ML032970341
| ML032970341 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/28/2003 |
| From: | Mohammed Shuaibi NRC/NRR/DLPM/LPD3 |
| To: | Nazar M Indiana Michigan Power Co |
| References | |
| TAC MB7162, TAC MB7163 | |
| Download: ML032970341 (5) | |
Text
October 28, 2003 Mr. Mano K. Nazar American Electric Power Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 1 - CORRECTION TO STAFF SAFETY EVALUATION FOR AMENDMENT NO. 278 (TAC NO. MB7162 AND MB7163)
Dear Mr. Nazar:
By letter dated July 18, 2003, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 278 to Facility Operating License No. DPR-58 for the Donald C. Cook Nuclear Plant, Unit 1. On Page 5 of the NRC staffs safety evaluation for this amendment (Enclosure 2 to the July 18th letter) the staff incorrectly made a reference to Westinghouse WCAP 15789.
This reference was made in relation to the staffs review of pressurized thermal shock reference temperature RTPTS. The correct reference is Westinghouse WCAP-15879. Enclosed is a corrected Page 5 to be used in place of the page in the safety evaluation issued with Amendment No. 278.
Sincerely,
/RA by DHood for/
Mohammed A. Shuaibi, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
Corrected Page 5 of Staff Safety Evaluation for Amendment No. 278 cc w/encls: See next page
ML032970341 OFFICE PM:PD3-1 LA:PD3-1 SC:PD3-1 NAME DHood for MShuaibi THarris MShuaibi for LRaghavan DATE 10/28/03 10/28/03 10/28/03
Donald C. Cook Nuclear Plant, Units 1 and 2 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, MI 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, MI 49127 David W. Jenkins, Esquire Indiana Michigan Power Company One Cook Place Bridgman, MI 49106 Mayor, City of Bridgman P.O. Box 366 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 Mr. John A. Zwolinski Director, Design Engineering and Regulatory Affairs Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107 Michigan Department of Environmental Quality Waste and Hazardous Materials Div.
Hazardous Waste & Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P. O. Box 30241 Lansing, MI 48909-7741 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 Michael J. Finissi, Acting Site VP and Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Corrected by letter from M. Shuaibi (NRC) to M. Nazar (AEP) dated October 28, 2003.
1.8x1019 n/cm2 which is the peak value at the inside surface of the vessel, thus, is acceptable.
The PT limit curves, the low-temperature overpressure protection setting, and the RTPTS to the end of the current license are determined by the properties of the intermediate to lower shell circumferential weld.
RTPTS to 32 EFPYs 10 CFR 50.61 requires recalculation of the RTPTS value whenever there are significant changes in the conditions of the beltline region. The planned power uprate and the change in critical element warrant recalculation of the RTPTS.
The related analysis was performed by Westinghouse and is documented in WCAP-15879 l
which was included in the licensees December 10, 2002, application. The 32 EFPY fluence was derived from WCAP-12483 and is an acceptable value. The evaluation of RTPTS followed the guidance in RG 1.99. The estimated value is 242 F. The relevant screening criterion in 10 CFR 50.61 is lower than 300 F, therefore, the RTPTS is acceptable.
4.0
SUMMARY
The NRC staff has determined that the proposed P-T limit curves are consistent with the alternate assessment criteria and methods of ASME Code Case N-641, and satisfy the requirements of 10 CFR 50.60(a)and(b), Acceptance Criteria for Fracture Prevention Measures for Light-water Nuclear Power Reactors for Normal Operation; Appendix G to 10 CFR Part 50, Fracture Toughness Requirements; and Appendix G to Section XI (1995 Edition), as exempted by the methods of analyses in the code case. The proposed curves for D.C. Cook, Unit 1 are, therefore, approved for incorporation into the technical specifications.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes the requirements with respect to installation or the use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (68 FR 15762). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.