ML071720314
| ML071720314 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/29/2007 |
| From: | John Hughey NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Crane C AmerGen Energy Co |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| Shared Package | |
| ml071720305 | List: |
| References | |
| TAC MD2310, TAC MD2311 | |
| Download: ML071720314 (13) | |
Text
June 29, 2007 Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENT RE: DELETION OF REFERENCE TO BANKED POSITION WITHDRAWAL SEQUENCE IN THE TECHNICAL SPECIFICATIONS (TAC NOS. MD2310 AND MD2311)
Dear Mr. Crane:
The Commission has issued the enclosed Amendments Nos. 260 and 264 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 8, 2006, as supplemented by letter dated February 5, 2007.
These amendments modify several TSs by removing reference to the Banked Position Withdrawal Sequence and replace it with the analyzed rod position sequence.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.
Sincerely,
/ra/
John Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
Enclosures:
- 1. Amendment No. 260 to Renewed DPR-44
- 2. Amendment No. 264 to Renewed DPR-56
- 3. Safety Evaluation cc w/encls: See next page
June 29, 2007 Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENT RE: DELETION OF REFERENCE TO BANKED POSITION WITHDRAWAL SEQUENCE IN THE TECHNICAL SPECIFICATIONS (TAC NOS. MD2310 AND MD2311)
Dear Mr. Crane:
The Commission has issued the enclosed Amendments Nos. 260 and 264 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 8, 2006, as supplemented by letter dated February 5, 2007.
These amendments modify several TSs by removing reference to the Banked Position Withdrawal Sequence and replace it with the analyzed rod position sequence.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.
Sincerely,
/ra/
John Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
Enclosures:
- 1. Amendment No. 260 to Renewed DPR-44
- 2. Amendment No. 264 to Renewed DPR-56
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC LPL1-2 R/F RidsNrrDorlLpl1-2 RidsNrrPMJHughey RidsNrrLAEWhitt RidsOgcRp GHill, OIS (4) RidsNrrDorlDpr RidsNrrDirsItsb RidsRgn1MailCenter RidsAcrsAcnwMailCenter JBudzynski Accession Numbers: Letter: ML071720314 TS Pages: Amd#260-ML071860178; Amd#264-ML071860173 Package: ML071720305
- Concurrence via letter, no significant changes OFFICE LPL1-2/PM LPL3-2/LA ITSB/BC SRXB/BC OGC (NLO) LPL1-2/BC NAME JHughey EWhitt TKobetz GCranston* ACuratola HChernoff DATE 6/28/07 (edits only) 06/27/2007 05/08/2007 06/27/2007 6/29/07 6/28/07 Official Record Copy
Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 cc:
Site Vice President Mr. Richard McLean Peach Bottom Atomic Power Station Power Plant and Environmental Exelon Generation Company, LLC Review Division 1848 Lay Road Department of Natural Resources Delta, PA 17314 B-3, Tawes State Office Building Annapolis, MD 21401 Plant Manager Peach Bottom Atomic Power Station Dr. Judith Johnsrud Exelon Generation Company, LLC National Energy Committee 1848 Lay Road Sierra Club Delta, PA 17314 433 Orlando Avenue State College, PA 16803 Regulatory Assurance Manager Peach Bottom Atomic Power Station Manager-Financial Control & Co-Owner Exelon Generation Company, LLC Affairs 1848 Lay Road Public Service Electric and Gas Company Delta, PA 17314 P.O. Box 236 Hancocks Bridge, NJ 08038-0236 Resident Inspector U.S. Nuclear Regulatory Commission Manager Licensing-Peach Bottom Peach Bottom Atomic Power Station Atomic Power Station P.O. Box 399 Exelon Generation Company, LLC Delta, PA 17314 200 Exelon Way, KSA -3E Kennett Square, PA 19348 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Vice President - Licensing and Regulatory 475 Allendale Road Affairs King of Prussia, PA 19406 Exelon Generation Company, LLC 4300 Winfield Road Mr. Roland Fletcher Warrenville, IL 60555 Department of Environment Radiological Health Program Vice President-Operations Mid-Atlantic 2400 Broening Highway Exelon Generation Company, LLC Baltimore, MD 21224 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Correspondence Control Desk Exelon Generation Company, LLC Associate General Counsel P. O. Box 160 Exelon Generation Company, LLC Kennett Square, PA 19348 4300 Winfield Road Warrenville, IL 60555 Director, Bureau of Radiation Protection Pennsylvania Department of Director-Licensing and Regulatory Affairs Environmental Protection Exelon Generation Company, LLC Rachel Carson State Office Building 200 Exelon Way, KSA 3-E P.O. Box 8469 Kennett Square, PA 1934 Harrisburg, PA 17105-8469 Board of Supervisors Peach Bottom Township 545 Broad Street Ext.
Delta, PA 17314-9203
EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 260 Renewed 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 8, 2006 as supplemented by letter dated February 5, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's 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 Renewed 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. 260, 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 within 60 days. Implementation of the amendment shall include updating the UFSAR in accordance with 10CFR50.71(e). This update shall include the effects of all safety analyses and evaluations performed by the licensee in support of the amendment.
