ML17319B269

Responds to NRC Re Environ Qualification of safety-related Equipment.Table Re Status of Compliance W/ NUREG-0737 Items Encl

ML17319B269
Person / Time
Site:	Cook
Issue date:	04/07/1982
From:	Hering R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Varga S Office of Nuclear Reactor Regulation
References
RTR-NUREG-0588, RTR-NUREG-0737, RTR-NUREG-588, RTR-NUREG-737, TASK-***, TASK-TM AEP:NRC:0578D, AEP:NRC:578D, NUDOCS 8204130140
Download: ML17319B269 (10)

Text

'REGULATORY ORNATION DISTRISUTION SY

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'AOCE'SSION NBR;8204130140 OOG ~ DATE: 82/04/07 NOTARI'ZED; NO DOCKET FACIL 50~315 Donal.d O+ Cook,Nuclear Power PlantE Uni,t 1E.Indiana

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.'50 316 Donald 6, Cook.Nuclear Power P lant'nit 2E Indiana 8

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"'A'UTH~NAME'UTHOR 'AFFILIATION HERINGiR ~ F ~

Indiana:8 Michigan Electric Co.

>RSC IP o tlAQE REO IP IENT, AF F ILI ATION VAAGArSDAR.

,Oper5ting Reactors Branch 1

'SUBJEOT:

Resppnls ty NRC 820219 litr'ne envir on aua1if ication of safety~nelated equipment',Table re status of compliance w/

NUREG 0737 iitems encl.

DISTRISUTION OODEI SOASS

>OQPIES >REGEIVED'LTR. /

ENCL I SIZE:

TITLE: Equipment!Qual-i ficat'ion (OR 8 iPRE OL)

NOTES!

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INDIANA 5 MICHIGAN ELECTRIC COMPANY P. O.

BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 April 7, 1982 AEP:NRC:0578D Donald C. Cook Nuclear Plant Unit Nos.

1"and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT Mr. Steven A. Varga, Chief Operating Reactors Branch

//1 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C.

20555

RECEDED, APR12398Z~

to I 0 INSlt ItunI0IIT~

I4I03IItNIIIIBIaIg

Dear Mr. Varga:

This letter responds to your letter dated February 19, 1982 and also includes several additional references requested in your January 15, 1982 letter as a follow-up to our submittal number AEP:NRC:0578C dated February 26, 1982.

The complete attachment, together with a copy of this letter is being sent to your Consultant, the Franklin Research Center as per your request.

1.

Res onse to Mr. S. Var a's letter of Februar 19 1982 on TMI

~enl ment In our conversation of March 8, 1982 with Mr. R. Krapf of the Franklin Research

Center, we were informed that the information and format of our letter AEP:NRC:0356D dated February 3, 1981 were acceptable and that the response to your letter should only address items installed after January 1,

1981.

Furthermore, we were told that the scope of the submittal as defined in AEP:NRC:0356D was adequate.

The table attached to this letter is the information requested by Items l.a, b and c.

The responses to items 1.d, 2.

and 3. are given below.

Item 1.d: The appropriate qualification criteria for the D.C. Cook Plant are the DOR Guidelines.

The May 27, 1980 Memorandum and Order (CLI-80-21) only requires that by June 30, 1982 equipment be qualified by DOR or NUREG 0588.

Since NUREG 0588 states that "Allreactors with Operating Licenses as of May 23, 1980 will be evaluated by the staff against the DOR guidelines...,"

the D. C. Cook Plant will be evaluated using the DOR guidelines.

Item 2.: The appropriate primary device System Component Evaluation Worksheets are shown on the attached table for the equipment which has

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Mr. Steven A. Varga AEP:

~:0578D approved qualification test reports.

The qualification documents which have not been already submitted, will be included in our forthcoming letter No. AEP:NRC:0578B to be submitted prior to May 15, 1982.

The items marked "later" will have the System Component Evaluation Worksheets provided following review and approval of the test reports.

This plan was chosen since providing a worksheet with only the specification portion completed would not be meaningful.

Item 3.:

Requests for extensions were submitted via our letter No.

AEP:NRC:0652 dated December 23, 1981 on items II.B.3.2, II.F.l.l, II.F.1.3, II.F.1.6 and II.F.2.3.

For items II.K.3.1 and II.K.3.5, we are part of the Westinghouse Owners Group investigation.

