ML052140156
| ML052140156 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/04/2005 |
| From: | Colburn T NRC/NRR/DLPM/LPD1 |
| To: | Pearce L FirstEnergy Nuclear Operating Co |
| Colburn T, NRR/DLPM, 415-1402 | |
| References | |
| TAC MC5862 | |
| Download: ML052140156 (7) | |
Text
August 4, 2005 Mr. L. William Pearce Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 (BVPS-1) - REVIEW OF THE CYCLE 17 VOLTAGE-BASED REPAIR CRITERIA 90-DAY REPORT (TAC NO. MC5862)
Dear Mr. Pearce:
By letter dated January 26, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML050320212), FirstEnergy Nuclear Operating Company (FENOC) submitted the 90-day steam generator (SG) alternate repair criteria report in accordance with BVPS-1 Technical Specification (TS) 4.4.5.5.e. The report focused on implementation of the voltage-based alternate repair criteria and the results of the W* methodology inspections (i.e.,
inspections in the tubesheet region). To support its review of this report, the Nuclear Regulatory Commission (NRC) staff considered the pertinent information related to these topics contained in the SG C-3 report submitted in accordance with BVPS-1 TS 4.4.5.5.c on November 5, 2004 (ADAMS Accession No. ML043200116), and the 15-day SG plugging report submitted in accordance with BVPS-1 TS 4.4.5.5.a on November 12, 2004 (ADAMS Accession No. ML043270491). The NRC staff did not review the statistical analysis in Appendix A of the January 26, 2005, report regarding the probability of detecting indications in the lower portion of the tubesheet since the licensee was not proposing this as a new methodology for determining the number of flaws in this region.
The NRC staff has completed its review of these reports and concludes that the licensee provided the information required by the BVPS-1 TSs and that no additional follow-up is required at this time. The NRC staffs review is enclosed Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
NRC Staffs Review cc w/encl: See next page
ML043200116), and the 15-day SG plugging report submitted in accordance with BVPS-1 TS 4.4.5.5.a on November 12, 2004 (ADAMS Accession No. ML043270491). The NRC staff did not review the statistical analysis in Appendix A of the January 26, 2005, report regarding the probability of detecting indications in the lower portion of the tubesheet since the licensee was not proposing this as a new methodology for determining the number of flaws in this region.
The NRC staff has completed its review of these reports and concludes that the licensee provided the information required by the BVPS-1 TSs and that no additional follow-up is required at this time. The NRC staffs review is enclosed Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
NRC Staffs Review cc w/encl: See next page DISTRIBUTION:
PUBLIC RBellamy, RI TColburn ACRS LLund MMurphy PDI-1 Reading RLaufer OGC MOBrien DLPM/DPR LMiller ACCESSION NUMBER: ML052140156
- Input received. No substantive changes made.
OFFICE PDI-1/PM PDI-2/LA EMCB/SC PDI-1/SC NAME TColburn MOBrien LLund*
RLaufer DATE 8/04/05 08/04/05 07/01/05 08/04/05
Enclosure NUCLEAR REGULATORY COMMISSION (NRC) STAFFS REVIEW OF THE 90-DAY STEAM GENERATOR (SG) TUBE INSERVICE INSPECTION REPORT FOR THE BEAVER VALLEY POWER STATION, UNIT NO. 1 (BVPS-1)
END-OF-CYCLE 17 REFUELING OUTAGE DOCKET NO. 50-334 By letter dated January 26, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML050320212), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted the 90-day SG alternate repair criteria report in accordance with BVPS-1 Technical Specification (TS) 4.4.5.5.e. The report focused on implementation of the voltage-based alternate repair criteria and the results of the W* methodology inspections (i.e.,
inspections in the tubesheet region). To support its review of this report, the NRC staff considered the pertinent information related to these topics contained in the FENOC SG C-3 report submitted in accordance with BVPS-1 TS 4.4.5.5.c on November 5, 2004 (ADAMS Accession No. ML043200116), and the 15-day FENOC SG plugging report submitted in accordance with TS Section 4.4.5.5.a on November 12, 2004 (ADAMS Accession No. ML043270491). The NRC staff did not review the statistical analysis in Appendix A of the January 26, 2005, report regarding the probability of detecting indications in the lower portion of the tubesheet since the licensee was not proposing this as a new methodology for determining the number of flaws in this region.
BVPS-1 has three Westinghouse Model 51 SGs which are designated SG A, SG B, and SG C.
All three SGs were inspected during the fall 2004 Cycle 16 refueling outage. Each of the BVPS-1 Westinghouse Model 51 SGs has 3388 mill-annealed Alloy 600 tubes which have an outside diameter of 7/8 inch and a wall thickness of 0.050 inch. The tubes have been explosively expanded full length into the tubesheet and are supported by several carbon steel tube support plates which contain drilled holes through which the tubes pass.
In the January 26, 2005, report, the licensee provided the scope, extent, methods, and results of BVPS-1 SG tube inspections performed in accordance with the voltage-based tube repair criteria and implementation of the W* criteria. In addition, the licensee described corrective actions (i.e., tube plugging or repair) taken in response to the inspection findings.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their TSs. Consistent with the NRC staffs evaluation of the end-of-cycle 15 refueling outage results submitted by letter dated July 14, 2004 (ADAMS Accession No. ML041830118), the NRC staff concludes that there are no technical issues regarding the voltage-based repair criteria that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. In addition, the staff concludes that there are no technical issues requiring follow-up from implementation of the W* criteria.
Principal Contributor: L. Miller Date: August 4, 2005 Beaver Valley Power Station, Unit Nos. 1 and 2
cc:
Mary OReilly, Attorney FirstEnergy Nuclear Operating Company FirstEnergy Corporation 76 South Main Street Akron, OH 44308 FirstEnergy Nuclear Operating Company Regulatory Affairs/Performance Improvement Larry R. Freeland, Manager Beaver Valley Power Station Post Office Box 4, BV-A Shippingport, PA 15077 Commissioner James R. Lewis West Virginia Division of Labor 749-B, Building No. 6 Capitol Complex Charleston, WV 25305 Director, Utilities Department Public Utilities Commission 180 East Broad Street Columbus, OH 43266-0573 Director, Pennsylvania Emergency Management Agency 2605 Interstate Dr.
Harrisburg, PA 17110-9364 Ohio EPA-DERR ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 J. H. Lash, Plant Manager (BV-IPAB)
FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077 Rich Janati, Chief Division of Nuclear Safety Bureau of Radiation Protection Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P O Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 298 Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Beaver Valley Power Station ATTN: R. G. Mende, Director Work Management (BV-IPAB)
Post Office Box 4 Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mr. B. F. Sepelak Post Office Box 4, BV-A Shippingport, PA 15077