ML17333A587

Expresses Apologies for Pages Being Omitted from Out Aep: NRC:1192D Ltr Submitted 960927

ML17333A587
Person / Time
Site:	Cook
Issue date:	10/02/1996
From:	Toth K INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1192D, NUDOCS 9610090284
Download: ML17333A587 (8)

Text

CATEGORY 1 REGULAT INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION,'NBR:9610090284 DOC.DATE: 96/10/02 NOTARIZED: NO 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 TOTH,K.J. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME 'RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Expresses apologies for pages being omitted from out AEP:

NRC:1192D ltr submitted 960927.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERN  : FILE CEN 1 1 NRR/DE/EMCB 1 1 RCH/HICB 1 1 NRR/DSSA/SPLB 1 1

,NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

0 U

E*

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 12 ENCL 11

I~ Indiana FI1ichigan Power Company 500 Circle Orive Buchanan, Mi 491071395 INQlAMl NlCHICAlN PQWM October 2, 1996 AEP:NRC:1192D U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Due to an administrative oversight, the attached pages were inadvertently omitted from out AEP:NRC:1192D letter submitted on September 27, 1996. I apologize for any inconvenience this oversight may have caused.

Sincerely, K. J. Toth .

Attachment pg)D/ '(

9610090284 Pbi002 PDR ADDCK 050003i5 f P POR LI Oc QL22

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DONALD C. COOK NUCLEAR PLANT BASIS FOR EMERGENCY ACTION LEVELS ECC CATEGORY NAME, EMERGENCY CLASS AND DESCRIPTION SP: 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 aoproaching the cold shutdown technical specification.!imit 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

C I' ~ h J

DONALD C. COOK NUCLEAR PLANT BASIS FOR EMERGENCY ACTION LEVELS ECC CATEGORY NAME, EMERGENCY CLASS AND DESCRIPTION S-4: SITE AREA EMERGENCY - INABILITY TO MAINTAIN A UNIT IN COLD SHUTDOWN INITIATINGCONDITION LOSS of water level in the reactor vessel that has or will uncover fuel in the reactor vessel.

MODE APPLICABILITY 5 and 6 EAL THRESHOLD VALUES Loss of reactor vessel water level as indicated by:

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

-AND-

2. Core uncovery as indicated by:

a. RVLIS NR < 44%-0 RCPs

-OR-

b. Reactor Vessel Water Level <

614'ASIS (References)

LOSS - Inability to restore RHR operability (e.g., restart the RHR pumps) when required.

The threshold values indicate that severe core damage can occur and RCS integrity may not be assured and thus indicate failures of functions needed for the protection of the public.

S4 - SITE AREA EMERGENCY

le

l P

PMP 2080.EPP.101 EMERGENCY CONDmON CATEGORIES Attachment A

~ ~

RECOGNITION CATEGORY: System Malfunctions ECC UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY SQ: IC ~ NOT< APPLICABLF'"'j;+ "<'<ii:"..'"'.>:."i":."'N'<>~4:i" "'...INABILITY::;:TO,:MAINTAIN:PL'ANT:;. lN';.COLb;;.:,:,:~pe>'". LOSS,:,OF,,:,WATER,LEVEL":IM::,.THE,';;';;;=;.  ;:;"';~".;::;.":;:~".;.:;:;:,",i,.':4 INABILITYTO "REACTOR,:';VESSEL'":,THAT:HAS::.OR',",";:,'.

>"'"'"'jNOT..'APPL'ICABLE'i:;$

MAINTAINA -'WILL',UNCO,'.VER:FiUEL";:;IN.".THE!.".';:',:,:;-:-::.-',:.."

UNIT IN COLD 'EACTOR: VESSEI'""""'iF"-"."""'"'-"":

SHUTDOWN Mode 5,6 Not Applicable 1. Loss of shutdown cooling as evidenced by 1. Loss of shutdown cooling as Not Applicable entry into OHP 4022.017.001, "Loss of RHR evidencef by entry into OHP Cooling" 4022.017001, "Loss of RHR Cooling"

-AND-

-AND-

2. Temperature increase that either.

2. Core uncoveiy as indicated by:

a. Exceeds Technical Specification cold shutdown limit of 200'F a. RVLIS NR <44% - 0 RCPs 4R- 4R-

b. Results in an UNCONTROLLED increase b. Reactor Vessel Water Level in RCS temperature rise approaching the < 614 feet cold shutdown technical specification limit of 2004F.

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