Specifically, this update shall state, but not be limited to: a statement that the methodology of GE Topical Reports NEDE-24011-P-A-15 (dated September 2005) and NEDE-24011-P-A-15-US (dated September 2005) shall be used to analyze control rod startup/shutdown sequences and control rod patterns; and a statement that cycle-specific control rod patterns during startup and shut down conditions shall continue to be controlled by the operator and the rod worth minimizer so that only specified control rod sequences and relative positions are allowed over the operating range of all control rods inserted to 10 percent of rated thermal power.
FOR THE NUCLEAR REGULATORY COMMISSION
/ra/
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: June 29, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 260 RENEWED FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert Page 3 Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.1-9 3.1-9 3.1-18 3.1-18 3.1-19 3.1-19 3.3-17 3.3-17 3.3-20 3.3-20 3.10-18 3.10-18 3.10-20 3.10-20
EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 264 Renewed License No. DPR-56
- 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 8, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's 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 Renewed Facility Operating License No. DPR-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 264, 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 within 60 days. Implementation of the amendment shall include updating the UFSAR in accordance with 10CFR50.71(e). This update shall include the effects of all safety analyses and evaluations performed by the licensee in support of the amendment.
Specifically, this update shall state, but not be limited to: a statement that the methodology of GE Topical Reports NEDE-24011-P-A-15 (dated September 2005) and NEDE-24011-P-A-15-US (dated September 2005) shall be used to analyze control rod startup/shutdown sequences and control rod patterns; and a statement that cycle-specific control rod patterns during startup and shut down conditions shall continue to be controlled by the operator and the rod worth minimizer so that only specified control rod sequences and relative positions are allowed over the operating range of all control rods inserted to 10 percent of rated thermal power.
FOR THE NUCLEAR REGULATORY COMMISSION
/ra/
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: June 29, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 264 RENEWED FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert Page 3 Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.1-9 3.1-9 3.1-18 3.1-18 3.1-19 3.1-19 3.3-17 3.3-17 3.3-20 3.3-20 3.10-18 3.10-18 3.10-20 3.10-20
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 260 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-44 AND AMENDMENT NO. 264 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-56 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278
1.0 INTRODUCTION
By application dated June 8, 2006, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061600452), Exelon Generation Company, LLC (the licensee),
requested changes to the Technical Specifications (TSs) for Peach Bottom Atomic Power Station, Units 2 and 3 (PBAPS 2 and 3). Supplemental information was provided by Exelon in a letter dated February 5, 2007 (ADAMS Accession No. ML070380169) in response to a Request for Additional Information. This response provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on August 15, 2006 (71 FR 46934).
Specifically, the proposed amendment would replace the current reference to Banked Position Withdrawal Sequence (BPWS) with a reference to the analyzed rod position sequence in TS 3.1.3, Control Rod Operability TS 3.1.6, Rod Pattern Control, TS 3.3.2.1, Control Rod Block Instrumentation, TS 3.10.7, Control Rod Testing - Operating, and TS 3.10.8, SHUTDOWN MARGIN (SDM) Test - Refueling.
This change is expected to allow greater flexibility in startup/shutdown sequence modifications beyond those allowed by the general requirements of the BPWS. The analyzed rod pattern would be optimized according to the current core conditions. For example, the TS revision would allow cycle specific control rod patterns for cases when it is desirable to maintain a control rod fully inserted. By optimizing the control rod startup and shutdown sequences, plant operations would improve as a result of reducing unnecessary reactivity manipulations and associated operational challenges.
The revised TS wording is consistent with a TS wording approved as part of the Improved Technical Specifications (ITS) conversion for Dresden Nuclear Power Station, Units 2 and 3,
LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2 (ADAMS Accession Nos. ML012280044, ML011130202 and ML011130309, respectively).
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, General Design Criteria (GDC) 28, reactivity limits, states that the reactivity control systems be designed with appropriate limits on the potential amount and rate of reactivity increase to prevent the adverse effects of postulated reactivity accidents. A postulated failure of the control rod drive system such as a rod dropout provides the potential for a relatively high rate of positive reactivity insertion which, if large enough, could cause a prompt power excursion. Such a prompt power excursion could cause a fuel element rupture, rapid fragmentation of the fuel cladding and dispersal of fuel and cladding into the coolant. Below 10 percent of rated thermal power (RTP),
startup and shutdown rod sequences are designed to limit the rate of reactivity change such that the rod drop accident would not produce fuel specific energies greater than 280 cal/gm.
Meeting the requirements of GDC 28 for the control rod drive systems ensures plant safety by limiting the effects of postulated reactivity accidents, thereby mitigating the adverse effects which could result in damage to the reactor coolant pressure boundary or impair the capability to cool the core. Although the PBAPS UFSAR states that Units 2 and 3 conform with the July 1967 AEC proposed General Design Criteria, the current GDC 28 is an appropriate acceptance criterion for the requested TS change.
