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)

Text

- ,

_ _

'

l 'l >

ci[ _ '

mm M.,

y

. > - ~, , .

,

a.~.

.N -

4

-

,

' 10 > 1 ~

Appendix

-

.,

s Notice'of' Violation

<

.

y ,

.. < fTolen Edison' Company! Docket No."50-346-I T [Ana:resultfofLthe:inspectionconducted'on' August.6through' November 4,s1985,

-

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

= cActions,;(10lCFR Part,2,7 Appendix'C), the following violations wer ! identified: -

~ - "

. , . . .- .. . . ,

~

fl.; (10 CFRl50,fAppendix:B,7CriterioniV, as implemented by the Toledo Edison

'

KCompany Nuclear. Quality: Assurance Manual:(NQAM) requires activities

~

'! -= 1 laffecting1guality be: prescribed by documented-instructions and those

~

-

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

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

-

x lasi:providing: specific 11mplementing instructions for performing activities e W "affecting qualityc : Nuclear. Facility Engineering' Procedure'(NFEP) 050, (Processing SurveillanceLReports',lrequires the' identification. portion of

'

g[' -

<

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

fadversefto quality is. identified by engineering personne .-

n '

Contrarytoltheabove,ithellicenseedid'nottutilize'ProcedureNFEP-050

~

%. .

<

J

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

.

'

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

< .

-

L(a)TErroneous,informationion pitch and stem 'diameterL of Limitorqu ,J c Tvalves. ;Thisfinformationv is critical in determining the' correct-torque fswitch; settings'and important to)the operability of the valve. The

~

' a ' -

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

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

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

+

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

, ?to squality, report was not'made until November 4, 198 This ~~is :a- Severity : Level' IV violation:(Supplement I).

.

-2.s >: Technical ~ Specification '3.7.2.1 Limiting _ Condition for Operation does not

'

"Gy '

'

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

' ~ '

"

coolant'i.'s =less' than 110 degrees Fahrenheit. If the conditions' stated

-

-

tabove are' exceeded,ithe pressure must be reduced to less than 237 psig 1 1~

'

'

'

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

,

-

be conducted prior to;repressurizing the steam generator above 237 psi '

y _  ! Contrary to the above,c on September 6,.1985, No.1 steam generator was 1 ipressu_rized to approximately 1050 psig, depressurized to below 237 psig

^

and re' pres'surized to'approximately'1050 psig with secondary coolant at

- ,

,

,

.

PDR

~8512240106'851217-ADOCK-05000346 7<

G PDR m

.

,

a& _ . &

4 '4 4 b, e g u

7-c~s- . 4 _.- J m .. _

Notice of. Viola' tion- '

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

~

i pressurization of the steam generator, an engineering analysis of the 7 ,

steam generator was not performe This'is af Severity Level IV violation (Supplement 1).

-

~

1 Technical -Specification 6.8.1 requires that written _ procedures be .

,

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

-

.

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

~

heat' balance: and performing a Technical Specification requirement was

'

calibrated without.the-use_of'a procedur : 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 o explanation in reply, including for each item of noncompliance: (1) corrective

~

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

.

Division of Reactor Projects r

'

t-m