ML24352A075
| ML24352A075 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 03/19/2025 |
| From: | Scott Wall Plant Licensing Branch III |
| To: | Rhoades D Constellation Energy Generation |
| Wiebe J | |
| References | |
| EPID L-2024-LLA-0068 | |
| Download: ML24352A075 (1) | |
Text
March 19, 2025 David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS NOS. 239, 239, 238, AND 238 REGARDING REMOVAL OF POWER DISTRIBUTION MONITORING SYSTEM (PDMS) DETAILS FROM TECHNICAL SPECIFICATIONS (EPID L-2024-LLA-0068)
Dear David Rhoades:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed amendments (listed below) in response to the Constellation Energy Generation, LLC application dated May 24, 2024), as supplemented by letter dated December 10, 2024:
- 1.
Amendment No. 239 to Renewed Facility Operating License No. NPF-72 and Amendment No. 239 to Renewed Facility Operating License No. NPF-77 for Braidwood Station, Units 1 and 2 (Braidwood), respectively;
- 2.
Amendment No. 238 to Renewed Facility Operating License No. NPF-37 and Amendment No. 238 to Renewed Facility Operating License No. NPF-66 for Byron Station, Units 1 and 2 (Byron), respectively; The amendments remove extraneous detail related to the Best Estimate Analyzer for Core Operations - Nuclear (BEACON') software and more closely align Braidwood and Byron Technical Specifications with the Standard Technical Specifications for Westinghouse plants, NUREG-1431, Revision 5.
A copy of the Safety Evaluation is also enclosed. A 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. STN 50-456, STN 50-457, STN 50-454 and STN 50-455
Enclosures:
- 1. Amendment No. 239 to NPF-72
- 2. Amendment No. 239 to NPF-77
- 3. Amendment No. 238 to NPF-37
- 4. Amendment No. 238 to NPF-66
- 5. Safety Evaluation cc: Listserv CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 239 Renewed License No. NPF-72
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (the licensee) dated May 24, 2024, as supplemented by letter dated December 10, 2024, 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 renewed 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. NPF-72 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 239 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed 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 no later than the start of the 2025 fall outage for Braidwood Unit 1.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: March 19, 2025 ROBERT KUNTZ Digitally signed by ROBERT KUNTZ Date: 2025.03.19 07:12:27 -04'00'
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 239 Renewed License No. NPF-77
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (the licensee) dated May 24, 2024, as supplemented by letter dated December 10, 2024, 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 renewed 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. NPF-77 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 239 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed 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 no later than the start of the 2026 spring outage for Braidwood, Unit 2.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: March 19, 2025 ROBERT KUNTZ Digitally signed by ROBERT KUNTZ Date: 2025.03.19 07:12:51 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 239 AND 239 RENEWED FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Renewed Facility Operating Licenses and 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.
Renewed Facility Operating Licenses REMOVE INSERT License NPF-72 License NPF-72 License NPF-77 License NPF-77 Technical Specifications REMOVE INSERT 3.1.4 - 2 3.1.4 - 2 3.1.4 - 3 3.1.4 - 3 3.1.4 - 4 3.1.4 - 4 3.2.1 - 1 3.2.1 - 1 3.2.1 - 2 3.2.1 - 2 3.2.1 - 3 3.2.1 - 3 3.2.1 - 4 3.2.1 - 4 3.2.1 - 5 3.2.1 - 5 3.2.1 - 6 3.2.2 - 1 3.2.2 - 1 3.2.2 - 2 3.2.2 - 2 3.2.2 - 3 3.2.2 - 3 3.2.4 - 1 3.2.4 - 1 3.2.4 - 2 3.2.4 - 2 3.2.4 - 3 3.2.4 - 3 3.2.4 - 4 3.2.4 - 4 3.2.5 - 1 3.2.5 - 1 5.6 - 3 5.6 - 3
(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 associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 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 renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 239 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-72 Amendment No. 239
(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 associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 239 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-77 Amendment No. 239
Rod Group Alignment Limits 3.1.4 BRAIDWOOD UNITS 1 & 2 3.1.4 2 Amendment 239 110 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
One rod not within alignment limit.
B.1.1 Verify SDM is within the limits specified in the COLR.
OR B.1.2 Initiate boration to restore SDM to within limit.
AND B.2 Reduce THERMAL POWER to 75% RTP.
