ML022460176
| ML022460176 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/23/2002 |
| From: | Boska J NRC/NRR/DLPM/LPD1 |
| To: | Skolds J Exelon Generation Co, Exelon Nuclear |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MB5351 | |
| Download: ML022460176 (10) | |
Text
September 23, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: REVISION TO TECHNICAL SPECIFICATIONS SAFETY LIMIT MINIMUM CRITICAL POWER RATIO FOR CYCLE 15 OPERATION (TAC NO. MB5351)
Dear Mr. Skolds:
The Commission has issued the enclosed Amendment No. 246 to Facility Operating License No. DPR-44 for the Peach Bottom Atomic Power Station, Unit No. 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated June 10, 2002, as supplemented by letter dated August 2, 2002.
This amendment revises the TSs for the safety limit for the minimum critical power ratio from its current value of 1.09 to 1.07 for two recirculation-loop operation, and from 1.10 to 1.09 for single recirculation-loop operation.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions Biweekly Federal Register Notice.
Sincerely,
/RA/
John P. Boska, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-277
Enclosures:
- 1. Amendment No. 246 to License No. DPR-44
- 2. Safety Evaluation cc w/encls: See next page
Peach Bottom Atomic Power Station, Units 2 and 3 cc:
Vice President, General Counsel and Secretary Exelon Generation Company, LLC 300 Exelon Way Kennett Square, PA 19348 Site Vice President Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Plant Manager Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Regulatory Assurance Manager Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Resident Inspector U.S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station P.O. Box 399 Delta, PA 17314 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Roland Fletcher Department of Environment Radiological Health Program 2400 Broening Highway Baltimore, MD 21224 Correspondence Control Desk Exelon Generation Company, LLC 200 Exelon Way, KSA 1-N-1 Kennett Square, PA 19348 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 Board of Supervisors Peach Bottom Township 545 Broad Street Ext.
Delta, PA 17314-9203 Mr. Richard McLean Power Plant and Environmental Review Division Department of Natural Resources B-3, Tawes State Office Building Annapolis, MD 21401 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Manager-Financial Control & Co-Owner Affairs Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, NJ 08038-0236 Manager Licensing-Limerick and Peach Bottom Exelon Generation Company, LLC Nuclear Group Headquarters Correspondence Control P.O. Box 160 Kennett Square, PA 19348
Peach Bottom Atomic Power Station, Units 2 and 3 cc:
Director - Licensing Mid-Atlantic Regional Operating Group Exelon Generation Company, LLC Nuclear Group Headquarters Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Vice President-Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President Mid-Atlantic Regional Operating Group Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Senior Vice President, Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President, Mid-Atlantic Operations Support Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Manager License Renewal Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
September 23, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: REVISION TO TECHNICAL SPECIFICATIONS SAFETY LIMIT MINIMUM CRITICAL POWER RATIO FOR CYCLE 15 OPERATION (TAC NO. MB5351)
Dear Mr. Skolds:
The Commission has issued the enclosed Amendment No. 246 to Facility Operating License No. DPR-44 for the Peach Bottom Atomic Power Station, Unit No. 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated June 10, 2002, as supplemented by letter dated August 2, 2002.
This amendment revises the TSs for the safety limit for the minimum critical power ratio from its current value of 1.09 to 1.07 for two recirculation-loop operation, and from 1.10 to 1.09 for single recirculation-loop operation.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions Biweekly Federal Register Notice.
Sincerely,
/RA/
John P. Boska, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-277
Enclosures:
- 1. Amendment No. 246 to License No. DPR-44
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PDI-2 R/F SRichards JAndersen JBoska MOBrien RCaruso THuang SWall RDennig GHill (2)
BPlatchek, RI ACRS OGC ACCESSION NO. ML022460176
- SE provided, no major changes were made.
- See previous concurrence OFFICE PD1-2/PM PD1-2/PM PD1-2/LA SRXB/BC*
OGC**
PDI-2/(A)SC NAME SWall JBoska SLittle for MOBrien RCaruso RWeisman JAndersen DATE 9/20/2002 9/20/2002 9/23/2002 9/11/02 9/19/02 9/23/2002 Official Record Copy
EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 246 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company), and PSEG Nuclear LLC (the licensees), dated June 10, 2002, as supplemented by letter dated August 2, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 246, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented prior to startup for Cycle 15 operations, scheduled for September 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
James W. Andersen, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 246 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 2.0-1 2.0-1
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 246 TO FACILITY OPERATING LICENSE NO. DPR-44 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 DOCKET NO. 50-277
1.0 INTRODUCTION
By letter dated June 10, 2002 (Reference 1), as supplemented by letter dated August 2, 2002 (Reference 2), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request for changes to the Peach Bottom Atomic Power Station (PBAPS), Unit 2, Technical Specifications (TSs) for Cycle 15 operation. The requested change would incorporate revised safety limit minimum critical power ratios (SLMCPRs) in TS 2.1.1.2. The PBAPS Unit 2 Cycle 15 core has 764 fuel assemblies, of which there are 284 fresh GE14 fuel bundles, 292 once-burned GE14 fuel bundles, and 188 twice-burned GE13 fuel bundles. The August 2, 2002, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination or expand the application beyond the scope of the original Federal Register notice.
