ML042320388
| ML042320388 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle  |
| Issue date: | 10/04/2004 |
| From: | Pickett D NRC/NRR/DLPM/LPD3 |
| To: | Crane C Exelon Generation Co |
| Pickett D, NRR/DLPM, 415-1364 | |
| Shared Package | |
| ML042320401 | List: |
| References | |
| TAC MC1291, TAC MC1292, TAC MC1293, TAC MC1294, TAC MC1295, TAC MC1296, TAC MC1912 | |
| Download: ML042320388 (28) | |
Text
October 4, 2004 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS. MC1293 AND MC1294); DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 (TAC NOS.
MC1291 AND MC1292); QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MC1295 AND MC1296) - ISSUANCE OF AMENDMENTS
Dear Mr. Crane:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 167 to Facility Operating License No. NPF-11 and Amendment No. 153 to Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2; Amendment No. 209 to Facility Operating License No. DPR-19 and Amendment No. 201 to Facility Operating License No. DPR-25 for Dresden, Units 2 and 3; and Amendment No. 221 to Facility Operating License No. DPR-29 and Amendment No. 216 to Facility Operating License No.
DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments are in response to your application dated November 3, 2003 (RS-03-209).
The amendments revise Technical Specification (TS) 3.4.1, Recirculation Loops Operating, by adding a limiting condition for operation requirement that the linear heat generation rate (LHGR) limits shall be modified for single recirculation loop operation as specified in the Core Operating Limits Report. The associated TS Bases would also be revised to reflect the new LHGR limit requirement.
C. Crane A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374, 50-237, 50-249, 50-254 and 50-265
Enclosures:
- 1. Amendment No. 167 to NPF-11
- 2. Amendment No. 153 to NPF-18
- 3. Amendment No. 209 to DPR-19
- 4. Amendment No. 201 to DPR-25
- 5. Amendment No. 221 to DPR-29
- 6. Amendment No. 216 to DPR-30
- 7. Safety Evaluation cc w/encls: See next page
C. Crane A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374, 50-237, 50-249, 50-254 and 50-265
Enclosures:
- 1. Amendment No. 167 to NPF-11
- 2. Amendment No. 153 to NPF-18
- 3. Amendment No. 209 to DPR-19
- 4. Amendment No. 201 to DPR-25
- 5. Amendment No. 221 to DPR-29
- 6. Amendment No. 216 to DPR-30
- 7. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PDIII-2 R/F LRossbach DPickett OGC AMendiola GHill (12)
TBoyce MBanerjee ACRS SReynolds, RIII PCoates EKendrick FAkstulewicz ADAMS Accession Number: ML042320401 (Package)
ADAMS Accession Number: ML042320388 (Amendment)
ADAMS Accession Number: ML042820128 (Technical Specifications)
OFFICE PM:LPD3-2 LA:LPD3-2 SC:SRXB OGC SC:LPD3-2 NAME DPickett PCoates FAkstulewicz* CMarco AMendiola DATE 08/23/04 08/20/04 08/03/04 09/29/04 10/01/04 OFFICIAL RECORD COPY
- See FAkstulewicz to DPickett memo dated August 3, 2004
LaSalle County Station Units 1 and 2 cc:
Site Vice President - LaSalle County Station Exelon Generation Company, LLC 2601 North 21st Road Marseilles, IL 61341-9757 LaSalle County Station Plant Manager Exelon Generation Company, LLC 2601 North 21st Road Marseilles, IL 61341-9757 Regulatory Assurance Manager - LaSalle Exelon Generation Company, LLC 2601 North 21st Road Marseilles, IL 61341-9757 U.S. Nuclear Regulatory Commission LaSalle Resident Inspectors Office 2605 North 21st Road Marseilles, IL 61341-9756 Phillip P. Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, IL 60603 Assistant Attorney General 100 W. Randolph St. Suite 12 Chicago, IL 60601 Chairman LaSalle County Board 707 Etna Road Ottawa, IL 61350 Attorney General 500 S. Second Street Springfield, IL 62701 Chairman Illinois Commerce Commission 527 E. Capitol Avenue, Leland Building Springfield, IL 62706 Robert Cushing, Chief, Public Utilities Division Illinois Attorney Generals Office 100 W. Randolph Street Chicago, IL 60601 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President - Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President of Operations - Mid-West Boiling Water Reactors Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
LaSalle County Station Units 1 and 2 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Dresden, Quad Cities and Clinton Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
Dresden Nuclear Power Units 2 and 3 cc:
Site Vice President Dresden Nuclear Power Station Exelon Generation Company, LLC 6500 N. Dresden Road Morris, IL 60450-9765 Dresden Nuclear Power Station Plant Manager Exelon Generation Company, LLC 6500 N. Dresden Road Morris, IL 60450-9765 Regulatory Assurance Manager - Dresden Exelon Generation Company, LLC 6500 N. Dresden Road Morris, IL 60450-9765 U.S. Nuclear Regulatory Commission Dresden Resident Inspectors Office 6500 N. Dresden Road Morris, IL 60450-9766 Chairman Grundy County Board Administration Building 1320 Union Street Morris, IL 60450
