ML17303B182

LER 86-058-01:on 861111 & 18,overtemp Delta T Reactor Trip Occurred on Increasing Reactor Coolant Temp Rate.Caused by Spike on Potentiometer.Valve Realigned & Unit Returned to Previous status.W/861230 Ltr

ML17303B182
Person / Time
Site:	Catawba
Issue date:	12/30/1986
From:	Ouellette R, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-86-058, LER-86-58, NUDOCS 8701050285
Download: ML17303B182 (4)

Text

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~o UNffKQ~sTATNS N VQLKAR:REGULARORY COMMlSSION:

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~,y ~'g .'g REQNhflV Ie 4r g 1450 MARIA LANb; SUIT% II'IO I

MfAI.HVTCRKfK. CALIFORNIA945'

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Steel DEQ i:9 F986:.

Oacket Nos.:. 50-528

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'50-529

$ 0-630; I~

II Arfbona'Nuclear. Pow'er:tI'r o feet.

P. 0.;ao~ Se034" '::

Phoenfu(, Arizonai 85072"RO34 r

Attention:-:. -I " Hre '.K."!E;.:.Van .Brunt 4r;, .

"-"-':" ".Gxecotfvei Vice.&residerrt r . =:f I

f h Gentlemen: 'C I r,

Subject:

'NRC >Inspection'bf Phlo-'erde"Units 1;:2 and 3l' This refers. to the 'fnspecth)n"conducted 4y':Messrs;'R..Zfiaierean'.

SostedI: 6:. Fiere3li;-J.'Se)l';i X. covey. ehd'C.Ser:ensign ef thee effice on October 3.3,: 1986:, through Novemberi 25, 1986 of actfviti'es autho~iied'.

by".HRC<fcenser8os': NPF 41r"NPF-51 and 'Constructfan Rermfti':Number'.r~":..

CPPR-l43; -and- to -'the dfs4ussfon 'of <our findings Iheld 'wf th yoqrsel A.:and::

other~ers'of your Istaff: at the rconelusfoni of the Ifnspectfon..

Areas.examined during Ithfs 4nspectfon are'described tn the enclosed:

fnspectienI'popo&; -~Mfthfn Ithese; areas,:the inspectfon consfsted-'of:

selectfve examfnatfons of p'rocedut es and.. representatfve reconds, 'fnter views with personnel, and observations by the'nspecrs..

Based on;,tea results of this f.nspec;tion,: ft appears that one fof your:

actfvftfes was, not conducted fn full compliance with NRC requirements, as .

set'iforth in'the )Notice. of Violatfon, enclosed her ewith as ~appendix'R

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Your'response to".this Hot:fee.is to he.submftted dn accordanca.wfthi the;.

provfsfons of 10:CFR 2..201 as:stated fn Appendix A, Nptice of Vfolatfon.

The enclosed violation fis associated with: the ommission in a V '

Licensee Event Report ef the: failuree mec m ch anism of a containment valve, which was report;ed.to have~ not ful.'1 y c 1 os d p n receipt of an <

gna: . Our review into %e circumstances associated w a> '"pe, . valve failure determine'4 that the. cause was .iden craft:. perso nnel. as a pluggedlmuffl'er', n th air. di ha 'our Although the muffl'er was cleaned and. ret t t'l d

concerned Chat your corrective actions did notiinclude. consider t,h t . i li ti:.for s.. or sim ilar air operated val.ves at the site.

Me also noted that an apparent weakness exists in the im lemen your root causeianalysis program,;in thati0 erations t

the procedural responsibi 1;'i y far .in tiat ng an ana} sis fo failures they deem: significant'o n; owever, the th presenh work co t d oes not routinely. provide safety-related. work o department. for assessment.:

engineer was not, aware of the and therefore icould t evaluation .for potentially.

In your;response to the enclosed A

y. gene d

'i failure of the'bove cont generi c implhcati ons.

violation, we re vest

'alve our additional concerns regarding .l) how ou d su that g y genenic implications, is or con itions adverse to quality;. and 2) how correct the apparent weakness in th 1 analysis program associated with how significant fai lure identified for fur her formal ana anal ysis andd generic resolution.

In accordance. with 10 2.790(a):,

i'1l b 1 d CFR in e'ublic th'RC a co of'o Document Room.:

The response directed by this letter and the accom an i.n N subject to the clearance procedure. of the Office of as reouired by the Paperwork Reduction Act: f 1980, Should you have any questions. concerningg this ins p e io , we i 1 be Si e rely, John B. Hartin Regional Administrator

Enclosures:

A- Appendix. A - Notice of Violation S. Inspection In Report Nos~ 50-528/86"33 50"529/86-"32 .and 50-530/86-26

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