AND B.3 Verify SDM is within the limits specified in the COLR.
AND B.4 Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 72 hours (continued)
Rod Group Alignment Limits 3.1.4 BRAIDWOOD UNITS 1 & 2 3.1.4 3 Amendment 239 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
(continued)
B.5 Re-evaluate safety analyses and confirm results remain valid for duration of operation under these conditions.
5 days C.
More than one rod not within alignment limit.
C.1.1 Verify SDM is within the limits specified in the COLR.
OR C.1.2 Initiate boration to restore required SDM to within limit.
AND C.2 Be in MODE 3.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (continued)
Rod Group Alignment Limits 3.1.4 BRAIDWOOD UNITS 1 & 2 3.1.4 4 Amendment 239 196 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and associated Completion Time of Condition B not met.
D.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1
NOTE--------------------
Not required to be performed for rods associated with inoperable rod position indicator or demand position indicator.
Verify position of individual rods within alignment limit.
In accordance with the Surveillance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.
In accordance with the Surveillance Frequency Control Program SR 3.1.4.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.7 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with:
a.
Tavg 550°F; and b.
All reactor coolant pumps operating.
Prior to criticality after each removal of the reactor head
FQ(Z) 3.2.1 BRAIDWOOD UNITS 1 & 2 3.2.1 1 Amendment 239 225 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
LCO 3.2.1 FQ(Z), as approximated by
)
Z
(
FC Q
and
)
Z
(
FW Q
, shall be within the limit specified in the COLR.
APPLICABILITY:
MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE---------
Required Action A.4 shall be completed whenever this Condition is entered.
)
Z
(
FC Q
not within limit.
A.1 Reduce THERMAL POWER 1% RTP for each 1%
)
Z
(
FC Q
exceeds limit.
AND A.2 Reduce Power Range Neutron Flux-High trip setpoints 1%
for each 1%
)
Z
(
FC Q
exceeds limit.
15 minutes after each
)
Z
(
FC Q
determination 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each
)
Z
(
FC Q
determination AND A.3 Reduce Overpower T trip setpoints 1%
for each 1%
)
Z
(
FC Q
exceeds limit.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each
)
Z
(
FC Q
determination AND A.4 Perform SR 3.2.1.1 and SR 3.2.1.2.
Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)
FQ(Z) 3.2.1 BRAIDWOOD UNITS 1 & 2 3.2.1 2 Amendment 239 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
NOTE---------
Required Action B.5 shall be completed whenever this Condition is entered.
)
Z
(
FW Q
not within limit.
B.1 Reduce THERMAL POWER as specified in the COLR.
AND B.2 Reduce AFD limits as specified in the COLR.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours AND B.3 Reduce Power Range Neutron Flux-High trip setpoints 1%
for each 1% that the maximum allowable power of the AFD limits is reduced.
AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.4 Reduce Overpower T trip setpoints 1%
for each 1% that the maximum allowable power of the AFD limits is reduced.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND B.5 Perform SR 3.2.1.1 and SR 3.2.1.2.
Prior to increasing THERMAL POWER above the maximum allowable power of the AFD limits C.
Required Action and associated Completion Time not met.
C.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
FQ(Z) 3.2.1 BRAIDWOOD UNITS 1 & 2 3.2.1 3 Amendment 239 SURVEILLANCE REQUIREMENTS
NOTE------------------------------------
During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.
SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify
)
Z
(
FC Q
is within limit specified in the COLR.
Prior to exceeding 75% RTP after each refueling AND Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which
)
Z
(
FC Q
was last verified AND In accordance with the Surveillance Frequency Control Program (continued)
FQ(Z) 3.2.1 BRAIDWOOD UNITS 1 & 2 3.2.1 4 Amendment 239 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.2.1.2
NOTE--------------------
If
)
Z
(
FW Q
measurements indicate that either the maximum over z [
)
Z
(
FC Q
/ K(Z)]
OR maximum over z [
)
Z
(
FW Q
/ K(Z)]
has increased since the previous evaluation of
)
Z
(
FC Q
or if
)
Z
(
FW Q
is expected to increase prior to the next evaluation of
)
Z
(
FC Q
- a. Increase
)
Z
(
FW Q
by the greater of a factor of [1.02] or the appropriate factor specified in the COLR and reverify
)
Z
(
FW Q
is within limits specified in the COLR; or b.