Quad Cities Nuclear Power Station Units 1 and 2 cc:
Site Vice President - Quad Cities Nuclear Power Station Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Nuclear Power Station Plant Manager Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Regulatory Assurance Manager - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Resident Inspectors Office U.S. Nuclear Regulatory Commission 22712 206th Avenue N.
Cordova, IL 61242 David C. Tubbs MidAmerican Energy Company One River Center Place 106 E. Second, P.O. Box 4350 Davenport, IA 52808-4350 Vice President - Law and Regulatory Affairs MidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, IL 61201
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. NPF-11 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Exelon Generation Company, LLC (the licensee), dated November 3, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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 set forth in 10 CFR Chapter I; 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 167, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Exelon Generation Company, LLC (the licensee), dated November 3, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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 set forth in 10 CFR Chapter I; 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 153, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
ATTACHMENT TO LICENSE AMENDMENT NOS. 167 AND 153 FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 DOCKET NOS. 50-373 AND 50-374 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contain marginal lines indicating the area of change.
Remove Page Insert Page 3.4.1-1 3.4.1-1
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Exelon Generation Company, LLC (the licensee) dated November 3, 2003, 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-19 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 209, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Exelon Generation Company, LLC (the licensee) dated November 3, 2003, 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 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 201, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
ATTACHMENT TO LICENSE AMENDMENT NOS. 209 AND 201 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by amendment number and contain marginal lines indicating the area of change.
Remove Page Insert Page 3.4.1-1 3.4.1-1
EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated November 3, 2003, 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 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 221, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated November 3, 2003, 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 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 216, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
ATTACHMENT TO LICENSE AMENDMENT NOS. 221 AND 216 FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by number and contain marginal lines indicating the area of change.
Remove Page Insert Page 3.4.1-1 3.4.1-1
ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 167 TO FACILITY OPERATING LICENSE NO. NPF-11 AMENDMENT NO. 153 TO FACILITY OPERATING LICENSE NO. NPF-18; AMENDMENT NO. 209 TO FACILITY OPERATING LICENSE NO. DPR-19 AMENDMENT NO. 201 TO FACILITY OPERATING LICENSE NO. DPR-25; AMENDMENT NO. 221 TO FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 216 TO FACILITY OPERATING LICENSE NO. DPR-30 EXELON GENERATION COMPANY, LLC MIDAMERICAN ENERGY COMPANY LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-237 AND 50-249 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265
1.0 INTRODUCTION
By letter dated November 3, 2003 (Ref. 1), Exelon Generation Company, LLC (EGC), the licensee for LaSalle County Station (LSCS) Units 1 and 2, Dresden Nuclear Power Station (DNPS) Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS) Units 1 and 2 plants, submitted a license amendment request (LAR). The proposed changes would revise Technical Specification (TS) 3.4.1, Recirculation Loops Operating, for each facility by adding a limiting condition for operation (LCO) requirement that the linear heat generation rate (LHGR) limits shall be modified for single recirculation loop operation (SLO) as specified in the Core Operating Limits Report (COLR). The licensee requested approval of the LAR by November 4, 2004.
