ML20039A196

Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.

ML20039A196
Person / Time
Site:	Prairie Island
Issue date:	12/09/1981
From:	FRANKLIN INSTITUTE
To:	NRC
Shared Package
ML20039A197	List: ML20039A196
References
CON-NRC-03-79-118, CON-NRC-3-79-118, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.2, TASK-TM IEB-79-01B, IEB-79-1B, RFI-5257-502, RFI-C5257-502, NUDOCS 8112160346
Download: ML20039A196 (7)

Text

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REQUEST Fox AnnITICNAL INFCRMATICN - ..,..-

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EQUIPMEIC EN7IRCNMENTAL QUALIFICATION (EEQ) '

P1TIIW CF LICENSEES' RESOLUTICN CF CUISTANDING ISSDES . >

FROM NRC EQUIPME!C ENVIRCNMENTAL QUALIFICATICN S&FETY -

EVALUATION REPORTS (SER) AND TMI ACTION. PIAN -

-- INS"ar.7.rn  ;.. . . . . EQU Nor,thern States Power, Company ..

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Prairie Island Unit / 7 "1- . : . .-

mecember 9, 1.983. -

- NRC Docket No. 50-se6 2 72.

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NRC TAC Noh 4250p) $f.,6~4 / .

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FRC mailing address is as follows: -

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Mr. Cyril J. Crane - '

Franklin Research Center The Parkway at Twentieth Street -  ;

Philadelphia, PA 19103 ,

Telephone No. 215/448-1353 Telecepy No. 215/448-1296 Telecepy confirmation No. 215/448-1215

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( . 'Fra 1('Res rch Center (FRC) of Philadelphia, Pa. da providing'assie . . . - , . . . - . .

• tance to the U.S. Nuclear Regulatory Conaiss, ion (NRC) for the eqrtipment - ' * -

enfironmental,qualificatien ,(EQ) review of operating ramctors.' FEC will- ~6 p.'

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performPa'ii'ZEQ"reviewI o k uns iLfcens o's 90-day respanse to ou*M4==== issues from the NBC Equipment Environmental Qualification Safety Eva1==eion Esport .

. (SER), ' . The review will be limited to safety-relatedpquipment potentially exposed to a harsh envf=n===t.' The .'

results wid'be presented in the form of a technical evaluation zaport for .- . ,

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each Plant., ,, ,. .

This" ' request f'or additional information (RFI) is the ramalt of an evaluation of the information provided by letters dated October 31,'1980 [1].

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and August 26, 1981 [2].*

A. ..FBC RE7IN OF THE LICENSEI'S 90-DAY RESPONSE TO THE MEC 22Q SE1 _.

Infcrmatien Recuested Eate Received bv FRC**

1. FRC requests .ne *.CCA/EE:.3 prcfiles, f or '

inside and outside containment, described on page 4 of Reference 2.

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2. :n refere.ce to the *.icensee's 90-day respense [2] to tne NRC SIR [3), a legible l .

single copy of each of the following -

qualification documents is requested in crder that the FRC evaluation nay proceed

a. ,Okenite Company Latter to A. Smith (NSP)

August 31, 1978

( A.2 4. 6) "* -

b. Kerite ' Company Report KPT-LVC-1 - -

April 13, 1977 (proprietary) .

(A.24.8)

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• Numbers in brackets refer ,to citations found in the list of references.

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"This column wi?1 be ecmpleted by FPC as the requested informattion is -

"- received.

• • • Nu=bers in parentheses refer to the Licensee's SCN sheet m=shers.

b,, :Franidin Researrh Center AQuamen af The hansan ensams

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Date Received by FRC** *

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c. Barton Test Report Fo. R3-285A . '

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october 1979 . .

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(A.21.1) ,.'

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GE, " Insulating Materials Product Dat'a* '5'~'*.*'#~~~~~*. p[. p-i

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74010A Epoxy Rosin and 74010 Epoxy

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Catalyst,' March 24, 1964, and *Effect of

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Radiation on Materials * -

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e. ACME-Cleveland Development Co.

