ML18353B251

LER 1975-003-00 for Palisades Nuclear Plant, During Modifications to Systems Associated with Postulated High-Energy Line Breaks Outside Containment, Three Procedural Deficiencies Involving Review of Design Changes and Documentation Were Det

ML18353B251
Person / Time
Site:	Palisades
Issue date:	03/31/1975
From:	Sewell R Consumers Power Co
To:	Office of Nuclear Reactor Regulation
References
LER 1975-003-00
Download: ML18353B251 (2)

Text

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• Power company The attached "Licensee Event Report" 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 *

• Some difficulty was experienced in classifying these events with regard to required reportability. An audit bf 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 nonconfonnances as a single unusual event requiring 30-day reporting.

Yours very truly, RBS/ce Ralph B. Sewell

• CC: JGKeppler, USNRC Nuclear Licensing Administrator

J. :-' .~./ -

• LICENSEE EVENT REPORT

• CONTROL BLOCK: I I I I I I I [PLEASE PRINT ALL REQUIRED INFORMATION) 1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

-~ I MI I I p I A I L I i I ...,.I_...._.....I -_IL......-.L.l---J..-1--'l__._I___.__I---L.1-...J-__.I I 4 I 1 I1 11 I 0 I I o I 31

~ 9 14 15 25 26 30 31 32 REPORT REPORT w

CATEGORY TYPE SOURCE DOCKl;T NUMBER EVENT DATE REPORT DATE

@I!1.coN'T l M) r I l1J I o I 5 I ol-1 o I2 I 5 I 5 I lo 12 I2 I B I 7 I 5 I lo I 3 I 3 I i I1 I 5 I 7 8 57 58 59 BO B1 BB B9 74 75 80 EVENT DESCRIPTION lol2I l.Quring modifications to systems associated with postulated high-energy line breaks outj 7 8 9 80 IPlsl lside containment, three procedural deficiencies involving review of design changes I 7 8 9 80 lol41 land documentation were detected. At the time of these modifications the plant was I 7 8 9 80 lol51 I shut down. These items were indicative of a program deficiency rather than a specific I 7 8 9 80 lolBI I equipment deficiency. Acceptable interim measures have been taken pending permanent J 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONEN/ CODE SUPPLIER MANUFACTURER VIOLATION

@El lxl xi illJ 12 I x I x I x I x I x I .xi17 l_gJ lxlxlxlxl ILJ 7 8 9 10 11 43 44 47 48 CAUSE DESCRIPTION

~ !Primarily due to inadequate design change control procedures during construction I 7 8 9 80 lolsl I activity. I

~ :!::--------------------------------------------'::

• E FACILITY STATUS  % POWER OTHER STATUS METHOD OF DISCOVERY DISCOVERY DESCRIPTION ETIJ L_gJ I0 I 0I 0I l..____Sh_u_td_o_wn_ ___.I UJ I QA Audit 7 8 9 10 12 13 44 45 4B 80 FORM OF ACTIVITY CONTENT 7

rn 8 RELEASED UJ 9

w OF RELEASE 10 1 NA AMOUNT OF ACTIVITY 1~1------------'44 45 LDCATiDN OF RELEASE 80 PERSONNEL EXPOSURES ITEi I ol NUMBER ol ol WTYPE DESCRIPTION

.__N_A_________________________________________________;.___J 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION 7

EEJ8 g*Iola lo 11I 12 .~N=A;;.__-------------------------------------------------J 80 OFFSITE CONSEQUENCES

~ I None - Inadequate procedures did not result in defective equipment.

7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION l2EJ. ~

7 8 9 1= NA 0 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 8 _ _ , 1 0 PUBLICITY

~ I Will be released to Michigan news media on submittal to NRC.

7 8 9 80 ADDITIONAL FACTORS

• I (Event Description)(Contd) corrective action completion (UE-1-75).

7 8 9 80 NAME:_Ra_l...;;;p;....h_B_.___ s_e_we_ll _ _ _ _ _ _ _ _ _ _ _ _ _ PHONE: (517) 788-1997 GPO 881

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