Repeat SR 3.2.1.2 once per 7 EFPD until either a. above is met or two successive flux maps indicate that the maximum over z [
)
Z
(
FC Q
/ K(Z)]
and maximum over z [
)
Z
(
FW Q
/ K(Z)]
has not increased.
(continued)
FQ(Z) 3.2.1 BRAIDWOOD UNITS 1 & 2 3.2.1 5 Amendment 239 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued)
Verify
)
Z
(
FW Q
is within limit specified in the COLR.
Prior to exceeding 75% RTP after each refueling AND Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which
)
Z
(
FW Q
was last verified AND In accordance with the Surveillance Frequency Control Program
N H
F 3.2.2 BRAIDWOOD UNITS 1 & 2 3.2.2 1 Amendment 239 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor
)
F
(
N H
H F shall be within the limit specified in the COLR.
APPLICABILITY:
MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE---------
Required Actions A.2 and A.3 must be completed whenever Condition A is entered.
N H
F not within limit.
A.1.1 Restore to within limit.
OR A.1.2.1 Reduce THERMAL POWER to < 50% RTP.
AND A.1.2.2 Reduce Power Range Neutron Flux-High trip setpoints to 55% RTP.
AND A.2 Perform SR 3.2.2.1.
AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 24 hours (continued)
N H
F 3.2.2 BRAIDWOOD UNITS 1 & 2 3.2.2 2 Amendment 239 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.3
NOTE---------
THERMAL POWER does not have to be reduced to comply with this Required Action.
Perform SR 3.2.2.1.
Prior to exceeding 50% RTP AND Prior to exceeding 75% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 95% RTP B.
Required Action and associated Completion Time not met.
B.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
N H
F 3.2.2 BRAIDWOOD UNITS 1 & 2 3.2.2 3 Amendment 239 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify N
H F is within limits specified in the COLR.
Prior to exceeding 75% RTP after each refueling AND In accordance with the Surveillance Frequency Control Program
QPTR 3.2.4 BRAIDWOOD UNITS 1 & 2 3.2.4 1 Amendment 239 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)
LCO 3.2.4 The QPTR shall be 1.02.
APPLICABILITY:
MODE 1 with THERMAL POWER > 50% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
QPTR not within limit.
A.1 Reduce THERMAL POWER 3% from RTP for each 1% of QPTR
> 1.00.
AND A.2 Determine QPTR.
AND A.3 Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.
AND 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each QPTR determination Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 24 hours after achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter (continued)
QPTR 3.2.4 BRAIDWOOD UNITS 1 & 2 3.2.4 2 Amendment 239 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.4 Re-evaluate safety analyses and confirm results remain valid for duration of operation under this condition.
AND A.5
NOTES--------
1.
Perform Required Action A.5 only after Required Action A.4 is completed.
2.
Required Action A.6 shall be completed whenever Required Action A.5 is performed.
Normalize excore detectors to restore QPTR to within limits.
AND Prior to increasing the THERMAL POWER above the limit of Required Action A.1 Prior to increasing the THERMAL POWER above the limit of Required Action A.1 (continued)
QPTR 3.2.4 BRAIDWOOD UNITS 1 & 2 3.2.4 3 Amendment 239 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.6
NOTE---------
Perform Required Action A.6 only after Required Action A.5 is completed.
Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions at RTP not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after exceeding the THERMAL POWER limit of Required Action A.1 B.
Required Action and associated Completion Time not met.
B.1 Reduce THERMAL POWER to 50% RTP.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
QPTR 3.2.4 BRAIDWOOD UNITS 1 & 2 3.2.4 4 Amendment 239 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1
NOTES--------------------
1.
With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER 75% RTP, the remaining three power range channel inputs can be used for calculating QPTR.
2.
SR 3.2.4.2 may be performed in lieu of this Surveillance.
Verify QPTR is within limit by calculation. In accordance with the Surveillance Frequency Control Program SR 3.2.4.2
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after input from one Power Range Neutron Flux channel is inoperable with THERMAL POWER > 75% RTP.
Verify QPTR is within limit using the movable incore detectors.
