ML17320B009

Application for Amend to License DPR-74,consisting of Proposed Emergency Change to Tech Spec 3.9.2 Re Refueling Operations

ML17320B009
Person / Time
Site:	Cook
Issue date:	04/24/1984
From:	Hering R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17320B010	List: ML17320B009 ML17320B011
References
AEP:NRC:0890, AEP:NRC:890, NUDOCS 8404300023
Download: ML17320B009 (6)

Text

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REGULATORY <FORMATION t)ISTRIBUTION S) EM (RIDS)

ACCESSION NBR:6400300023 DOC,DATE: 64/04/24 NOTARIZED; NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Planti Unit 2i Indiana 8 05000316 AUTH'AtlE AUTHOR AFFILIATION HERINGgR.F. Indiana 8 Michigan Electric Co.

REC IP. NAME RECIPIENT AFFILIATION t DENTONrH ~ RE Office of Nuclear Reactor Regulationp Director I

SUBJECT:

Application for amend to License DPR-74iconsisting of proposed emergency change to Tech Spec 3.9.2 re refueling oper ations, DISTR UTION CODE: A001S COPIES RECEIVED:LTR ENCL SIZE:

T T,: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAYiE LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 01 7 7 INTERNAL; ELD/HDS3 0 NRR/DE/MTEB 1 NRR/DL DIR 1 NRR/DL/ORAB 1 0

'4 1

I/METB' 1 NRR/DSI/RAB 1 1 RGN3 1 1 EXTERNAL: ACRS 09 6 6 LPDR 03 1 1

'NRC PDR 02 1 1 NSIC 05 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 23

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INDIANA 8 NICHIGAN ELECTRIC CONPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 April 24, 1984 AEP:NRC:0890 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License Nos. DPR-74 PROPOSED EMERGENCY CHANGE TO TECHNICAL SPECIFICATION 3.9.2 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

Due to specific circumstances currently existing at D. C. Cook Nuclear Plant Unit 2, we are requesting an emergency change to the subject Technical Specification (T/S). Specifically, the T/S states:

"As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.

ACTION: With the zeguizements of the ahove specification not satisfied, immediately suspend all opezations involving CORE ALTERATIONS or positive reactivity changes..."

The current circumstances at the Plant are:

(1) On Friday, April 20, 1984, during the Unit 2 refueling activities, one of the two source range neutron flux monitors began behaving erratically, rendering it inoperable.

(2) We have proceeded to partially dewater the refueling cavity to make repairs to the inoperable monitor. We have replaced the detector and are still unable to achieve successful operation.

(3) Defueling (CORE ALTERATIONS) activities were suspended with all but 30 fuel assemblies removed.

(4) Two of the remaining 30 fuel assemblies contain sources for startup of the reactor. Fifteen assemblies are near operable detector N31 and fifteen assemblies are near inoperable detector N32.

(5) Continued delays to fix the inoperable detector prior to completion of defueling would delay startup commensurately for no apparent safety reasons.

8404300023 840424 '

PDR ADOCK 05000316 'DR

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~ Mr. Harold R. Dento AEP:NRC:0890

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Therefore, we are proposing that T/S 3.9.2 be amended to allow defueling of the remaining 30 assemblies during the current Unit 2 (1984) outage, with only one OPERABLE source range neutron flux monitor.

Based on our review of the current core conditions, we have concluded that the core multiplication factor (k-effective) will always be reduced by the removal of fuel assemblies and the commensurate replacement of 2000 ppm borated water. Therefore, we believe the remaining 30 fuel assemblies could be removed with only one OPERABLE source range neutron monitor and not create significant hazards consideration as defined 10 CFR 50.92. Specifically, the proposed change will not increase the probability or consequences of a previously-analyzed accident. The change may reduce in some way a safety margin, but it is clearly within the acceptance criteria for maintaining the core subcritical.

The Attachment to this letter contains the proposed revised T/S page. The change is indicated by vertical bars drawn on the right hand margin of the page.

The proposed change has been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at its next scheduled meeting.

Pursuant to the requirements of 10 CFR 50.91(b)(1), a copy of this letter and its attachment have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission.

We interpret this application for a license amendment to constitute a Class III Amendment as defined in 10 CFR 170.22. Therefore, a check in the amount of $ 4000.00 will be forwarded in the near future as payment for processing the aforementioned request.

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 Presiden Attachment cc: John E. Dolan W. G. Smith, Jr. Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman

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