ML17333A937
| ML17333A937 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/08/1997 |
| From: | Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1202C, NUDOCS 9707140447 | |
| Download: ML17333A937 (6) | |
Text
CATEGORY j REGUDATOIIINFORMATION DIBTRIBUTION TEM (RIDE)
~ ACCESSION NBR:9707140447 DOC.DATE: 97/07/08 NOTARIZED: YES DOCKET ¹ FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear'ower Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
American Electric Power Co., Inc.
FITZPATRICK,E.
Indiana Michigan Power Co. (formerly Indiana s Michigan Ele RECIP.NAME'ECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards response to 970507 RAI re util 941116 request for change in min time decay required after shutdown for movement of irradiated fuel from core to storage in spent fuel pool.
DISTRIBUTION CODE:
IE26D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Startup Report/Refueling Report (per Tech Specs)
NOTES:
RECIPIENT ID CODE/NAME PD3-3 PD COPIES LTTR ENCL 1
1 RECIPIENT ID CODE/NAME HICKMAN,J COPIES LTTR ENCL 1
1 INTERNA ILE EXTERNAL: NOAC FILE 01 1
1 1
1 1
1 NRR/DSSA/SRXB/B NRC PDR 1
1 1
1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK/
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 7
ENCL 7
Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1395 IIIIDIANA MICHIGAN IsWkR July 8, 1997 AEP: NRC: 1202C Docket No.:
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
RESPONSE
TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REFUELING OPERATIONS DECAY TIME This letter and its attachment constitute a
response to the May 7,
- 1997, NRC request for additional information concerning our
.November 16, 1994, submittal.
Our original submittal requested a
change in the minimum time decay required after shutdown for movement of irradiated fuel from the core to storage in the spent fuel pool.
Sincerely, ee E.
E. Fitzpatrick Vice President SWORN AND SUBSCRIBED BEFORE ME THIS DAY OF 1997 Notary Public My Commission Expires Md/
JANICE M. BICKERS Nary Pubic, Bemen County, M M7 Cornrnission Expires Feb. 16, 2001 vlb Attachment A. A. Blind.
A. B. Beach MDEQ -
DW 6c RPD NRC Resident Inspector J.
R. Padgett 9707140447 rr70708 PDR ADOCK OS0003XS PDR llillllillllllllllllllllllllllllllllllll
ATTACHMENT TO AEP:NRC: 1202C
'E REQUEST FOR ADDITIONAL INFORMATION REGARDING REFUELING OPERATIONS DECAY TIME RESPONSE
~,
Attachment to AEP:NRC:1202C Page 1
question "Provide a discussion of the procedures to be utilized by the Donald C.
Cook site staff to monitor and control the spent fuel pool water temperature and the decay heat load so as to remain within the design basis limiting values for routine refuelings and the maximum heat load cases.
Include discussion of the location of needed instrumentation, means of monitoring it, and integration of operations staff activities with engineering staff activities in order to implement the procedure(s)."
Res onse to uestion Normal operating procedures, annunciator response procedures, routine monitoring procedures, augmented monitoring procedures, and abnormal operating procedures provide direction for the operation and control of the spent fuel pool cooling and cleanup system (SFPCCS)
The cumulative guidance of these procedures and current practices are discussed in this response.
The thermal design bases of the SFPCCS are to maintain temperature less than 159.54F, with a heat load such that boiling will not occur for at least 5.74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> in the event of loss of all cooling capability.
Peak spent fuel pool (SFP) temperature and time to boil analyses are coordinated by regulatory affairs and engineering staff prior to full core offloads to ensure these design bases are not violated during refueling operations.
SFP temperature indication and annunciation are available locally at the SFP (two thermal sensors located in the east end of the SFP),
and remotely at the control subpanel in the SFP pump room.
An SFP temperature annunciator alarm is'vailable in each unit's control
- room, and is monitored by the control room staff.
The procedures require tours be performed each shift by the operations staf f to confirm local SFP temperature readings are within acceptable ranges.
The normal operating temperature range for the SFP is determined from an administrative temperature goal substantially lower than the design basis temperature.
Prior to a full core offload, the peak SFP temperature analysis result is utilized by engineering staff to determine the maximum SFP temperature goal for the specific refueling operation.
The control room SFP temperature annunciator is utilized to maintain the SFP temperature below the determined administrative goal.
Annunciator response procedures provide direction to the operations staff to return the SFP temperature to the normal operating temperature range.
Additional oversight and monitoring of the SFPCCS is provided during refueling operations as a portion of the shutdown risk management program.
This program provides administrative controls for establishing overall plant requirements so
- that, overall shutdown risk levels are evaluated and minimized.
A "guarded equipment" designation has historically been assigned to the SFP component cooling water supply and supporting systems, as well as the power supply to the SFP cooling.
A "guarded equipment" designation limits maintenance activities on the equipment.
In addition, SFPCCS performance monitoring,
- trending, system walkdowns, and engineering reviews are conducted by the engineering staff.
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