ML030800563

RAI, Review of License Amendment Request to Modify the Existing Minimum Critical Power Ratio Safety Limits

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 Carol OClaire, Chief, Radiological Branch 76 South Main St. Ohio Emergency Management Agency Akron, OH 44308 2855 West Dublin Granville Road Columbus, OH 43235-7150 Resident Inspectors Office U.S. Nuclear Regulatory Commission Mayor, Village of Perry P.O. Box 331 P.O. Box 100 Perry, OH 44081-0331 Perry, OH 44081-0100 Regional Administrator, Region III Dennis Clum U.S. Nuclear Regulatory Commission Radiological Assistance Section Supervisor 801 Warrenville Road Bureau of Radiation Protection Lisle, IL 60532-4531 Ohio Department of Health P.O. Box 118 Sue Hiatt Columbus, OH 43266-0118 OCRE Interim Representative 8275 Munson Zack A. Clayton Mentor, OH 44060 DERR Ohio Environmental Protection Agency Mr. Vernon K. Higaki ATTN: Mr. Zack A. Clayton Manager - Regulatory Affairs P.O. Box 1049 FirstEnergy Nuclear Operating Company Columbus, OH 43266-0149 Perry Nuclear Power Plant P.O. Box 97, A210 Chairman 10 Center Road Perry Township Board of Trustees Perry, OH 44081 3750 Center Road, Box 65 Perry, OH 44081 Timothy Rausch, Plant Manager FirstEnergy Nuclear Operating Company Daniel Z. Fisher Perry Nuclear Power Plant Transportation Department P.O. Box 97, SB306 Public Utilities Commission Perry, OH 44081 180 East Broad Street Columbus, OH 43215-3793 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

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.