In accordance with the Surveillance Frequency Control Program
DNBR 3.2.5 BRAIDWOOD UNITS 1 & 2 3.2.5 1 Amendment 239 3.2 POWER DISTRIBUTION LIMITS 3.2.5 DELETED
Reporting Requirements 5.6 BRAIDWOOD UNITS 1 & 2 5.6 3 Amendment 239 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";
LCO 3.1.3, "Moderator Temperature Coefficient";
LCO 3.1.5, "Shutdown Bank Insertion Limits";
LCO 3.1.6, "Control Bank Insertion Limits";
LCO 3.1.8, "PHYSICS TESTS Exceptions - MODE 2";
LCO 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z))";
LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor
)
F
( N H
LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)";
LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits"; and LCO 3.9.1, "Boron Concentration";
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluations Methodology," July 1985.
2.
Not Used.
3.
NFSR-0016, "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods," July 1983.
4.
NFSR-0081, "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods Using the Phoenix-P and ANC Computer Codes," July 1990.
5.
Not used.
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 238 Renewed License No. NPF-37
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (the licensee) dated May 24, 2024, as supplemented by letter dated December 10, 2024, 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 renewed 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. NPF-37 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 238 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed 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 no later than the start of the 2026 spring outage for Byron, Unit 1.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: March 19, 2025 ROBERT KUNTZ Digitally signed by ROBERT KUNTZ Date: 2025.03.19 07:13:32 -04'00'
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 238 Renewed License No. NPF-66
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (the licensee) dated May 24, 2024, as supplemented by letter dated December 10, 2024, 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. NPF-66 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 238, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed 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 no later than the start of the 2026 fall outage for Byron, Unit 2.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: March 19, 2025 ROBERT KUNTZ Digitally signed by ROBERT KUNTZ Date: 2025.03.19 07:14:01 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 238 AND 238 RENEWED FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Renewed Facility Operating Licenses and 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.
Renewed Facility Operating Licenses REMOVE INSERT License NPF-37 License NPF-37 License NPF-66 License NPF-66 Technical Specifications REMOVE INSERT 3.1.4 - 2 3.1.4 - 2 3.1.4 - 3 3.1.4 - 3 3.1.4 - 4 3.1.4 - 4 3.2.1 - 1 3.2.1 - 1 3.2.1 - 2 3.2.1 - 2 3.2.1 - 3 3.2.1 - 3 3.2.1 - 4 3.2.1 - 4 3.2.1 - 5 3.2.1 - 5 3.2.1 - 6 3.2.2 - 1 3.2.2 - 1 3.2.2 - 2 3.2.2 - 2 3.2.2 - 3 3.2.2 - 3 3.2.4 - 1 3.2.4 - 1 3.2.4 - 2 3.2.4 - 2 3.2.4 - 3 3.2.4 - 3 3.2.4 - 4 3.2.4 - 4 3.2.5 - 1 3.2.5 - 1 5.6 - 3 5.6 - 3
(2)
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 Updated Final Safety Analysis Report, as supplemented and amended; (3)
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)
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 associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 238 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
(4)
Deleted.
Renewed License No. NPF-37 Amendment No. 238
(2)
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 Updated Final Safety Analysis Report, as supplemented and amended; (3)
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)
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 associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 238, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
Renewed License No. NPF-66 Amendment No. 238
Rod Group Alignment Limits 3.1.4 BYRON UNITS 1 & 2 3.1.4 2 Amendment 238 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
One rod not within alignment limit.
B.1.1 Verify SDM is within the limits specified in the COLR.
OR B.1.2 Initiate boration to restore SDM to within limit.
AND B.2 Reduce THERMAL POWER to 75% RTP.
AND B.3 Verify SDM is within the limits specified in the COLR.
AND B.4 Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 72 hours (continued)
Rod Group Alignment Limits 3.1.4 BYRON UNITS 1 & 2 3.1.4 3 Amendment 238 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
(continued)
B.5 Re-evaluate safety analyses and confirm results remain valid for duration of operation under these conditions.
5 days C.
More than one rod not within alignment limit.
C.1.1 Verify SDM is within the limits specified in the COLR.
OR C.1.2 Initiate boration to restore required SDM to within limit.
AND C.2 Be in MODE 3.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (continued)
Rod Group Alignment Limits 3.1.4 BYRON UNITS 1 & 2 3.1.4 4 Amendment 238 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and associated Completion Time of Condition B not met.
D.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1
NOTE--------------------
Not required to be performed for rods associated with inoperable rod position indicator or demand position indicator.
Verify position of individual rods within alignment limit.
In accordance with the Surveillance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.
In accordance with the Surveillance Frequency Control Program SR 3.1.4.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.7 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with:
a.