2.0 BACKGROUND
TS 3.4.1 for LSCS, DNPS, and QCNPS currently have LCO requirements that the average planar linear heat generation rate (APLHGR) limit and the minimum critical power ratio (MCPR) limit shall be modified during SLO conditions as specified in the COLR. The proposed TS change adds the LCO requirement to also modify the LHGR limit, as specified in the COLR, for SLO. Currently, with no TS requirement, administrative controls are used to ensure that the LHGR limits are appropriately adjusted. The LHGR limit provides thermal-mechanical protection against fuel cladding damage and failure for normal operation and anticipated operational occurrences (AOOs). The APLHGR limit provides Emergency Core Cooling System (ECCS) protection for LOCA events. The MCPR limit provides protection against fuel damage from cladding overheating.
The proposed TS change will allow the facilities to use the latest NRC approved nuclear modeling methods from the General Electric licensing topical report NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II, Ref. 2) for determining the core operating thermal limits to ensure that the fuel design limits are not exceeded during normal operation, including AOOs.
LHGR limits are included in the TS for most boiling water reactor (BWR) plants. However, in 1987, the staff approved Amendment 19 to GESTAR-II that allowed the option for the LHGR to be monitored as part of the APLHGR TS. Under this option, monitoring and adhering to the APLHGR limits also ensures compliance to the LHGR limit. As a result, some licensees, including the Hatch plant, removed the LHGR from the TS.
In 1999, the staff approved Amendment 26 to GESTAR II which describes improved nuclear design and monitoring methods using the PANAC11 nuclear model. These improved methods increase the accuracy in core monitoring analyses such that separate monitoring of LHGR and APLHGR limits may provide more design and operating flexibility. Licensees who adopted the Amendment 19 composite maximum average planar linear heat-generation rate (MAPLHGR) limit approach, or who have used another fuel vendors thermal-mechanical and LOCA criteria to monitor limits and are now choosing to use the Amendment 26 PANAC11 model to monitor LHGR and APLHGR limits separately, must reexamine their TS for potential changes to reestablish separate LHGR monitoring.
The staff notes that licensees have not consistently addressed the separation of the LHGR and APLHGR limits resulting in differing implementations of GESTAR-II Amendment 19. The Hatch plant, for example, adopted the optional use of composite ECCS and thermal-mechanical APLHGR limits and removed references to the LHGR limits from its TS.
The staff review of a recent Hatch TS change request (Ref. 3) represents a precedent for this review in that it presents the approach to reincorporate the LHGR limit into the TS LCO.
GESTAR II Amendment 27 (Ref. 4) contains administrative changes to clarify the two options identified in Amendment 19. Using this approach, the thermal-mechanical (T-M) considerations may be monitored either by a composite MAPLHGR limit which includes the effects of both the ECCS-LOCA and T-M limits or by separate MAPLHGR and LHGR limits where the MAPLHGR limits are used to impose ECCS-LOCA limits and the LHGR limits are used to impose the T-M constraints. It was also stated in the Amendment 27 submittal that with the implementation of the Amendment 26 PANAC11 nuclear model, it is planned that the composite MAPLHGR limit will not be used and that instead the MAPLHGR and the LHGR will be monitored separately.
The licensee is using the PANAC11 model for core licensing calculations and has identified a TS change to add an LCO requirement that modifies the LHGR limit for SLO. To accomplish this, the licensee will add an LCO statement to address plant monitoring and limitation requirements for LHGR under SLO conditions. This LCO currently has the Required Action statements and Completion Time, as well as the Surveillance Requirements for APLHGR and MCPR monitoring. Currently, with no TS requirement, administrative controls are used to ensure that the LHGR limits are appropriately adjusted.
