ML17333A988
| ML17333A988 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/12/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. |
| References | |
| TAC-M91023, TAC-M91024, NUDOCS 9708180243 | |
| Download: ML17333A988 (8) | |
Text
August 12, 1997 Mr. E. E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107
SUBJECT:
DONALDC. COOK NUCLEAR PLANT, UNIT NOS.
1 AND 2 - REQUEST FOR ADDITIONALINFORMATION RE: REFUELING OPERATIONS DECAY TIME (TAC NOS. M91023 AND M91024)
Dear Mr. Fitzpatrick:
The staff is continuing to review your submittals dated November 16, 1994, February 1, 1996, August 1, 1996, and July 8, 1997.
We will require additional information to complete our review.
Please respond to the enclosed Request for Additional Information within 30 days.
Please contact me at (301) 415-3017 ifyou have any questions on the above.
Sincerely, John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315/316
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 August 12, 1997 Mr. E. E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107
SUBJECT:
DONALDC. COOK NUCLEAR PLANT, UNIT NOS.
1 AND 2 - REQUEST FOR ADDITIONALINFORMATION RE: REFUELING OPERATIONS DECAY TIME (TAC NOS. M91023 AND M91024)
Dear Mr. Fitzpatrick:
The staff is continuing to review your submittals dated November 16, 1994, February 1, 1996, August 1, 1996, and July 8, 1997.
We will require additional information to complete our review.
Please respond to the enclosed Request for Additional Information within 30 days.
Please contact me at (301) 415-3017 ifyou have any questions on the above.
Sincerely, John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315/316
Enclosure:
Request for Additional Information cc w/encl: See next page
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E. Fitzpatrick Indiana Hichigan Power Company CC:
Regional Administrator, Region III U.S."Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street
- Lansing, HI 48913 Township Supervisor Lake Township Hall P.O.
Box 818
- Bridgman, HI 49106 Al Blind, Site Vice President Donald C.
Cook Nuclear Plant 1 Cook Place
- Bridgman, HI 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, HI 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW.
Washington, DC 20037 Hayor, City of Bridgman P.O.
Box 366
- Bridgman, HI 49106 Special Assistant to the Governor Room 1 - State Capitol
- Lansing, HI 48909 Drinking Water and Radiological Protection Division Hichigan Department of Environmental guality 3423 N. Hartin Luther King Jr Blvd P.O.
Box 30630 'CPH Mailroom
- Lansing, HI 48909-8130 Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Steve J.
Brewer Indiana Hichigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, HI 49107
0
REQUEST FOR ADDITIONALINFORMATION FOR TECHNICALSPECIFICATION CHANGE REGARDING THE CORE SHUTDOWN TIME FOR DECAY HEAT CALCULATION DONALDC. COOK NUCLEAR PLANT, UNIT NOS.
1 AND 2 DOCKET NOS. 50-315 AND 50-316 (TAC NOS. M91023 AND M91024) 1.0 With regard to the spent fuel pool (SFP) cooling analyses for the normal refueling scenarios, Cases 1A and 2 as presented in the February 1, 1996, submittal are based on the spent fuel assemblies discharged from Unit 1 during the cycle 25A. Since Unit 2 will be operating at a higher power level than Unit 1 (3,588 MWt vs. 3,250 MWt), the analyses for Case 1A and 2 should be revised based on the spent fuel assemblies discharged from Unit 2 during cycle 20B. Also, Tables 3, 4, and 5, and Figures 1, 3, 6, and 8 should be revised to include the results from the above revised analyses.
2.0 In the analyses for the scenario of back-to-back full core discharge with two SFP cooling trains (Case 3), spent fuel assemblies from Unit 2 are assumed to be discharged in three groups each with a different bumup value.
Provide curves to show the decay heat rates as a function of time generated in the SFP from each of these groups.
3.0 In the response (A 4) to the staffs RAI provided in the February 1, 1996, submittal, decay heat generation rates for spent fuel assemblies from each previous discharge cycle are provided.
Decay heat generation rates from these previously discharged spent fuel assemblies are also provided in Attachments 2 and 3 to the letter dated August 1, 1996.
However, decay heat generation rates presented in the August 1, 1996, submittal deviate significantly from that presented in the February 1, 1996, submittal; provide clanflcation and justification for this discrepancy.
4.0 Is full-core offload a current practice during normal refueling?
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