ML17320A255

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Forwards Update on Activities Re NUREG-0737,Items II.B.3, Post-Accident Sampling, II.F.1, Noble Gas Monitoring & III.D.3.4, Control Room Habitability. Info Supersedes Previous Correspondence on Topics
ML17320A255
Person / Time
Site: Cook  
Issue date: 12/14/1982
From: Hunter R
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-3.D.3.4, TASK-TM AEP:NRC:0678D, AEP:NRC:678D, NUDOCS 8212210125
Download: ML17320A255 (8)


Text

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'AUTH BYNAME AUTHOR AFFILIATION HUNTERiR,ST Indiana L Michigan Electric Co,

'REC IP, NAME RECIPIENT AFFILIATION DENTONgH,RE Office of Nuclear Reactor Regulationi Director

SUBJECT:

Forwards update on activities re NUREG>>0737'tems II,B,3g

."Post Accident Sampling~." II F,lp "Noble Gas Monitoring" L IIIAD,3'~ "Control 'Room Habitability ~

" Info supersedes previous cotrespondence on topics.

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0 INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 10 BOWLING GREEN STATION NEW YORK, N. Y. 10004 December 14, 1982 AEP:NRC: 0678D Donald C. Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG&737 IMPLEMENTATION DATES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555,

Dear Mr. Denton:

The Attachment to-this letter provides an update on Indiana Michigan Electric Company (X&MECo) activities related to Items II.B.3, IX.F.l Attachments 1,

2 and 6, and IIX.D.3.4 of NUREG-0737.

The completion dates provided for these items supersede or confirm, as indicated, the dates provided in previous correspondence on these topics.

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

Very truly yours, RSH /os Attachment R. S.

unter Vice President cc.

John E. Dolan Columbus

'. P. Alexich R. W. Jurgensen W. G. Smith, Jr.

R. C. Callen G. Charnoff NRC Resident Inspector at Cook Plant Bridgman

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Attachment to AEP:NRC:0678D Donald C. Cook Nuclear Plant Unit Nos.

1 and 2

NUREG-0737 Implementation Datee

"ATTACHMENT"TO AEP:NRC:0678D The following. information is being submitted at the request, of the NRC and reflects the current status and completion schedule for five NUREG-0737 items.

The completion schedules provided below supersede those provided in our previous correspondence on these topics.

Each of the five NUREG-0737 items is addressed below.

Item II.B.3 (Post-Accident Sam lin )

The Post-Accident Sampling (PAS) System is installed and operable (capable of obtaining a sample) in both Units No.

1 and No'. 2.

In accordance with the commitment made in our AEP:NRC:0716A submittal dated November 5, 1982, we have reviewed the accessibility and/or qualification of PAS System valves outside containment.

We have also investigated the normal sampling valves inside containment needed for sampling of the RCS for possible improvement or replacement.

The results of the reviews indicate that only minor modifications to the installed system will be needed.

These modifications will be limited to the replacement of specified radio<<sensitive components of the normal sampling system valves (e.g., "0" rings).

The above mentioned modifications notwithstanding, Indiana Michigdn Electric Company (ISMECo.) believes that the system presently installed fulfills the requirements of NUREG-0737; Item II.B.3.

II.F.I Attachment '1 "(Noble Gas Monitorin )

The equipment provided to fulfillthe requirements of this item was identified in Table 1 of the Attachment to our AEP:NRC:0586 submittal dated July 10, 1981.

0'ur recent submittal No. AEP:NRC:0705, dated November 5, 1982, clarified the function of certain radiation monitors in light of the NUREG-0737 requirements for noble gas monitoring and discussed several problems with radiation monitoring system equipment provided to fulfillthe requirements of this NUREG-0737 item.

The particular problems discussed involved failures of the electronic interface boxes for the main steam safety valves/power+ gerated relief valve monitors on secondary loops two and three in Unit No.

1 due to high ambient temperatures.

Moisture problems affecting the steam jet air ejectors and gland steam condenser vent monitors were also discussed.

Our analysis of the situation indicates that the current requirements of NUREG-0737; Item II.F.l - Attachment 1

for both Units of the Cook Plant, will be met by May 31',

1983.

Item II.F.1 - Attachment '2 (Iodine and Particulate Sam lin )

In our AEP:NRC:0678 submittal, dated May 14,

1982, I&MECo requested an extension to the implementation dates for this item until ninety days after the 'scheduled 1982 refueling outage for each Unit.

Our review of this item has resulted in a revised completion date for Units No, 1 and No.

2 of approximately April 30, 1983.

Item II.F.1 Attachment 6

(H dro en Monitori

)

As stated in our AEP:NRC:0631A submittal dated September 29,

1982, a Post-Accident Containment Hydrogen Monitoring System (PACHMS) is installed in each Unit of the Cook Plant in fulfillment of the requirements of NUREG-0737; Item II.F.l. - Attachment 6.

Operation of the PACHMS will require the issuance of revised Technical Specifications by the NRC.

Proposed Technical Specifications were included in the AEP:NRC:0631A submittal.

I&MECo believes that the system presently installed fulfills the requirements of NUREG<<0737; Item II.F.1..

Item III.D.3.4. (Control Room Habitabilit )

In our AEP:NRC:0678A submittal dated June 28,

1982, I&MECo confirmed the January 1,

1983 commitment date for implementation of the control room habitability modifications set forth in our AEP:NRC:0398C submittal dated February 9, 1981.

Our present schedule calls for physical installation of required equipment by December 31, 1982.

However, final tie-in of the Unit No.

1 Reactor Protection System into the control room isolation logic will not be completed prior to the end of the current Unit No.

2 refueling outage, scheduled for the middle to the end of January, 1983.