ML17333A593

Clarifies Emergency Action Level (EAL) Statement as Requested by NRC Staff on 960926

ML17333A593
Person / Time
Site:	Cook
Issue date:	09/27/1996
From:	Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1192D, TAC-M89878, TAC-M89879, NUDOCS 9610110372
Download: ML17333A593 (10)

Text

CATEGORY 1 3>> REGULATE INFORMATION DISTRIBUTION'+STEM (RIDS)

ACCESSION NBR:9610110372 DOC.DATE: 96/09/27 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. American Electric Power Co., Inc.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Clarifies emergency action level (EAL) statement as C requested by NRC staff on 960926.

A DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR ENCI SIZE:

TITLE: OR Submittal: Emergency Preparedness Plans, Implement'g Procedures, C T NOTES:. E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME 'LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 HICKMANFJ 1 1 0 INTERNAL: E CENTER 0 2 2 NRR/DRPM/PERB 1 1 88 N3 RACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

U N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8

7 indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071395 INSMMA EAICIIIGAN PQWkN September 27, 1996 AEP:NRC:1192D Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 PROPOSED EMERGENCY ACTION LEVELS RESPONSE TO REQUEST FOR CLARIFICATION (TAC NOs. M89878 and M89879)

The purpose of this letter is to clarify one emergency action level (EAL) statement as requested by your staff on September 26, 1996.

The EAL statement S4 in the ALERT column, number 1, reads, "Loss of functions provided in OHP 4022.017.001, 'Loss of RHR Cooling'".

Your staff proposed and we agree to the following change to statement number 1: "Loss of shutdown cooling as evidenced by entry into OHP 4022.017.001, 'Loss of RHR Cooling'".

Page 20 of 26, revision 2, of PMP 2080 EPP.101, "Emergency Classification" and the EAL basis document S4-ALERT page have been changed and are provided in the attachment to this letter.

We remain available to answer any additional questions that the NRC staff might have.

Sincerely, E. E. Fitzpatrick Vice President

)en Attachment

'96iOii0372 960927

'PDR 'ADOCK 050003i5 F PDR

U. S. Nuclear Regulatory Commission AEP:NRC:1192D Page 2 cc: A. A. Blind A. B. Beach MD' DW & RPD NRC Resident Inspector - Bridgman J. R. Padgett

ATTACHMENT TO AEP:NRC:1192D PMP 2080 EPP.101, "Emergency Classification" Page 20 of 26, Revision 2 EAL Basis Document, page S Alert

PMP 2080.EPP.101 EMERGENCY CONDITION CATEGORIES Attachment A RECOGNITION CATEGORY: System Malfunctions ECC UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY SP: IC  :!NOT,'APPLlCABL'E;;::",,;::, ';IL'OSSOF,,,WATER,'f'EVEL",:',1N,THE',",.:":,.";.; ;NOT,APi? L'ICABLE:i;;";,'4-':,':;;,".::;.';-",:,";,

'";INABILtT'Yi'iT~O!MA!NTAINPL'ANTI!M'COLD""'3,:,'j""<"

INABILITYTO )REACTOR:,YESSEL THAT.:'.HAS;.OR'.,:;::"

MAINTAINA .,'.:;::.,WlL'L",.UNCOVERFUEI.-;:;IN,';THE .::::::Ã UNIT IN COLD SHUTDOWN Mode 5,6 EAL Not Applicable 1. Loss of shutdown cooling as evidenced by 1. Loss of functions provided in Not Applicable entry into OHP 4022.017.001, Loss of RHR OHP 4022.017.001, Loss of RHR Cooling Cooling.

-AND- -AND-

2. Temperature increase that either. 2. Core uncovery as Indicated by:

a. Exceeds Technical Specification cold a. RVLIS NR <44% - 0 RCPs shutdown limit of 200'F

-OR-4R-

b. Reactor Vessel Water Level

b. Results in an UNCONTROLLED increase < 614 feet in RCS temperature rise approaching the cold shutdown technical specification limit f 200oF Page 20 of 26 Rev. 2

P

~f V

DONALD C. GOOK NUCLEAR PLANT BASIS FOR EMERGENCY ACTION LEVELS

'CC CATEGORY NAME, EMERGENCY CLASS AND DESCRIPTION S-4: ALERT - INABILITYTO MAINTAINA UNIT IN COLD SHUTDOWN INITIATINGCONDITION Inability'to maintain plant in Cold Shutdown.

MODE APPLICABILITY 5 and 6 EAL THRESHOLD VALUES

1. Loss of shutdown cooling as evidenced by entry into OHP 4022.017.001, "Loss of RHR Cooling."

-AND-

2. Temperature increase that either

a. exceeds Technical Specification cold shutdown limit of 200'F

-OR-

b. results in an UNCONTROLLED increase in RCS temperature rise approaching the cold shutdown technical specification limit of 200'F.

BASIS (References)

UNCONTROLLED - means a temperature increase that is not the result of a planned evolution. It is included to preclude the declaration of an emergency for circumstances where decay heat removal is intentionally removed from service and is controlled within the requirements of the technical specifications.

The threshold value indicates a substantial degradation in the level of safety of the plant by indicating a potential complete loss of the ability to removal decay heat in the Cold Shutdown and Refueling modes. NRC concerns expressed in Generic Letter 88-17, S4 - ALERT

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