3.0 TECHNICAL EVALUATION
The design-basis accident for positive reactivity insertion is the Control Rod Drop Accident (CRDA). The BPWS is designed to limit the rate of reactivity change such that the rod drop accident would not produce fuel specific energies greater than 280 cal/gm during both startup and shutdown, whenever the reactor thermal power is below the Low Power Setpoint (LPSP) of 10 percent of RTP.
Current PBAPS TS require that the startup and shutdown control rod sequence must comply with the requirements of the BPWS whenever reactor thermal power is below the LPSP of 10 percent of RTP. These BPWS requirements are identified in the previously approved GE topical report Banked Position Withdrawal Sequence, NEDO-21231, dated January 1977.
These requirements are based upon the design-basis accident that results in a positive reactivity insertion for CRDA. The BPWS is designed to limit the rate of reactivity change to be consistent with the CRDA analysis limit during both startup and shutdown operations. The CRDA analysis assumes that the reactor operator follows prescribed withdrawal sequences.
The licensee states, and shall incorporate into the UFSAR, that under the proposed revision, cycle-specific control rod patterns during startup and shut down conditions will continue to be controlled by the operator and the rod worth minimizer so that only specified control rod sequences and relative positions are allowed over the operating range of all control rods inserted to 10 percent of RTP. These sequences will continue to limit the potential amount of reactivity addition that could occur in the event of a CRDA. Therefore, the requested TS change is consistent with GDC 28.
Using the words the analyzed rod position sequence will provide greater flexibility in cycle-specific control rod patterns for cases when it is desirable to maintain a control rod fully inserted. For example, this would include situations in which suppression of failed fuel rods or
suspected channel bow locations requiring rod insertion do not conform to BPWS requirements.
This TS change will allow other analyses to be performed to develop modified startup/shutdown sequences and control rod patterns. These sequences will be developed to minimize incremental control rod reactivity worth in accordance with the Nuclear Regulatory Commission (NRC) approved GE topical reports: General Electric Standard Application for Reactor Fuel, NEDE- 24011-P-A-15, dated September 2005 (GESTAR-II), and United States (U.S.)
Supplement, NEDE-24011-P-A-15-US, dated September 2005 (ADAMS Accession No. ML060180313). The PBAPS Final Safety Analysis Report Sections 3.1, 4.6, and 3.13 were also reviewed to ensure that the plants reactivity control system design bases and regulatory commitments will continue to be satisfied when the proposed change is made.
This change will result in reducing unnecessary reactivity manipulations and associated operational challenges. Furthermore, this change will allow failed fuel to remain suppressed during plant startup/shutdown preventing further potential fuel damage and allows control rods to remain inserted in fuel cells with identified channel deformation. In addition, the change will allow optimization of cycle-specific control rod startup and shutdown sequences that conform to the GESTAR-II requirements. Also, the licensee states that these cycle-specific control rod patterns during startup and shut down conditions will continue to be controlled by the operator and the rod worth minimizer so that only specified control rod sequences and relative positions are allowed over the operating range of all control rods inserted to 10 percent of RTP.
These changes are expected to be of benefit in the conduct of control rod sequence manipulations during startup/shutdown conditions by reducing unnecessary reactivity manipulations and associated operational challenges by allowing failed fuel to remain suppressed, preventing further potential fuel damage and allowing control rods to remain inserted in fuel cells with identified channel deformation.
The TS revision was reviewed and approved as part of the ITS conversion for Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2. The licensee states that the analyzed rod position sequence patterns are more flexible and advantageous to plant startup/shutdown operations than the BPWS. Since the NRC staff believes that the additional flexibility afforded by utilizing the analyzed rod position sequence patterns would improve the margin of safety during plant startup/shutdown by avoiding unnecessary rod manipulations and because the same NRC-approved methodology used to develop the BPWS control rod pattern will be employed to develop the analyzed rod position sequences, the licensees amendment request is acceptable.
This license amendment request contained the licensees planned markups of the TS Bases associated with this change. The TS Bases are not part of the TSs as defined by Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36. The NRC staff did not perform an evaluation of these TS Bases changes and staff concurrence with the TS Bases changes is not implied by this evaluation. The NRC staff may review the evaluations that support TS Bases changes during its inspection activities.
4.0 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 provided no comments.
5.0 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 (71 FR 46934). 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.
6.0 CONCLUSION
The staff has reviewed the licensees proposal to amend existing TS 3.1.3, Control Rod Operability TS 3.1.6, Rod Pattern Control, TS 3.3.2.1, Control Rod Block Instrumentation, TS 3.10.7, Control Rod Testing - Operating, and TS 3.10.8, SHUTDOWN MARGIN (SDM)
Test - Refueling by replacing BPWS with reference to the analyzed rod position sequence.
The staff concludes that the amendment request is acceptable.
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 Commission's 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.
Principal Contributor: J. Budzynski Date: June 29, 2007