Tavg 550°F; and b.
All reactor coolant pumps operating.
Prior to criticality after each removal of the reactor head
FQ(Z) 3.2.1 BYRON UNITS 1 & 2 3.2.1 1 Amendment 238 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
LCO 3.2.1 FQ(Z), as approximated by
)
Z
(
FC Q
and
)
Z
(
FW Q
, shall be within the limit specified in the COLR.
APPLICABILITY:
MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE---------
Required Action A.4 shall be completed whenever this Condition is entered.
)
Z
(
FC Q
not within limit.
A.1 Reduce THERMAL POWER 1% RTP for each 1%
)
Z
(
FC Q
exceeds limit.
AND A.2 Reduce Power Range Neutron Flux-High trip setpoints 1%
for each 1%
)
Z
(
FC Q
exceeds limit.
15 minutes after each
)
Z
(
FC Q
determination.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each
)
Z
(
FC Q
determination AND A.3 Reduce Overpower T trip setpoints 1%
for each 1%
)
Z
(
FC Q
exceeds limit.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each
)
Z
(
FC Q
determination AND A.4 Perform SR 3.2.1.1 and SR 3.2.1.2.
Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)
FQ(Z) 3.2.1 BYRON UNITS 1 & 2 3.2.1 2 Amendment 238 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
NOTE---------
Required Action B.5 shall be completed whenever this Condition is entered.
)
Z
(
FW Q
not within limit.
B.1 Reduce THERMAL POWER as specified in the COLR.
AND B.2 Reduce AFD limits as specified in the COLR.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours AND B.3 Reduce Power Range Neutron Flux-High trip setpoints 1%
for each 1% that the maximum allowable power of the AFD limits is reduced.
AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.4 Reduce Overpower T trip setpoints 1%
for each 1% that the maximum allowable power of the AFD limits is reduced.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND B.5 Perform SR 3.2.1.1 and SR 3.2.1.2.
Prior to increasing THERMAL POWER above the maximum allowable power of the AFD limits.
C.
Required Action and associated Completion Time not met.
C.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
FQ(Z) 3.2.1 BYRON UNITS 1 & 2 3.2.1 3 Amendment 238 SURVEILLANCE REQUIREMENTS
NOTE------------------------------------
During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.
SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify
)
Z
(
FC Q
is within limit specified in the COLR.
Prior to exceeding 75% RTP after each refueling AND Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which
)
Z
(
FC Q
was last verified AND In accordance with the Surveillance Frequency Control Program (continued)
FQ(Z) 3.2.1 BYRON UNITS 1 & 2 3.2.1 4 Amendment 238 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.2.1.2
NOTE-------------------
If
)
Z
(
FW Q
measurements indicate that either the maximum over z [
)
Z
(
FC Q
/ K(Z)]
OR maximum over z [
)
Z
(
FW Q
/ K(Z)]
has increased since the previous evaluation of
)
Z
(
FC Q
or if
)
Z
(
FW Q
is expected to increase prior to the next evaluation of
)
Z
(
FC Q
a.
Increase
)
Z
(
FW Q
by the greater of a factor of [1.02] or the appropriate factor specified in the COLR and reverify
)
Z
(
FW Q
is within limits specified in the COLR; or b.
Repeat SR 3.2.1.2 once per 7 EFPD until either a. above is met or two successive flux maps indicate that the maximum over z [
)
Z
(
FC Q
/ K(Z)]
and maximum over z [
)
Z
(
FW Q
/ K(Z)]
has not increased.
(continued)
FQ(Z) 3.2.1 BYRON UNITS 1 & 2 3.2.1 5 Amendment 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued)
Verify
)
Z
(
FW Q
is within limit specified in the COLR.
Prior to exceeding 75% RTP after each refueling AND Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which
)
Z
(
FW Q
was last verified AND In accordance with the Surveillance Frequency Control Program
N H
F 3.2.2 BYRON UNITS 1 & 2 3.2.2 1 Amendment 238 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor
)
F
(
N H
H F shall be within the limit specified in the COLR.
APPLICABILITY:
MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE---------
Required Actions A.2 and A.3 must be completed whenever Condition A is entered.
N H
F not within limit.
A.1.1 Restore to within limit.
OR A.1.2.1 Reduce THERMAL POWER to < 50% RTP.