3.0 REGULATORY EVALUATION
The Commissions regulatory requirements related to the content of TS are set forth in Section 50.36, Technical Specifications" of Title 10 of the Code of Federal Regulations (10 CFR). This regulation requires that the TS include items in five specific categories. These categories include: 1) safety limits, limiting safety system settings, and limiting control settings, 2) limiting conditions for operation, 3) surveillance requirements, 4) design features, and 5) administrative controls.
Additionally, Criterion 2 of 10 CFR 50.36(c)(2)(ii) requires a limiting condition for operation to be established for a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. Since the LHGR satisfies Criterion 2, the LCO should be included in the TS.
10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, establishes the acceptance criteria for the design basis LOCA.
Specifically, paragraph (b)(1) requires the calculated maximum fuel element peak cladding temperature (PCT) to not exceed 2200 F.
NUREG-0800, Standard Review Plan, Section 4.2 Fuel System Design, defines the basis for the acceptance criteria for staff reviews. These criteria include three parts: (1) design bases that describe specified acceptable fuel design limits (SAFDLs), (2) design evaluation that demonstrates that the design bases are met, and (3) testing, inspection, and surveillance plans that show that there is adequate monitoring and surveillance of irradiated fuel. The design bases include: (1) fuel system damage, (2) fuel rod failure, and (3) fuel coolability. The LHGR and APLHGR limits are part of the SAFDLs.
4.0 TECHNICAL EVALUATION
Standard Review Plan, Section 4.2 provides the guidance for safety evaluation reviews of the fuel system design. The fuel system consists of arrays of fuel rods including fuel pellets and tubular cladding, spacer grids, end plates, and reactivity control rods. The objectives of the fuel system safety review provide assurance that: (1) the fuel system is not damaged as a result of normal operation and AOOs, (2) fuel system damage is never so severe as to prevent control rod insertion when it is required, (3) the number of fuel rod failures is not underestimated for postulated accidents, and (4) coolability is always maintained. As indicated above, the LHGR provides protection against fuel cladding damage and failure for normal operation and AOOs while the APLHGR provides protection for LOCA events.
4.1 Linear Heat Generation Rate (LHGR)
The LHGR is defined as the power generated in a fixed length of a fuel rod. The plant monitoring system continuously monitors LHGR on a six-inch-segment basis for each fuel rod in units of kilowatts per foot (kW/ft). The LHGR is monitored and compared to the limit to ensure that fuel thermal-mechanical design limits (e.g., 1% strain, fuel melting), which prevent fuel cladding failure, are not exceeded during normal operation and AOOs.
With the approval of Amendment 26 to GESTAR II, licensees planning to use the improved models may need to add (or restore) a new LCO related to the LHGR limit included in the power distribution section of the TS. This LCO addresses plant monitoring and limitation requirements of the LHGR. The LCO contains required actions, completion times, and surveillance requirements. Similar to the existing APLHGR and the MCPR LCOs, the added LHGR limit is applicable at reactor power levels greater than 24 percent. Consequently, inability to meet the LHGR limit within the specified completion time will require that reactor power be reduced to below 24 percent. The surveillance requirements include the frequency of surveillance.
4.2 Technical Specifications Affected The TS potentially affected by separate monitoring of the LHGR include: (1) LHGR definition, (2) LHGR limit, (3) recirculation loops operating, (4) core operating limits report (COLR), and (5)
TS Bases.
4.2.1 TS Section 1.1 Definitions, Linear Heat Generation Rate Since the current TS definition is consistent with the LHGR definition in Section 3.1, the staff concludes that the existing definition is acceptable and therefore does not require any changes as a result of this amendment.
