ML20126E530

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Identifies Required Info Re SEP Topic Environ Qualification of Safety-Related Equipment. NRC Safety Assessment Will Consider Ability to Respond to All Dbes,Importance of Safety Function & All Available Testing & Qualification Data
ML20126E530
Person / Time
Site: Palisades, Big Rock Point  File:Consumers Energy icon.png
Issue date: 12/23/1977
From: Stello V
Office of Nuclear Reactor Regulation
To: Bixel D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8102040164
Download: ML20126E530 (5)


Text

.

Becket,Nos. 0-155

'f 50- 5 DEC 9

  • 077 Consup rs Power Conpany ATTH: Mr. David A. Bixel Nuclear Licensino Administrator 212 West Michigan Avenuo Jackson, Nichigan 49201 Gentlemn:

PE: BIG R0rt P0ll'T PALISADES PLAfiT Our letter of December 1,1977, discussed your participation in tna Systenatic Evaluation Program (SEP) for operatino reactors and provide?

a report describino the procran. The program includes the topic

  • Environ ~ ental Oualific c;on of Safety Related Eoui ment" as one of the topics of safety significance. The procram further provides tFat topics ennsidered to be of special safety significance would continue to be evaluated on a case-by-case basis in advance of completing the overall program. The staff has determined that it is appropriate to cowlete its review of this subject as the first topic of the SEP.

The enclosed " Staff Report on the Environmental Qualification of Safety-Pelated Electrical Equionent" (NLPEG 413) supports the staff position that no imdiate action for your facilities is required, but that it is appropriate to initiate the review of this topic. This document was prepared as part of the KRC staff's response of Dece $er 15,1977 to a Union of Concerned Scientists petition dated November 4,1977. The report also provides the staff review procedure, a discussion of the historical evolution of regulatory criteria, current generic staff l

effort, a sumary of relevant operating experience and other infornation 1

i relevant to this topic.

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~~;

it Therefore, pursuant to 50.54f f), please deliver to the Office of Nuclear A Reactor Regulation, Nuclear Rooulatory Corcission within 60 days from the (Wate of this letter three signed originals and 40 copies of the followino

- infomation:

T(03b%ilok

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Consuorrs Power Company p

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Identification of safety-related electrical equipment located both j

inside and outside containaent which are required to perfom a safety f unction under the environmental condition resulting from each Design 7-M Basis Event (DBE) for your facilities. The D!:0 is defined as any singic event which could potentially result in greater than routine ralease of radioactivity from the site. Briefly describe the safety function provided by each iten of the eculpment identified. Describe the location of the ecuiprent.

Identify any non-safety syster, equirnnt or components, which, if subjected to the environmental conditions associated with a DP,E, could affect the safety function of any safety-related system.

Identify non-safety systens which could perfom the function of a safety systen by ar.cliorating the consequences of a DDE and specify electrical ecuipment required tc assure function of such non-safety systerc.

2.

OIfinition of the limiting service environ.a.entel conditions for operattn] of the equipment and components identified above. The environ'aerital paraneters should include pressure, temperature, huridi ty, submergence, stea1, radiatioil, chemicals, vibration or any conoination of the abeve (seismic conditions are not to be includ+d but will be considered elsewhere in the SEP). These environe. ental conditions should be presented as a function of tine an'i tne DBE producing the conditions should be identified. The tiac period durinn wtiich each itar of equipment would be requiree to operate in a DBE environoent should also be identified.

'1 Deteraination of the current status of environmntal qcclification for safety-related electrical equipeent and identification of the supporting documentation. Any evidence by tests end analyses of environcental qualification for any environnental condition should '

i be considered and provided.

Any infomation previously provided to the HP.C that is still approoriate may be provided by reference.

We will be contacting you shortly to arrance a rieetino to provide you with additional background infomation.

In addition, a visit of your fac111 tics will be scheduled in the near future to obtain inforration on

.- safety-rtlated electrical equipment through direct onsite observation of j

t these systems.

s Consuncrs Power Company,

Our safety assessment of this review topic will consider:

(1)tbility of the f acility to adequately respond to all design basis events, f g(2) inportance of the safety function and alternate ways of perfominc

$the safety function such as the possible use of non-safety system, (3) all fhveilabic testing and qualification data, (4) any existing protection nf

'I he eonipment f-o:. the environ"ient, or (5) any other besis for acceptability t

that you might identify.

Sincerely.

-Minni fl@CS N Tietor 5tch

[ictor Stello, Jr., Director Division of Operatir.g Reactors Office of Nuclear Reactor Regulation (6f'A N ~O "'"'

Enclowre:

4 b r 6-n d W /' d Steff Report cc w/ enclosure:

Sec next recc DISTRIBUTION Docket (2)

NRC PDR (2)

Local POR (2)

SEP Reading ORB #1 Reading ORB #2 Reading Vstello KRGoller DEisenhut TJCarter ASchwencer GZech SSheppard DKDavis EAReeves RMDiggs 0 ELD I&E(3) j8@c[athy g,cg_ g g< cjv g, g>Now e

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- ACRS (16) g y 4 N %q JGuibert RCudlin EC_apg DOR:hR D DOR:AD/0T DOR:DIRO

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DLZiemann:ah y,[M'S blXdEChKRGoller,,__ DEisenhut VSklo 12/;N77 12/23/M8 12/5/N 1M3B

.R/ m 12/AM NRC PORM 518 (9 76) NBCM 0240 8 us s. oovensiussFr puiavine ' irica sW = M o

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Dairyland Power Cooperative q Our safety assessment of this review topic will consider:

b) ability

,p of the facility to adequately respond to all design basis events,

.j (2) importance of the safety function and alternate ways of perfoming the safety function such as the possible use of non-safety system, (3) all

'I available testing and qualification data, (4) any existing protection of the equipment from the environment, or (5) any other basis for acceptaDility that you might identify.

Sincerely,

(

I l

Victor Stello, Jr., Director l

Division of Operating Reactors i

Office of Nuclear Reactor Regulation i

l

Enclosure:

i Staff Report l

cc w/ enclosure:

l See next page I

l l

1 l

l, NOTE:

Concurrence in this letter to DPC shows concurrence in identical letters to licensees of the following plants: 'Dresden 1/2, c?

'0yster Creek, Millstone 1,' San Onofre,iiaddam Neck Big Rock, i

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  • Palisades.: Ginna and' Yankee-Rowe l

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12//77 12/ /77 12/.1(/77 12/31/77 jy(yV' lYd/d i NRC FORM 318 (9 76) NRCM 0240 W u. e. soygmHMgNT PRINTING OFNC Bs 1976*0,44&4

Consumers Power Company December 23, 1977 ~~ CC W/ enclosure * ,, M. I. Miller, Esquire T Isham, Lincoln & Beale -t Suite 4200

[ One First National Plaza Chicagc, Illinois 60670 J. L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 492C1 Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Mr. Charles F. Bayless Of Counsel Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 George C. Freeman, Jr., Esquire Hunton, Willians, Gay and Gibson 700 East Main Street Richmond, Virginia 23212 Peter W. Steketee, Esquire 505 Peoples Building

. Grand Rapids, Michigan 49503 3! Charlevoix Public Librarv ~ if_107ClintonStreet - Charlevoix, Michigan 49720 D}}