ML23158A195
| ML23158A195 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Peach Bottom, Ginna  |
| Issue date: | 08/30/2023 |
| From: | Scott Wall NRC/NRR/DORL/LPL3 |
| To: | Rhoades D Constellation Energy Generation |
| Goetz, S | |
| References | |
| EPID L-2022-LLA-0151 | |
| Download: ML23158A195 (32) | |
Text
August 30, 2023 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2, AMENDMENT NOS. 348 AND 326; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, AMENDMENT NOS. 343 AND 346; AND R. E. GINNA NUCLEAR POWER PLANT, AMENDMENT NO. 156 - ISSUANCE OF AMENDMENTS TO ADOPT TSTF-273-A, REVISION 2, SAFETY FUNCTION DETERMINATION PROGRAM CLARIFICATIONS (EPID L-2022-LLA-0151)
Dear Mr. Rhoades:
The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued the enclosed amendments (listed below) in response to the Constellation Energy Generation, LLC application dated October 25, 2022 (Agencywide Documents Access and Management System Accession No. ML22298A010).
Enclosed amendments:
- 1.
Amendment No. 348 to Renewed Facility Operating License No. DPR-53 and Amendment No. 326 to Renewed Facility Operating License No. DPR-69 for Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2, respectively;
- 2.
Amendment No. 343 to Subsequent Renewed Facility Operating License No. DPR-44 and Amendment No. 346 to Subsequent Renewed Facility Operating License No. DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, respectively; and
- 3.
Amendment No. 156 to Renewed Facility Operating License No. DPR-18 for R. E. Ginna Nuclear Power Plant (Ginna).
The amendments revise the technical specifications for each facility based on Technical Specification Task Force (TSTF) traveler TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications (ML040611069) to add explanatory text to the programmatic description of the safety function determination program in TS 5.5.15 (CCNPP),
TS 5.5.11 (PBAPS) and TS 5.5.14 (Ginna) to provide clarification that when determining loss of function, a loss of power does not need to be considered.
The NRC staff also notes that by letter dated December 14, 2021 (ML21299A005), the NRC issued Amendment Nos. 340 and 318 for CCNPP Units 1 and 2, respectively. During the issuances of these amendments two typographical errors on TS page 5.5-16 were introduced.
On July 13, 2023 (ML23186A037), the NRC staff issued a correction letter to correct these typographical errors but provided the incorrect copy of TS page 5.5-16 as the enclosure. The version of TS page 5.5-16 that is being issued with Amendment Nos. 348 and 326 for CCNPP Units 1 and 2, respectively, both incorporates TSTF-273-A, and reflects the previously corrected typographical errors discussed in the July 13, 2023, correction letter. We apologize for any inconvenience this may have caused.
A copy of the NRC staffs Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317, 50-318, 50-277, 50-278, and 50-244
Enclosures:
- 1. Amendment No. 348 to DPR-53
- 2. Amendment No. 326 to DPR-69
- 3. Amendment No. 343 to DPR-44
- 4. Amendment No. 346 to DPR-56
- 5. Amendment No. 156 to DPR-18
- 6. Safety Evaluation cc: Listserv
CALVERT CLIFFS NUCLEAR POWER PLANT, LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 348 License No. DPR-53
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated October 25, 2022, 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 Renewed Facility Operating License No. DPR-53 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 348, are hereby incorporated into this license. Constellation Energy Generation, LLC 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 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 30, 2023 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2023.08.30 13:29:44 -04'00'
CALVERT CLIFFS NUCLEAR POWER PLANT, LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 326 Renewed License No. DPR-69
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated October 25, 2022, 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 Renewed Facility Operating License No. DPR-69 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 326, are hereby incorporated into this 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 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 30, 2023 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2023.08.30 13:30:09 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 348 AND 326 RENEWED FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License DPR-53 License DPR-53 Page 3 Page 3 License DPR-69 License DPR-69 Page 3 Page 3 TSs TSs 5.5-16 5.5-16 Amendment No. 348 (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1)
Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at steady-state reactor core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 348, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
(a)
For Surveillance Requirements (SRs) that are new, in Amendment 227 to Facility Operating License No. DPR-53, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 227. For SRs that existed prior to Amendment 227, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 227.
(3)
Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 345 are hereby incorporated into this license.
Constellation Energy Generation, LLC shall operate the facility in accordance with the Additional Conditions.
Amendment No. 326 (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1)
Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at steady-state reactor core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 326, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
(a)
For Surveillance Requirements (SRs) that are new, in Amendment 201 to Facility Operating License No. DPR-69, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 201. For SRs that existed prior to Amendment 201, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 201.
(3)
Less Than Four Pump Operation The licensee shall not operate the reactor at power levels in excess of five (5) percent of rated thermal power with less than four (4) reactor coolant pumps in operation. This condition shall remain in effect until the licensee has submitted safety analyses for less than four pump operation, and approval for such operation has been granted by the Commission by amendment of this license.