4.2.2 TS Section 3.2.3 Linear Heat Generation Rate (LHGR), LCO 3.2.3 LCO 3.2.3 establishes the required action, completion time, and surveillance requirements for the LHGR limit at a reactor power greater than 24 percent. Failure to meet the LHGR limit within the specified completion time will result in a power reduction to below 24 percent. The staff concludes that the TS LCO 3.2.3 is acceptable and therefore does not require any changes as a result of this amendment.
4.2.3 TS Section 3.4.1 Recirculation Loops Operating, LCO 3.4.1 LCO 3.4.1 addresses reactor operation with one or two recirculation loops. Reactor operation with one recirculation loop is generally more limiting than with two recirculation loops. Currently, the LCO addresses the APLHGR limit, MCPR limit, and reactor protection system instrumentation and control rod block instrumentation requirements. The licensee proposes to add a line item LHGR limit to LCO 3.4.1. The proposed line item states that the LHGR limit will be modified when the reactor is operating with a SLO using the limit value contained in the COLR. Based on the similar approach for the other thermal limits (MCPR and MAPLHGR), the staff concludes that the proposed line item inclusion of an SLO LHGR limit in LCO 3.4.1 is acceptable.
4.2.4 TS Section 5.6.5 Core Operating Limits Report (COLR)
Core operating limits shall be established prior to each reload cycle and will be documented in the COLR. The proposed LCO 3.2.3 states that the SLO LHGR shall be less than or equal to the limits specified in the COLR. The licensee will add the SLO LHGR limit value to the Section 5.6.5 COLR requirements. Since it is consistent with the other COLR requirements, the staff concludes that the proposed LCO LHGR limit value in Section 5.6.5 COLR is acceptable.
4.2.5 TS Bases The licensee stated that the LHGR Bases 3.2.3 and 3.4.1 sections are to be revised to include references to the LHGR limit. The staff examined these Bases revisions and notes that the revisions appropriately support the TS changes.
4.3 Summary The NRC staff has reviewed the licensee amendment request for proposed revisions to the TS for the subject facilities. The staff reviewed the licensee submittal in accordance with the guidance and limitations of 10 CFR 50.36, 10 CFR 50.46, and the applicable sections of NUREG-0800. Based on the staff evaluation as set forth above, the staff concludes that the proposed TS revisions are acceptable.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
This amendment changes 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 amendment involves 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 amendment involves no significant hazards consideration and there has been no public comment on such finding (69 FR 694). Accordingly, the amendment meets 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 amendment.
7.0 CONCLUSION
The staff 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
8.0 REFERENCES
1.
Letter from P. R. Simpson (EGC) to U.S. NRC, Request for Amendment to Technical Specifications to Add Requirement to Modify Linear Heat Generation Rate Limit During Single Recirculation Loop Operation, RS-03-209, dated November 3, 2003. [ADAMS Accession #ML033180448]
2.
Letter from S. A. Richards (U.S. NRC) to G. A. Watford (GE Nuclear Energy),
Amendment 26 to GE Licensing Topical Report NEDE-24011-P-A, GESTAR II, Implementing Improved GE Steady-State Methods (TAC No. MA6481), dated November 10, 1999. [ADAMS Accession #ML993230184]
3.
Letter from C. Gratton (NRC) to H. L. Sumner, Jr. (Hatch), Edwin I. Hatch Nuclear Plant, Units 1 and 2 re: Issuance of Amendments (TAC Nos. MC0975 and MC0976), dated March 8, 2004. [ADAMS Accession # ML040680971]
4.
Letter from H. N. Berkow (NRC) to M. Harding (GNF), Final Safety Evaluation for Global Nuclear (GNF) Licensing Topical Report NEDE-24011P, GESTAR II, Amendment 27' (TAC No. MC0347), dated July 16, 2004. [ADAMS Accession # ML042010353]
Principal Contributor: Edward Kendrick, SRXB, NRR Date: October 4, 2004