ML030800563
| ML030800563 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/31/2003 |
| From: | Sands S NRC/NRR/DLPM/LPD3 |
| To: | Kanda W FirstEnergy Nuclear Operating Co |
| SANDS S, NRR/DLPM, 415-3154 | |
| References | |
| TAC MB7517 | |
| Download: ML030800563 (4) | |
Text
March 31, 2003 Mr. William R. Kanda Vice President - Nuclear FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97, A200 10 Center Road Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF LICENSE AMENDMENT REQUEST TO MODIFY THE EXISTING MINIMUM CRITICAL POWER RATIO SAFETY LIMITS (TAC. NO. MB7517)
Dear Mr. Kanda:
By letter dated January 30, 2003, FirstEnergy Nuclear Operating Company, requested approval of a license amendment for the Perry Nuclear Power Plant (PNPP) to modify the existing minimum critical power ratio safety limit contained in the technical specification 2.1.1.2.
During the review, the Nuclear Regulatory Commission staff has identified that additional information is needed in order to complete the review. Specific questions are presented in the enclosed request for additional information (RAI).
The enclosed questions have already been discussed with your staff. In order to accommodate PNPPs refueling outage, please respond to this RAI by April 14, 2003. If you have any questions concerning our review, or additional time is needed to respond to the RAI, please contact me at (301) 415-3154.
Sincerely,
/RA by Jon Hopkins for/
Stephen P. Sands, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for Additional Information cc w/encl: See next page
Perry Nuclear Power Plant, Unit 1 cc:
Mary E. OReilly FirstEnergy Corporation 76 South Main St.
Akron, OH 44308 Resident Inspectors Office U.S. Nuclear Regulatory Commission P.O. Box 331 Perry, OH 44081-0331 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4531 Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, OH 44060 Mr. Vernon K. Higaki Manager - Regulatory Affairs FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97, A210 10 Center Road Perry, OH 44081 Timothy Rausch, Plant Manager FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97, SB306 Perry, OH 44081 Mayor, Village of North Perry North Perry Village Hall 4778 Lockwood Road North Perry Village, OH 44081 Donna Owens, Director Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P. O. Box 4009 Reynoldsburg, OH 43068-9009 Carol OClaire, Chief, Radiological Branch Ohio Emergency Management Agency 2855 West Dublin Granville Road Columbus, OH 43235-7150 Mayor, Village of Perry P.O. Box 100 Perry, OH 44081-0100 Dennis Clum Radiological Assistance Section Supervisor Bureau of Radiation Protection Ohio Department of Health P.O. Box 118 Columbus, OH 43266-0118 Zack A. Clayton DERR Ohio Environmental Protection Agency ATTN: Mr. Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149 Chairman Perry Township Board of Trustees 3750 Center Road, Box 65 Perry, OH 44081 Daniel Z. Fisher Transportation Department Public Utilities Commission 180 East Broad Street Columbus, OH 43215-3793
March 31, 2003 Mr. William R. Kanda Vice President - Nuclear FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97, A200 10 Center Road Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF LICENSE AMENDMENT REQUEST TO MODIFY THE EXISTING MINIMUM CRITICAL POWER RATIO SAFETY LIMITS (TAC. NO. MB7517)
Dear Mr. Kanda:
By letter dated January 30, 2003, FirstEnergy Nuclear Operating Company, requested approval of a license amendment for the Perry Nuclear Power Plant (PNPP) to modify the existing minimum critical power ratio safety limit contained in the technical specification 2.1.1.2.
During the review, the Nuclear Regulatory Commission staff has identified that additional information is needed in order to complete the review. Specific questions are presented in the enclosed request for additional information (RAI).
The enclosed questions have already been discussed with your staff. In order to accommodate PNPPs refueling outage, please respond to this RAI by April 14, 2003. If you have any questions concerning our review, or additional time is needed to respond to the RAI, please contact me at (301) 415-3154.
Sincerely,
/RA by Jon Hopkins for/
Stephen P. Sands, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC THarris PD3-2 R/F OGC AMendiola ACRS SSands GGrant, RIII ADAMS Accession Number: ML030800563 OFFICE PM:LPD3-2 LA:LPD3-2 SC:LPD3-2 NAME SSands THarris AMendiola DATE 3/28/03 3/28/03 3/28/03 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION PERRY NUCLEAR POWER PLANT (PNPP)
LICENSE AMENDMENT REQUEST TO MODIFY EXISTING MINIMUM CRITICAL POWER RATIO (MCPR) SAFETY LIMITS CONTAINED IN TECHNICAL SPECIFICATIONS The Nuclear Regulatory Commission staff has reviewed the January 30, 2003, FirstEnergy Nuclear Operating Company submittal regarding changes to the PNPP technical specification change and has the following questions and comments concerning the submittal:
1.
It was shown (in Table 1 of Attachment 6 of the January 30, 2003, submittal) that both Cycle 9 and Cycle 10 used same power distribution uncertainty and non-power distribution uncertainty for the safety limit for minimum critical power (SLMCPR) calculation. Please provide the basis for the proposed large reduction of the SLMCPR value in a summary table for both Cycle 9 and Cycle 10. Also, provide the impact on SLMCPR reduction relative to Cycle 9 value due to flatness of the core bundle-by-bundle MCPR distributions and flatness of the bundle pin-by-pin power/R-factor distributions.
2.
Describe the detailed calculation process to model the core design through entire cycle to show any impact on the SLMCPR value for both two-loop operation and single-loop operation due to end-of-cycle penalty of top-peaked power shape.