Programs and Manuals 5.5 5.5 Programs and Manuals CALVERT CLIFFS - UNIT 1 5.5-16 CALVERT CLIFFS - UNIT 2 Amendment No. 348 Amendment No. 326 c.
Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and d.
Other appropriate limitations and remedial or compensatory actions.
A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:
a.
A required system redundant to system(s) supported by the inoperable support system is also inoperable; or b.
A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or c.
A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.
5.5.16 The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.
Containment Leakage Rate Testing Program A program shall be established to implement the leakage testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, Option B. This program shall be in accordance with the guidelines contained in Nuclear Energy Institute (NEI) 94-01, Industry Guideline for Implementing Performance Based Option of 10 CFR Part 50, Appendix J, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A dated October 2008.
CONSTELLATION ENERGY GENERATION, LLC PSEG NUCLEAR, LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 343 Subsequent Renewed License No. DPR-44
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated October 25, 2022, 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 Subsequent 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. 343, are hereby incorporated in the license. Constellation Energy Generation, LLC 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 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Subsequent Renewed Facility Operating License Date of Issuance: August 30, 2023 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2023.08.30 13:31:22 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 343 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 DOCKET NO. 50-277 Replace the following pages of the Subsequent Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License DPR-44 License DPR-44 Page 3 Page 3 TSs TSs 5.0-16 5.0-16 5.0-17 5.0-17
Page 3 Subsequent Renewed License No. DPR-44 Amendment No. 343 (1)
Constellation Energy Generation, LLC, pursuant to Section 104b of the Act and 10 CFR Part 50, Licensing of Production and Utilization Facilities, to possess, use, and operate the facility and PSEG Nuclear to possess the facility at the designated location in Peach Bottom, York County, Pennsylvania in accordance with the procedures and limitations set forth in this license; (2)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or components; (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.
C.
This subsequent renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 4016 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 343, are hereby incorporated in the license.
Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Technical Specifications (TS) Bases Control Program (continued) d.
Proposed changes that meet the criteria of b. above shall be reviewed and approved by the NRC prior to implementation.
Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.11 Safety Function Determination Program (SFDP)
This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.
a.
The SFDP shall contain the following:
1.
Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected; 2.
Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists; 3.
Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and 4.
Other appropriate limitations and remedial or compensatory actions.
b.
A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:
(continued)
PBAPS UNIT 2 5.0-16 Amendment No. 343
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Program (SFDP) (continued) 1.
A required system redundant to system(s) supported by the inoperable support system is also inoperable; or 2.
A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or 3.
A required system redundant to support system(s) for the supported systems (b.1) and (b.2) above is also inoperable.
c.
The SFDP identifies where a loss of safety function exists.
If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.
5.5.12 Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008, as modified by the following exception:
a.
Section 10.2: MSIV leakage is excluded from the combined total of 0.6 La for the Type B and C tests.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 49.1 psig.
The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.7% of primary containment air weight per day.
Leakage Rate acceptance criteria are:
a.
Primary Containment leakage rate acceptance criterion is 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 0.60 La for the Type B and Type C tests and 0.75 La for Type A tests; (continued)
PBAPS UNIT 2 5.0-17 Amendment No. 343
CONSTELLATION ENERGY GENERATION, LLC PSEG NUCLEAR, LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 346 Subsequent Renewed License No. DPR-56
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated October 25, 2022, 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 Subsequent 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. 346, are hereby incorporated in the license. Constellation Energy Generation, LLC 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 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Subsequent Renewed Facility Operating License Date of Issuance: August 30, 2023 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2023.08.30 13:32:00 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 346 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 DOCKET NO. 50-278 Replace the following pages of the Subsequent Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License DPR-56 License DPR-56 Page 3 Page 3 TSs TSs 5.0-16 5.0-16 5.0-17 5.0-17
Page 3 Subsequent Renewed License No. DPR-56 Amendment No. 346 Pennsylvania in accordance with the procedures and limitations set forth in this license; (2)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or components; (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.
C.
This subsequent renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 4016 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 346, are hereby incorporated in the license.
Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Technical Specifications (TS) Bases Control Program (continued) d.
Proposed changes that meet the criteria of b. above shall be reviewed and approved by the NRC prior to implementation.
Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.11 Safety Function Determination Program (SFDP)
This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.
a.
The SFDP shall contain the following:
1.
Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected; 2.
Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists; 3.
Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and 4.
Other appropriate limitations and remedial or compensatory actions.
b.
A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed.
For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:
(continued)
PBAPS UNIT 3 5.0-16 Amendment No. 346
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Program (SFDP) (continued) 1.
A required system redundant to system(s) supported by the inoperable support system is also inoperable; or 2.
