITY T Y PE DESCRIPTON DE lzJ l NA l

' 89 10 80 PUBLICITY l Will be released to Michigan news media on submittal to NRC.

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7 89 80 eN AOUlTIONAL FACTORS f

\\, j l (Event Description)(Contd) corrective action completion (UE-1-75).

l 7 89 80 8I I

7 89 80 Ralph B. Sewell (517) 788-1997 NAME:

PHONE:

GPO 889 667