ML17333A587
| 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:
RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERN
- FILE CEN RCH/HICB
,NRR/DSSA/SRXB OGC/HDS2 COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
0 RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 1
1 NRR/DE/EMCB 1
1 NRR/DSSA/SPLB 1
1 NUDOCS-ABSTRACT 1
1 E
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 U.
S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
AEP:NRC:1192D 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/ '(
f 9610090284 Pbi002 PDR ADDCK 050003i5 P
POR LI Oc QL22
'I 1
h il
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 - INABILITYTO MAINTAIN A UNIT IN COLD SHUTDOWN INITIATINGCONDITION LOSS of water level in the reactor vessel that has or willuncover 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.
-OR-b.
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
l e
- l P
EMERGENCY CONDmON CATEGORIES PMP 2080.EPP.101 Attachment A
~
~
ECC UNUSUAL EVENT RECOGNITION CATEGORY: System Malfunctions ALERT SITE AREA EMERGENCY GENERAL EMERGENCY SQ:
INABILITYTO MAINTAINA UNIT IN COLD SHUTDOWN IC
~ NOT<APPLICABLF'"'j;+ "<'<ii:"..'"'.>:."i":."'N'<>~4:i" "'...INABILITY::;:TO,:MAINTAIN:PL'ANT:;.lN';.COLb;;.:,:,:~pe >'".
LOSS,:,OF,,:,WATER,LEVEL":IM::,.THE,';;';;;=;.
"REACTOR,:';VESSEL'":,THAT:HAS::.OR',",";:,'.
-'WILL',UNCO,'.VER:FiUEL";:;IN.".THE!.".';:',:,:;-:-::.-',:.."
'EACTOR: VESSEI'""""'iF"-"."""'"'-"":
>"'"'"'jNOT..'APPL'ICABLE'i:;$
- "';~".;
- ;.":;:~".;.:;:;:,",i,.':4 Mode 5,6 Not Applicable 1.
Loss of shutdown cooling as evidenced by entry into OHP 4022.017.001, "Loss of RHR Cooling" 1.
Loss of shutdown cooling as evidencef by entry into OHP 4022.017001, "Loss of RHR Cooling" Not Applicable
-AND-
-AND-2.
Temperature increase that either.
a.
Exceeds Technical Specification cold shutdown limit of 200'F 2.
Core uncoveiy as indicated by:
a.
RVLIS NR <44% - 0 RCPs 4R-4R-b.
Results in an UNCONTROLLED increase in RCS temperature rise approaching the cold shutdown technical specification limit of 2004F.
b.
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