ML081980628
| ML081980628 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/31/2008 |
| From: | Goodwin C NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| Goodwin C | |
| References | |
| TAC MD8458 | |
| Download: ML081980628 (5) | |
Text
July 31, 2008 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO INSERVICE INSPECTION RELIEF REQUEST IR-054 (TAC NO. MD8458)
Dear Mr. Bezilla:
By letter to the Nuclear Regulatory Commission (NRC) dated March 31, 2008 (Agencywide Documents Access and Management System Accession No. ML080990625), FirstEnergy Nuclear Operating Company submitted a relief request from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI examination requirements regarding reactor pressure vessel nozzle-to-vessel welds and nozzle inner radii, for the Perry Nuclear Power Plant, Unit No. 1. The proposed alternative utilizes Code Case N-702, AAlternative Requirements for Boiling-Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,@ with its underlying technical basis documented in a BWR Vessel and Internals Project (BWRVIP) report BWRVIP-108, Technical Basis for the Reduction of Inspection Requirements for the Boiling-Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on July 21, 2008, it was agreed that you would provide a response within 45 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely,
/RA/
Cameron S. Goodwin, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO INSERVICE INSPECTION RELIEF REQUEST IR-054 (TAC NO. MD8458)
Dear Mr. Bezilla:
By letter to the Nuclear Regulatory Commission (NRC) dated March 31, 2008 (Agencywide Documents Access and Management System Accession No. ML080990625), FirstEnergy Nuclear Operating Company submitted a relief request from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI examination requirements regarding reactor pressure vessel nozzle-to-vessel welds and nozzle inner radii, for the Perry Nuclear Power Plant, Unit No. 1. The proposed alternative utilizes Code Case N-702, AAlternative Requirements for Boiling-Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,@ with its underlying technical basis documented in a BWR Vessel and Internals Project (BWRVIP) report BWRVIP-108, Technical Basis for the Reduction of Inspection Requirements for the Boiling-Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on July 21, 2008, it was agreed that you would provide a response within 45 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, Cameron S. Goodwin, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMCGoodwin RidsNrrLATHarris RidsAcrsAcnw&mMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr SSheng, NRR RidsNrrDciCvib ADAMS Accession Number: ML081980628 *By memo (ML081780164)
OFFICE LPL3-2/PM LPL3-1/LA DCI/CVIB/BC LPL3-2/BC NAME CGoodwin THarris MMitchell*
RGibbs DATE 07 / 28 /08 07 / 30 /08 6/26/08 07 / 31 /08 OFFICIAL RECORD COPY
Perry Nuclear Power Plant, Unit No. 1 cc:
David W. Jenkins, Attorney FirstEnergy Corporation Mail Stop A-GO-15 76 South Main Street Akron, OH 44308 Resident Inspector's Office U.S. Nuclear Regulatory Commission P.O. Box 331 Perry, OH 44081-0331 Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, OH 44060 Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A200 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 Mayor, Village of North Perry North Perry Village Hall 4449 Lockwood Road North Perry Village, OH 44081 Dean Jagger, Chief Boiler Inspector 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 Robert Owen 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 James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Joseph J. Hagan President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308
Perry Nuclear Power Plant, Unit No. 1 cc:
Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Paul A. Harden Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 In reviewing the FirstEnergy Nuclear Operating Company=s (FirstEnergy) submittal dated March 31, 2008 (Agencywide Documents Access and Management System Accession No. ML080990625), related to a relief request from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI examination requirements regarding reactor pressure vessel (RPV) nozzle-to-vessel welds and nozzle inner radii, for the Perry Nuclear Power Plant, Unit No. 1 (Perry), the Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review:
=
Background===
The technical bases supporting your request for relief from the ASME Code,Section XI examination requirements regarding RPV nozzle-to-vessel welds and nozzle inner radii and use of an alternative based on ASME Code Case N-702, AAlternative Requirements for Boiling-Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,@ for Perry are documented in BWR Vessel and Internals Project (BWRVIP) Report BWRVIP-108, Technical Basis for the Reduction of Inspection Requirements for the Boiling-Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii. The safety evaluation (SE) on BWRVIP-108 dated December 19, 2007, listed conditions for an applicant to demonstrate the plant-specific applicability of BWRVIP-108 to its plant. Your submittal indicated that all conditions specified in the SE are satisfied. One of the conditions is that the RPV heatup/cooldown rate is less than 115º F. However, the information from the NRC resident inspector at Perry indicated that, recently, Perry had more than two events with the heatup/cooldown rate exceeding 115º F.
Request for Additional Information Please discuss heatup/cooldown rate versus time information for these events and their frequency (how often does it occur). The staff plans to use this information to adjust the probabilistic fracture mechanics results reported in BWRVIP-108 to assess its impact.