ML17334A330

Provides Addl Info Re Installation of Containment Isolation Valve QCR-301,as Suppl to Util .Valve Will Be Installed During Scheduled 1982 Refueling Outage.Diagram Encl

ML17334A330
Person / Time
Site:	Cook
Issue date:	10/16/1981
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0405A, AEP:NRC:405A, NUDOCS 8110210289
Download: ML17334A330 (8)

Text

RKGULAiTORY INFORMATION< O'ISTR'I BUT'ION SYSTK'<I: (RIDS)

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'9', R'o Offfoci of Nuclear Reactor< Regulatfoni Dir ectori SUBJECT':: Provf des=addi fnfo re fn<stal l ation ot Containment'solatfon<

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INDIANA K'ICHIGAN ELECTRIC COMPANY P.

Oe BOX 18 BOWLING GR 8 EN STATION NEW YORK, N. Y'" 10004 October 16, 1981 AEP:NRC:0405A

.Donald C.

Cook Nuclear Unit Nos.

1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 Containment Isolation Valve gCR-301 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.

S. Nuclear Regulatory Commission Washington, D.

C. '0555

Dear Mr. Denton:

This letter provides additional information concerning the in-stallation of Containment Isolation Valve gCR-301 and supplements our December 10, 1980 letter (AEP:NRC:0449).

The NRC Safety Evaluation Report on our TMI-2 activities dated March 20, 1981 required that item 2.1.4 of the Technical Specifications be modified to classify the letdown orifice isolation valves as containment isolation valves.

In our letter of December 10; 1980 (AEP:NRC:0449),

we proposed the addition of another Containment Isolation Valve in the CVCS letdown line rather than this reclassification.

This design change is necessary due to the relatively high exposures anticipated to personnel required to perform 10 CFR 50 Appendix J leak rate testing for the orifice valves.

The attached figure shows the intended location of this isolation valve together with its leak testing connection.

The valve will be leak-rate tested in accordance with 10 CFR 50 Appendix J requirements, and operability tested as required by Technical Specifications issued on August 25.

1981.

In accordance with our containment isolation design

~/7 criteria in the FSAR, the valve is located as close to the containment 9

penetration as reasonably practical.

The control circuit design is the same as that utilized on the other Containment Isolation Valves at Cook Plant and is powered from the other redundant electrical safeguards train rather than from the existing in-series letdown isolation valve power train.

8110210289 811016 PDR ADCCK 05000315 P

PDR

f1r. Harold R. Denton AEP:NRC:0405A This installation of gCR-301 will allow convenience of access to perform the required testing.

A refueling outage is required for installation of this modification.

The valve and its associated equipment including solenoids, cables, etc., will be installed during the scheduled 1982 refueling outages of both Units 1

and 2.

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,

/os CC:

Vice President John E. Dolan R.

C. Callen G. Charnoff R.

W. Jurgensen O.

V. Shaller - Bri'dgman Joe Williams, Jr.

Region III Resident Inspector - Bridgman

)ll(lj;l(l

Mr.

Ha R. Oenton AEP:NRC:0405A bc:

S. J. Milioti/H. L. Sobel/J.

I. Castresana/S.

M. Toth/AEP:NRC:00405 S.

H. Horowitz/J.

M. Intrabartola R.

F. Hering/S.

H. Steinhart/J.

C. Jeffery R.

F. Kroeger B.

H. Bennett/R.

V. Sheehan J.

F. Stietzel - Bridgman S. Miner -

NRC DC-N-6015.1 AEP:NRC:00622 AEP:NRC:00405A

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