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)

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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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'4 I2 Prairie Island Unit / 7 "1-mecember 9, 1.983.

NRC Docket No. 50-se6 2 72. ~

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

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FRC mailing address is as follows:

Mr. Cyril J. Crane

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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 m. _.

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

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

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

perform a'ii'ZEQ"reviewI k uns iLfcens o's 90-day respanse to ou*M4==== issues P

o from the NBC Equipment Environmental Qualification Safety Eva1==eion Esport.

The review will be limited (SER), '

to safety-relatedpquipment potentially exposed to a harsh envf=n===t.'

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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].*

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

Eate Received bv FRC**

Infcrmatien Recuested 1.

FRC requests.ne *.CCA/EE:.3 prcfiles, f or inside and outside containment, described on f

page 4 of Reference 2.

2.

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

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) "* -

Kerite ' Company Report KPT-LVC-1 b.

April 13, 1977 (proprietary)

(A.24.8)

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

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

received.

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

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Date Received by FRC** *

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Barton Test Report Fo. R3-285A '

october 1979

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....a GE, " Insulating Materials Product Dat'a*

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.' 'W-i 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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ACME-Cleveland Development Co.

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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 r

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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

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( A.2 4.3) 1.

R. E. Shoults (Westinljhouse)

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

January 19, 1977 (A.24.3) 2-g d' Frank!!n Research Center A W alh Fm sumane j

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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

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GE Letter to A. Smith (ESP)

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November 21, 1978 (Attachment)~

( A.24. 4)

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Robert Kantner (NAMCQ)

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Letter to Paul T. Aoska (NSP)

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November 18, 1980 (A.6.5, A.6.9)

' Nuclear Radiation and Switch Applications p.

October 7, 1974 (A.6.7) q.

Honeywell Catalog 50, p. E-2 (A.6.7) l r.

B. Bondow (E-M)

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e 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)

Okenite Company Cest Procedure sent to t.

Mr. Alt.echt (NSP) on April 20, 1978 (A.24.6.

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REFERENCES

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

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.n Letter to 3. G. Ke Pinal Response to IE Rcilgtin 79-013,' Frairie W.'

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Subject:

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{T,:, *], ;.

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'. 7 Island Nuclear Generating PlantF;..

,[f Northern States Power Company, 31-Oct-40,.

2.

,. o.' Mayer 5-a

N Letter to NRC. Subjects Prairie Island Nuclear

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Generating Plant - Response to II Sulletin 79-013

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Safety Evaluation Report

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Northern States Power Compsey/ 26-Aug-4~

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.. Office of Nuclear Reactor Regulation

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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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