ML17331A809

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Forwards Permanent Mod Details to Unit 2 600-volt Motor Control Ctrs & 4 Kv & 600-volt Switchgear Buses/Cabinets Per .Mods to Unit 1 Support Welding at Rear of Reactor & Generator Trip Breakers Per Also Encl
ML17331A809
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 09/24/1981
From: Hunter R
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML17331A811 List:
References
AEP:NRC:0486B, AEP:NRC:486B, GL-81-14, NUDOCS 8109290473
Download: ML17331A809 (10)


Text

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Office of Vuclear Reactor Regulationi Director CROCHET 05000315 05 0316 SUBJECT; For ~a> ds permanent nod detai control ctrs 5

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Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 Request for Relief from Technical Specification Section 3.0.3

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.:. r Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555

References:

(1) AEPSC letter from Mr. R. M. Jurgensen to Mr. H. R. Denton dated August 14, 1981 (2) AEPSC letter from Mr. R.

M. Jurgensen to Mr. H.

R. Denton dated August 17, 1981 (3)

NRC letter from Mr. T. M. Novak to Mr. John E. Dolan dated August 18, 1981

Dear Mv. Denton:

This letter is a follow-up letter to references 1

and 2 and responds to reference 3.

As noted in ouv August 17, 1981 letter, permanent modifi-cations were made to the following equipment at the Donald C.

Cook Nuclear Plant:

A) 600V Motor Control Centers - Unit 2 only i) MCC-2-AM - A ii) MCC-2-AM -

D B) 4 kV Switchgear Buses/Cabinets i ) Unit 1 - T11A, T11B, TllC, T11D ii ) Unit 2 - T21A, T21B, T21C, T21D C) 600V Switchgear Buses/Cabinets i ) Unit 1 - llA, llB, llC, 11D ii) Unit 2 - 21A, 218,

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f /00.0Q The details of these permanent modifications are shown in Attachment A.

810'7290473 810924 PDR ADOCK 05000315 P

PDR

Mr. H. R. Denton, Director AEP:NRC:0486B Our continued review of related electrical equipment and systems indicated that in Unit 1 the support welding at the rear of the reactor trip breakers and the generator trip breakers was deficient.

The following equipment was identified as needing modifications:

Reactor Trip Breakers:

RTA, RTB and BYA, BYB Generator Trip Breakers:

1S and 1N This deficiency was reported to your Staff on August 24, 1981 and permanent modifications were completed by August 25, 1981.

The details of these modifications are also included in Attachment A.

As of thi s date all equipment identified during the review performed as part of Generic Letter 81-14 which required corrective action has been repaired.

Copies of references (1) and (2) are attached for your information.

A $4,400 check accompanies this letter as indicated in Reference (1).

Very truly yours,

/

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4.'l.

R. S. Hunter Vice President cc:

John E. Dolan - Columbus R.

C. Callen G. Charnoff R.

>f. Jurgensen D. V. Shaller - Bridgman Joe Williams, Jr.

Region III Resident Inspector - Bridgman

ATTACHMENT A

TO AEP:NRC:04868.

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