ML17333A935
| ML17333A935 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/09/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| TAC-M96064, TAC-M96363, NUDOCS 9707110042 | |
| Download: ML17333A935 (7) | |
Text
duly 9, 1997 Mr. E. E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, Ml 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONALINFORMATIONRE'OWER UPRATE PROGRAM (TAC NOS.
M96363 AND M96364)
Dear Mr. Fitzpatrick:
The staff is reviewing your submittal dated July 11, 1996.
We will require additional information to complete our review.
Please respond to the enclosed Request for Additional Information within 60 days.
Please contact me at (301) 415-3017 if you have any questions on the above.
Sincerely, Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Request for Additional Information cc w/encl:
See next page DISTRIBUTION:
Docket File PUBLIC EAdensam (EGA1)
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/97 nci<CIAI RECORD COPY
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July 9, 1997 Mr. E. E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, Ml 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONALINFORMATION RE: POWER UPRATE PROGRAM (TAC NOS.
M96363 AND M96364)
Dear Mr. Fitzpatrick:
The staff is reviewing your submittal dated July 11, 1996.
We willrequire additional information to complete our review.
Please respond to the enclosed Request for Additional Information within 60 days.
Please contact me at (301) 415-3017 if yo'u have any questions on the above.
Sincerely, Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Request for Additional Information cc w/encl; See next page DISTRIBUTION:
Docket File PUBLIC EAdensam (EGA1)
PD3-3 Reading JRoe GMarcus OGC ACRS GGrant, Rill CWu DOCUMENT NAME: G:iDCCOOKiCO96364.RAI OFFICE NAME DATE PM:PD33 JHickman g/
/97 LA:PD33 E
CBoyle
/97 OFFICIAL REC RD COPY
Hr. E.
E. Fitzpatrick Indiana Michigan Power Company CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street
- Lansing, Michigan 48913 Township Supervisor Lake Township Hall P.O.
Box 818 Bridgman, Michigan 49106 Al Blind, Site Vice President Donald C. Cook Nuclear Plant 1 Cook Place Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.
W.
Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol
- Lansing, Michigan 48909 Drinking Water and Radiological Protection Division Michigan Department of Environmental guality 3423 N. Hartin Luther King Jr Blvd P. 0.
Box 30630 CPH Mailroom
- Lansing, Michigan 48909-8130 Donald C.
Cook Nuclear Plant Units 1 and 2
Hr. Steve J.
Brewer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, Michigan 49107
REQUEST FOR ADDITIONALINFORMATION FOR TECHNICALSPECIFICATION CHANGE TO REFLECT POWER UPRATE DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 (TAC NOS. M96363 AND M96364) 1
~
In Section 2.0 of Reference 2, you indicated that WCAP-11902 and Supplement were used as the basis for the evaluation'f the Unit 2 operation at a core power level of 3588 MWt. However, WCAP-11902 licensing report was reviewed and approved, by the staff, for D. C. Cook Unit 1 operating at 3250 MWt. Clarify whether the Supplement to WCAP-11902, entitled, "Rerated Power and Revised Temperature and Pressure Operation for Cook Nuclear Plant Units 1 and 2 Licensing Report," was reviewed and approved by the staff for application at Cook Nuclear Plant (CNP).
If not, state the basis of applying these two previous evaluations for CNP operation at a power level of 3588 MWt. Also provide a table of comparison for all performance parameters between the proposed Unit 2 uprate rate and the previous rerated program.
2.
Clarify whether the rerating analyses of the pressure transients and the postulated loss-of-coolant accident (LOCA) include the proposed'pressurizer safety and relief valve tolerance z3%, and the previously NRC-approved main steam safety and relief valves tolerance of z3%.
Ifnot, state how the rerating analyses applies to the proposed Unit 2 power uprate.
3.
Discuss the operability of safety-related mechanical components (i.e., valves and pumps) affected by the power uprate to ensure that the performance specifications and technical specification requirements (e.g., flow rate, close and open times) will be met for the proposed power uprate.
Confirm that safety-related motorwperated valves (MOVs) will be capable of performing their intended function(s) following the power uprate including such affected parameters as fluid flow, temperature, pressure and differential pressure, and ambient temperature conditions.
Identify mechanical components for which operability at the uprated power level could not be confirmed.
4.
In reference to Sections 3.11.2 and 3.11.3 of Reference 2 (WCAP-14489), provide the maximum calculated stresses and Cumulative Usage Factors at the most limiting locations and components of the reactor vessel and internal, steam generator, reactor coolant pump, pressurizer, and control rod drive mechanism.
Also provide the allowable code limits, the code, and code edition used in the evaluation for the power uprate.
If different from the code of record, provide the necessary justification.
5.
In Table 2.1-1 of Reference 1, the current core power limit is 3391 MWt thermal.
On page 2 of Appendix 1 to Reference 1, the group one proposed changes have the current rated core power level of 3411 MWt. Clarify the difference.
ENCLOSURE
6.
Discuss the analytical methodology and assumptions used in evaluating pipe supports, nozzles, penetrations, guides, valves, pumps, heat exchangers and support anchors at the power uprate conditions.
Were the analytical computer codes used in the evaluation different from those used in the original design-basis analysis'f so, identify the new codes and provide justification for using the new codes and state how the codes were qualified for such applications.
7.
Discuss the effect of flow induced vibration on the steam generator U-bend tubes and the heat exchanger in consideration of high flow rate required for the power uprate.
REFERENCES:
1.
Letter (AEP:NRC:1223) from American Electric Power to the NRC, "Donald C. Cook Nuclear Plant, Units 1 and 2, License Nos. DPR-58 and DPR-74, Proposed License and Technical Specification Changes, and Increase Unit 2 Rated Thermal Power," dated July 11, 1996, and attachments.
2.
Westinghouse Electric Corporation, WCAP-14489, Revision 1, "Donald C. Cook Nuclear Plant Unit 2 3600 MWt Uprating Program Licensing Report," dated May 1996.