2.

Additional references re uested in Mr. Var a's Janua 15 1982 letter The following items were not included in our submittal No. AEP:NRC:

0578C, dated February 26, 1982.

They are attached to this letter.

Attachment Item Title "Flood-up Tube Qual. Packet" "Instr. Cable Termination Packet" "Required Time Qual. Analysis" "t" (Unit 1)

"E.Q. for Outside Containment Cable" "v" (Unit 1)

"Electrical Penetration and "u" (Unit 2)

Analysis" "Containment Spray Motor Radiation Qualification" p

q I

1 GIld s

This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, R. F. Hering Vice President

/md cc: (attached)

Jl P~

I

A Mr. Steven A. Varga AEP:NRC'D CC:

John E. Dolan Columbus R.

W. Jurgensen W.

G. Smith, Jr.

Bridgman R.

C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant Bridgman Mr. Cyril J.

Crane Franklin Research Center R.

S. Hunter

ENCLOSURE TO, AEP:NRC:05?8D TABLE 1 PLT. ID SYS. COi~P.

EVAL.WORKSHEET REF.FROM AEP

~E.RE NRC:005788 (NOTE 1)

I.D.2 Plt.Sfty Parameter

. QR-131 Display No Not Required II.B.l RCS Vents NSO-21 to 24 NSO-61 to 64 Yes Later II.B.3 II.D.3 Post Accident Sampling Valve Position Indication None Assigned QR-107 Lmt. Swtchs.

On NRV-151,

152, 153 Yes Yes Not Required Later LS-1 for Limit Switches II.E.1.2

.AFW Plow Ind.

FFI-210,220,

230, 240 Yes Later II.E.4.2.2 Cont. sol.

Dependapility QCR-301 (Note 2)

Yes Later II,F.l.l Noble Gas Monit.

ERS-1300,1400 2300

& 2400 VRS-1500

& 2500 No Not Required II.F.1.2 II.F.1.3 Iodine Monitor Post Accident CT High Range Area Monitor QR-108 VRA-1310,1510 2310

& 2510 No Yes Not Required Later II.F.1.4 II.F.1.5 Upper CT Area Monitor CT Pressure CT Wtr.Level VRS-1101,1201

2101, 2201 PPP-300 to 303 PPA-310 to 313 NLA-310 NLI-311, 320 321 Yes Yes No Yes Later 129

& I30 (NOTE 3)

Not Required Later II.F.1.6 CT Hydrogen Monit'or None Assigned No Not Applicable

C TABLE 1 (Continued)

PLT. ID SYS.COMP.

EVAL.WORKSHEET REF.FROi~f AEP

~E.R~E MiC:00578B (NOTE 1)

XI.F.2.1

~

Subcooling Htr.

(Pressure Temp. Inputs)

NTR-110 to 140 NTR-210 to 240 NPS-121, 122 Yes I28 (NTR's)

I22

& I23 (NPS Unit 1)

I23

& X24 (NPS Unit 2)

(NOTE 3)

Il.F.2.3 XI.G.1 Level Xnst.

Power Supplies to PZR Relief Valves Block Valves, and Level Indications NLX-110 to 130 111 to 131 NRV-151 to 153 LLMO-151 to 153 NLP-151 to 153 Yes Yes Later (NOTE 3)

Sll-1 (NRV's)

V9-1 (NMO's) and I18 (Unit 1)

NLP's I19 (Unit 2 NLP 's)

II.K.3.1 II.K.3. 5 II.K.3.2.2 Auto PORV Isol.

Auto Trip of RCS Pumps Anticipated Trip On Turbine Trip NM0-151,152,153 Not Applicable Yes V9-1 To Be Later Established No Not Required (NOTE 3)

Note 1 Only the primary device System Component Evaluation Worksheet is listed since the cross-reference listing included in AEP:NRC:0578B provides the correlation of associated items such as cable and termination, Note 2 Containment Isolation Valves for:

a) Item II.B.3: ECR-416,

417, 496, 497, 535

& 536, NCR-105,

106, 109

& 110 b) Item II.F.1.1: ECR-31, 32, 33, 35

& 36 c) Item II.F.1.6:

ECR-10 through-29 inclusiue Note 3 Page numbers corresponding to our forthcoming submittal No. AEP:NRC:0578B

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