2.0 EVALUATION The licensee requested a change to the PBAPS Unit 2 TSs for Cycle 15 in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90. Specifically, the licensee proposed to change the SLMCPR values in TS 2.1.1.2 from 1.09 to 1.07 for two recirculation-loop operation and from 1.10 to 1.09 for single recirculation-loop operation with the reactor vessel steam dome pressure 785 psig and core flow 10 percent of rated core flow.
The licensee described the methodology used to calculate the SLMCPR values for the TS changes in the submittal. The Cycle 15 SLMCPR analysis was performed by Global Nuclear Fuel (GNF-A) using the plant-and cycle-specific fuel and core parameters, and U.S. Nuclear Regulatory Commission (NRC)-approved methodologies (References 3, 4, and 5).
The NRC staff has reviewed: (1) an issue relating to the staffs March 2001 audit of GNF-A databases for GEXL14 correlation, (2) the applicability of the previously-approved methodologies to GE14 fuel, and (3) the justification for changing the SLMCPR from 1.09 to 1.07 for two recirculation-loop operation and from 1.10 to 1.09 for single recirculation-loop operation using the approach stated in Amendment 25 to NEDE-24011-P-A.
The NRC staff identified discrepancies in GNF-A databases while conducting an audit of GNF-As GEXL correlation development for the Duane Arnold Energy Center plant-specific power uprate application in March 2001 (Reference 6). The licensee addressed the issue and provided the results of additional analyses that indicated there is sufficient conservatism for the PBAPS Unit 2 Cycle 15 SLMCPR values to accommodate the penalty due to expected top-peaked power shape during PBAPS Unit 2 Cycle 15 operation. The NRC staff reviewed the licensees evaluation and found it to be acceptable since NRC-approved methodologies were used.
To address the applicability of the previously approved methodologies to GE14 fuel, GNF-A submitted two letters for the staffs review: (1) FLN-2001-016, from Glen A. Watford, General Electric (GE), to NRC, Confirmation of 10x10 Fuel Design Applicability to Improved SLMCPR, Power Distribution and R-Factor Methodologies, dated September 24, 2001, and (2) FLN-2001-017, from Glen A. Watford, GE, to NRC, Confirmation of Applicability of GEXL14 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Core Containing GE14 Fuel, dated October 1, 2001. The NRC staff has reviewed GNF-As evaluation contained in the two letters and has found the approach, supplemented by the use of a higher interim GEXL14 correlation uncertainty, acceptable for this application because NRC-approved methodologies were used. Further tests in the future have been planned and committed to by GNF-A to revise the uncertainty for the GEXL correlation.
Based on its review of the licensees application (Reference 1), and the supplement (Reference 2), the NRC staff finds that the Cycle 15 SLMCPR analysis for PBAPS Unit 2 is acceptable because it uses appropriate plant-and cycle-specific fuel and core parameters in conjunction with NRC-approved methods. The proposed Cycle 15 SLMCPR values will ensure that 99.9 percent of the fuel rods in the core will not experience boiling transition, which satisfies the requirements of General Design Criterion 10 of Appendix A to 10 CFR Part 50 regarding acceptable fuel design limits. The analysis shows that SLMCPR values for PBAPS Unit 2 Cycle 15 operation have sufficient conservatism to accommodate the penalty due to top-peaked power shape during Cycle 15 operation. In view of the above, the staff also concludes that the justification for analyzing and determining the SLMCPR value of 1.07 for two recirculation-loop operation and 1.09 for single recirculation-loop operation is acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (67 FR 50953). Accordingly, the amendments meet 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 amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
6.0 REFERENCES
1.
Letter from Michael P. Gallagher, Exelon, to NRC, License Amendment Request 02-00304 Safety Limit Minimum Critical Power Ratio (SLMCPR) Change, dated June 10, 2002.
2.
Letter from Michael P. Gallagher, Exelon, to NRC, License Amendment Request 02-00304 Response to Request for Additional Information Concerning Safety Limit Minimum Critical Power Ratio (SLMCPR) Change, dated August 2, 2002.
3.
Letter from Frank Akstulewicz, NRC, to Glen A. Watford, GE, "Acceptance for Referencing of Licensing Topical Reports NEDC-32601P, Methodology and Uncertainties for Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluation; and Amendment 25 to NEDE-24011-P-A on Cycle Specific Safety Limit MCPR," dated March 11, 1999.
4.
Letter from Thomas H. Essig, NRC, to Glen A. Watford, GE, "Acceptance for Referencing of Licensing Topical Report NEDC-32505P, Revision 1, R-Factor Calculation Method for GE11, GE12 and GE13 Fuel," dated January 11, 1999.
5.
NEDO-10958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, dated January 1977.
6.
Letter from Brenda L. Mozafari, NRC, to Gary Van Middlesworth, Nuclear Management Company, LLC, Duane Arnold Energy Center - Request for Additional Information on the Proposed Extended Power Uprate Program, dated June 4, 2001.
Principal Contributors: T. Huang, S. Wall Date: September 23, 2002