IR 05000806/2011004

Notice of Violation from Insp on 850806-1104

ML20138N676
Person / Time
Site:	Davis Besse, 05000806
Issue date:	12/17/1985
From:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20138N660	List: IR 05000346/1985025 IR 05000806/2011004 ML20138N657
References
50-346-85-25, NUDOCS 8512240106
Download: ML20138N676 (2)

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Appendix

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Notice'of' Violation s

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< fTolen Edison' Company!

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Docket No."50-346-

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[Ana:resultfofLthe:inspectionconducted'on' August.6through' November 4,s1985,

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Land.in'accordance'with the GeneraliPolicy'and-Procedures for NRC Enforcement-H

= cActions,;(10lCFR Part,2,7 Appendix'C), the following violations were.

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! identified:

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fl.; (10 CFRl50,fAppendix:B,7CriterioniV, as implemented by the Toledo Edison KCompany Nuclear. Quality: Assurance Manual:(NQAM) requires activities

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1 laffecting1guality be: prescribed by documented-instructions and those

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g' 's Lactiv'itiestbe~accomplishedLinlaccordance-with.these instructions. 'The:

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e iToledo Edison NQAM identifies-the_ Nuclear Facility Engineering ~ Procedures

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lasi:providing: specific 11mplementing instructions for performing activities

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"affecting qualityc : Nuclear. Facility Engineering' Procedure'(NFEP) 050, g[' -

(Processing SurveillanceLReports',lrequires the' identification. portion of

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1a7 surveillance report be completed within.one or two. days when a condition l

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fadversefto quality is. identified by engineering personnel.

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Contrarytoltheabove,ithellicenseedid'nottutilize'ProcedureNFEP-050

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.in;a timely man'nerJinzidentifying-two conditions adverse to: quality 'as

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f < required by Section'A of that procedure. 'Those two conditions were

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L(a)TErroneous,informationion pitch and stem 'diameterL of Limitorque.

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Tvalves. ;Thisfinformation is critical in determining the' correct-torque v

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fswitch; settings'and important to)the operability of the valve.

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11cens'ee'wasLaware of theierroneous information for;over a' year but.did

not. initiatefa; condition adverselto ~ quality report until. the Fall-of i

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1985 G (b) The' erroneous interpretation that'the-water-cooled subsystem.

'of thefcontrol' room emergencylventilation.1 system-(CREVS):is'not required M

1for operabilityiof the. CREVS. ' ;0n-October 11,-1985, the licensee was informed'that the both1the water-cooled and the ' air-cooled subsystems'

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l wereirequired for operability of the' CREVS.1However, a condition adverse =

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?to quality, report was not'made until November 4, 1985.

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1This ~~is :a-Severity : Level' IV violation:(Supplement I).

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>: Technical ~ Specification '3.7.2.1 Limiting _ Condition for Operation does not

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" allow' steam generator pressurelin' excess of 237 psig when the secondary

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coolant'i.'s =less' than 110 degrees Fahrenheit.

If the conditions' stated

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tabove are' exceeded,ithe pressure must be reduced to less than 237 psig

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within 30-minutes:and an engineering' analysis of the steam generator must 1 ~

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be conducted prior to;repressurizing the steam generator above 237 psig.

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! Contrary to the above,c on September 6,.1985, No.1 steam generator was

ipressu_rized to approximately 1050 psig, depressurized to below 237 psig and re' pres'surized to'approximately'1050 psig with secondary coolant at

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Notice of. Viola' tion-

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less than'110 degrees Fahrenheit.. Prior to the second 1050 psig

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i pressurization of the steam generator, an engineering analysis of the

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steam generator was not performed.

This'is af Severity Level IV violation (Supplement 1).

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Technical -Specification 6.8.1 requires that written _ procedures be

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established,< implemented-and maintained covering the activities -specified

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in Appendix A of Regulatory Guide 1.33, November, 1972.- Section H of:

~ Regulatory Guidejl.33,1 Procedures and Calibrations, states in'part:

" Equipment to be calibrated by appropriate procedures are readout

= instruments, interlock. permissive and prohibit circuits,- alarm devices, sensors,_ signal ~ conditioners, controls.and protective _ circuits."

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IContra'r$tolthe above', an instrunent. channel inputting to the secondary -

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heat' balance: and performing a Technical Specification requirement was calibrated without.the-use_of'a procedure.

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This.is a. Severity Level _V violation'(Supplement I).

n Pursuant to the~ provisions of 10 CFR.2.201, you are required-to submit to this office within' thirty _ days of the' date of this Notice a written statement or.

explanation in reply, including for each item of noncompliance: (1) corrective

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action,taken and-the results achieved; (2) corrective action to be taken to avoid.further' noncompliance; and (3) the date when full. compliance will be achieved.. Consideration may be given.to extending your response -time for good

'cause shown..

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DEc 171935 g.g y 4 Dated C. E. Norelius, Director

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Division of Reactor Projects r

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