A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or 3.
A required system redundant to support system(s) for the supported systems (b.1) and (b.2) above is also inoperable.
- c.
The SFDP identifies where a loss of safety function exists.
If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.
5.5.12 Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, Revision 3-A dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008, as modified by the following exception:
a.
Section 10.2: MSIV leakage is excluded from the combined total of 0.6 La for the Type B and C tests.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 49.1 psig.
The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.7% of primary containment air weight per day.
Leakage Rate acceptance criteria are:
- a. Primary Containment leakage rate acceptance criterion is 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 0.60 La for the Type B and Type C tests and 0.75 La for Type A tests; (continued)
PBAPS UNIT 3 5.0-17 Amendment No. 346
R. E. GINNA NUCLEAR POWER PLANT, LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 156 Renewed License No. DPR-18
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated October 25, 2022, 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 Renewed Facility Operating License No. DPR-18 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 156, are hereby incorporated in the renewed license. Constellation Energy Generation, LLC 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 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 30, 2023 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2023.08.30 13:32:39 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 156 RENEWED FACILITY OPERATING LICENSE NO. DPR-18 R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License DPR-18 License DPR-18 Page 4 Page 4 TSs TSs 5.5-10 5.5-10 R. E. Ginna Nuclear Power Plant Amendment No. 156 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 156, are hereby incorporated in the renewed license.
Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Fire Protection Constellation Energy Generation, LLC shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensees amendment request dated March 28, 2013, supplemented by letters dated December 17, 2013; January 29, 2014; February 28, 2014; September 5, 2014; September 24, 2014; December 4, 2014; March 18, 2015; June 11, 2015; August 7, 2015; and as approved in the safety evaluation report dated November 23, 2015. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.
(a)
Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed fire PRA model, methods that have been approved by NRC through a plant-specific license amendment or NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.
- 1.
Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.
Programs and Manuals 5.5 b.
Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
1.
A change in the TS incorporated in the license; or 2.
A change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
c.
The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
d.
Proposed changes that meet the criteria of Specification 5.5.13.b.1 or Specification 5.5.13.b.2 shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71e.
5.5.14 Safety Function Determination Program (SFDP)
This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:
a.
Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected; b.
Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists; c.
Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and d.
Other appropriate limitations and remedial or compensatory actions.
A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:
a.
A required system redundant to the supported system(s) is also inoperable; or R.E. Ginna Nuclear Power Plant 5.5-10 Amendment 156
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 348 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 326 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 AMENDMENT NO. 343 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-44 AMENDMENT NO. 346 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-56 AND AMENDMENT NO. 156 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-18 CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 R. E. GINNA NUCLEAR POWER PLANT DOCKET NOS. 50-317, 50-318, 50-277, 50-278, AND 50-244
1.0 INTRODUCTION
By application dated October 25, 2022 (Agencywide Documents Access and Management System Accession No. ML22298A010), Constellation Energy Generation, LLC (CEG, the licensee) submitted a license amendment request (LAR) for Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2; Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3; and R. E. Ginna Nuclear Power Plant (Ginna) (collectively, the facilities). The proposed amendments revise the technical specifications (TS) for each facility based on Technical Specification Task Force (TSTF) traveler TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications, dated July 16, 1999 (ML040611069). The U.S. Nuclear Regulatory Commission (NRC or Commission) approved TSTF-273-A, Revision 2, on August 16, 1999 (ML16237A031).
These amendments revise the TSs to add explanatory text to the programmatic description of the safety function determination program (SFDP) in TS 5.5.15 (CCNPP), TS 5.5.11 (PBAPS) and TS 5.5.14 (Ginna) to provide clarification that when determining loss of function, a loss of power does not need to be considered.
1.1 Proposed TS Changes to Adopt TSTF-273-A The following text will be added to TS 5.5.11 (PBAPS, Units 2 and 3), TS 5.5.15 (CCNPP), and TS 5.5.14 (Ginna), additions in bold italics:
A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed.
For the purpose of this program, a loss of safety function may exist when a support system is inoperable and the following text will be added to TS 5.5.11 (PBAPS, Units 2 and 3), addition in bold italics:
Safety Function Determination Program (SFDP) (continued)
When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.
1.2 Editorial Variations CEG implemented changes to TS 5.5.15 (CCNPP) and TS 5.5.14 (Ginna), Safety Function Determination Program (SFDP) at CCNPP, Units 1 and 2, and Ginna under TSTF-567, Revision 1 Add Containment Sump TS to Address GSl [General Safety Issue] -191 Issues (CCNPP: ML21299A005; Ginna: ML20167A007). The change under TSTF-567 added the following wording to TS 5.5.15 (CCNPP) and TS 5.5.14 (Ginna): When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system. As such, the revised TS for CCNPP, Units 1 and 2, and Ginna, will not include this change.