Qualification of NAMCO Controls Limit Switch - Model EA-170, Rev.1 .

I- July 24, 1978 (A.6.5, A.6.9, A.17.2) . . ,

f. ACME-Cleveland Development Co. Test Plan '

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r August 31, 1977 . .

(A.16.6, A.12.6, A.12.7, A.2.3, A.2.4, A.4. 4, A. 6.3, A. 6. 4, 6.6, 14.3, A.15.1, ' '

• A.15.2, A.16.8, A.19.5, A.19.6)

g. " Comparative Beat Resistance. of Hypalon ,

and Nec; ene," by K. Whitleck -

Elastc=ers Research Division of CuPcnt (A.24.9)

h. ES Calculatien* File Nos. 0910-204EQ-01 0910-205-Okonite-01 0910-205-Ke:ite ,

0910 205-3:W-01

1. EOS Repcre Nos. 04-0910-13, June 1981 04-0910-07, June 1981

j. J. M. Allen (Mcbil Cill' .

Intter to J. Sorenson (NSP)

February 7,,1980 ,

(A.24.2)

. k. D. R. Jones (Chevron USk, Inc.) '

CorresMm!ence with A. Smith (NSP) october 30, 1979

( A.2 4.3)

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1. R. E. Shoults (Westinljhouse)

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-r$f- ' Letter to G. A. Reed (Wis-Minn Power) -

January 19, 1977 (A.24.3) g 2-d' Frank!!n Research Center .

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-RFI-C$257-502;.., Y l95.. .

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Date Received bv FRC** *

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'm. B. C. Lauroesch (CE) .

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- Corresponden e with J. King (GE) . '

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August 7,1978 'j' ;

( A.24. 4) , -

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. n. GE Letter to A. Smith (ESP) *

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November 21, 1978 (Attachment)~ . .

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( A.24. 4) ~.

o. Robert Kantner (NAMCQ) .

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Letter to Paul T. Aoska (NSP) I .

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November 18, 1980 -

(A.6.5, A.6.9) ,

- p. ' Nuclear Radiation and Switch Applications ---

October 7, 1974

. (A.6.7)  :

q. Honeywell Catalog 50, p. E-2 -

l (A.6.7) _ .

e r. B. Bondow (E-M) ~

I4tter to J. Sorenson (NSP) .

March 25,1980 (A.7.1)

s. NSC Letter to NSP ,

Component Aging Evaluation September 29, 1980 ,

( A.7.1, A.24.1)

t. Okenite Company Cest Procedure sent to Mr. Alt.echt (NSP) on April 20, 1978 .

(A.24.6.

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REFERENCES ..

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1. D. E. G11berts, L. O. Mayer- . . . . .. .

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~4 <- .i?:gm .'".-.n: '.t ",- .3:.:-

Letter to 3. G. Ke .. -

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Subject:

Pinal Response to IE Rcilgtin 79-013,' Frairie W.' .

Island Nuclear Generating PlantF;.. *

'6.- '. 7 -..  ?  ? -# x.

Northern States Power Company, 31-Oct-40 ,. ' '# . - m

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R-%jg_'.'. "

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5-a :N

. 2. ,. o.' Mayer .

Letter to NRC. Subjects Prairie Island Nuclear

s. v.- W

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. . . l ' ,'  ;',*1*4 g. '. ,*'. :

.._. Generating Plant - Response to II Sulletin 79-013 *

.'.'rt'.S ,7

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Safety Evaluation Report - Q. - .-

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Northern States Power Compsey/ 26-Aug-4~ . g. .

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. 3.

. Office of Nuclear Reactor Regulation

-;;.gg,.

Safety Evaluation Report for Prairie Island Units 1 and 2 -

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• Environmental Qualification of safety-Related .

Electrical Equipment 2- . .

. NRC, 12-May-81 - .. . .~

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