PBAPS, Units 2 and 3, and Ginna utilize different numbering than the Standard Technical Specifications (STS) on which TSTF-273 was based. Specifically, the TS numbering for NUREG-1433 for BWR [boiling-water reactors]/4 plants includes TS 5.5.12, Safety Function Determination Program, which corresponds to TS 5.5.11 for PBAPS, Units 2 and 3. The TS numbering for NUREG-1433 for Westinghouse plants includes TS 5.5.15, Safety Function Determination Program, which corresponds to TS 5.5.14 for Ginna. This difference is administrative in nature and does not affect the applicability of TSTF-273 to PBAPS, Units 2 and 3, and Ginna.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) section 50.36(c)(2) requires that TSs include limiting conditions for operation (LCOs). Per 10 CFR 50.36(c)(2)(i), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation also requires that when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the condition can be met.
The NRC staff guidance for the review of TSs is in chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition (SRP), March 2010 (ML100351425).
As described therein, as part of the regulatory standardization effort, the NRC staff has prepared STSs for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the Standard Technical Specifications, Westinghouse Plants, NUREG-1431, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21259A155 and ML21259A159);
Standard Technical Specifications, General Electric Plants, BWR/4, NUREG-1433, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21272A357 and ML21272A358, respectively); and Standard Technical Specifications, Combustion Engineering Plants NUREG-1432 Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21258A421 and ML21258A424, respectively).
These NUREGs were developed such that the Actions for a single support system inoperability would be addressed by that support system's Actions - without cascading to the supported system, even if both trains of the support system were inoperable resulting from a loss of function. This intent is clarified by the proposed changes specified in section 1.1, above. Without this clarification, supported systems with a single support system (such as both containment spray and emergency core cooling system trains supported by the refueling water tank) would be declared inoperable when the support system is inoperable under the provisions of LCO 3.0.6 even though the support system Actions were designed to provide the appropriate response.
3.0 TECHNICAL EVALUATION
The licensee proposed to revise TS 5.5.15 (CCNPP), TS 5.5.11 (PBAPS) and TS 5.5.14 (Ginna) by incorporating TSTF-273-A, Revision 2, changes. The changes to TS 5.5.15, TS 5.5.11 and TS 5.5.14, and the Bases for LCO 3.0.6, are intended to clarify the intent of LCO 3.0.6 in the event a single inoperable TS support system makes both redundant subsystems of a supported system inoperable (a loss of safety function condition). The STS were developed such that the LCO actions for a single support system inoperability would be addressed by that support system's actions, without cascading to the supported system's LCO actions. LCO 3.0.6 establishes this exception to LCO 3.0.2 for support systems that have an LCO specified in the TSs. However, LCO 3.0.6 also requires an evaluation under the SFDP to ensure that a loss of safety function does not exist.
The NRC staff concludes that these changes do not affect the design, operation, or maintenance of CCNPP, PBAPS, and Ginna, but only provide clarity for determining when a loss of safety function condition exists and what LCO actions are required to be taken when a safety function is lost. By clarifying the intent of the existing requirements of the SFDP and LCO 3.0.6, these changes remove an ambiguity that could lead to a misinterpretation of those requirements.
Additionally, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(2) continue to be met because the minimum performance level of equipment needed for safe operation of the facility is contained in the LCO, and the appropriate remedial measures are specified if the LCO is not met. Based on the above, the NRC staff concludes that the changes to TS 5.5.15 (CCNPP), TS 5.5.11 (PBAPS) and TS 5.5.14 (Ginna), are acceptable.
The NRC staff reviewed the proposed variations discussed in Section 1.2 of this safety evaluation from TSTF-273-A and determined that they are editorial in nature, do not substantively change TS requirements, and continue to meet the intent of TSTF-273-A.
Therefore, the NRC staff finds the proposed variations acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Maryland and New York State officials, and the Commonwealth of Pennsylvania officials were notified of the proposed issuance of the amendments on June 6, 2023. The State and Commonwealth officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components 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 in the Federal Register (87 FR 79359; December 27, 2022),
and there has been no public comment on such finding. 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 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) there is reasonable assurance that 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.
Principal Contributors: J. Wilson, NRR C. Tilton, NRR Date: August 30, 2023
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2, AMENDMENT NOS. 348 AND 326; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, AMENDMENT NOS. 343 AND 346; AND R. E. GINNA NUCLEAR POWER PLANT, AMENDMENT NO. 156 - ISSUANCE OF AMENDMENTS TO ADOPT TSTF-273-A, REVISION 2, SAFETY FUNCTION DETERMINATION PROGRAM CLARIFICATIONS (EPID L-2022-LLA-0151)
DATED AUGUST 30, 2023 DISTRIBUTION:
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