AND A.1.2.2 Reduce Power Range Neutron Flux-High trip setpoints to 55% RTP.
AND A.2 Perform SR 3.2.2.1.
AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 24 hours (continued)
N H
F 3.2.2 BYRON UNITS 1 & 2 3.2.2 2 Amendment 238 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.3
NOTE---------
THERMAL POWER does not have to be reduced to comply with this Required Action.
Perform SR 3.2.2.1.
Prior to exceeding 50% RTP AND Prior to exceeding 75% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 95% RTP B.
Required Action and associated Completion Time not met.
B.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
N H
F 3.2.2 BYRON UNITS 1 & 2 3.2.2 3 Amendment 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify N
H F is within limits specified in the COLR.
Prior to exceeding 75% RTP after each refueling AND In accordance with the Surveillance Frequency Control Program
QPTR 3.2.4 BYRON UNITS 1 & 2 3.2.4 1 Amendment 238 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)
LCO 3.2.4 The QPTR shall be 1.02.
APPLICABILITY:
MODE 1 with THERMAL POWER > 50% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
QPTR not within limit.
A.1 Reduce THERMAL POWER 3% from RTP for each 1% of QPTR
> 1.00.
AND A.2 Determine QPTR.
AND A.3 Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.
AND 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each QPTR determination Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 24 hours after achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter (continued)
QPTR 3.2.4 BYRON UNITS 1 & 2 3.2.4 2 Amendment 238 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.4 Re-evaluate safety analyses and confirm results remain valid for duration of operation under this condition.
AND A.5
NOTES--------
1.
Perform Required Action A.5 only after Required Action A.4 is completed.
2.
Required Action A.6 shall be completed whenever Required Action A.5 is performed.
Normalize excore detectors to restore QPTR to within limits.
AND Prior to increasing the THERMAL POWER above the limit of Required Action A.1 Prior to increasing the THERMAL POWER above the limit of Required Action A.1 (continued)
QPTR 3.2.4 BYRON UNITS 1 & 2 3.2.4 3 Amendment 238 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.6
NOTE---------
Perform Required Action A.6 only after Required Action A.5 is completed.
Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions at RTP not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after exceeding the THERMAL POWER limit of Required Action A.1 B.
Required Action and associated Completion Time not met.
B.1 Reduce THERMAL POWER to 50% RTP.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
QPTR 3.2.4 BYRON UNITS 1 & 2 3.2.4 4 Amendment 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1
NOTES--------------------
1.
With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER 75% RTP, the remaining three power range channel inputs can be used for calculating QPTR.
2.
SR 3.2.4.2 may be performed in lieu of this Surveillance.
Verify QPTR is within limit by calculation. In accordance with the Surveillance Frequency Control Program SR 3.2.4.2
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after input from one Power Range Neutron Flux channel is inoperable with THERMAL POWER > 75% RTP.
Verify QPTR is within limit using the movable incore detectors.
In accordance with the Surveillance Frequency Control Program
DNBR 3.2.5 BYRON UNITS 1 & 2 3.2.5 1 Amendment 238 3.2 POWER DISTRIBUTION LIMITS 3.2.5 DELETED
Reporting Requirements 5.6 BYRON UNITS 1 & 2 5.6 3 Amendment 238 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";
LCO 3.1.3, "Moderator Temperature Coefficient";
LCO 3.1.5, "Shutdown Bank Insertion Limits";
LCO 3.1.6, "Control Bank Insertion Limits";
LCO 3.1.8, "PHYSICS TESTS Exceptions - MODE 2";
LCO 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z))";
LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor
)
F
( N H
LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)";
LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits"; and LCO 3.9.1, "Boron Concentration";
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluations Methodology," July 1985.
2.
Not Used.
3.
NFSR-0016, "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods," July 1983.
4.
NFSR-0081, "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods Using the Phoenix-P and ANC Computer Codes," July 1990.
5.
Not used.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 239 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 239 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 238 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-37, AND AMENDMENT NO. 238 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-66 CONSTELLATION ENERGY GENERATION, LLC BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, AND STN 50-455
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated May 24, 2024 (Agencywide Documents Access and Management System Accession No. ML24145A116), as supplemented by letter dated on December 10, 2024 (ML24345A147),
Constellation Energy Generation, LLC (CEG, the licensee), submitted a license amendment request (LAR) with proposed changes to the Technical Specifications (TSs) for Braidwood Station (Braidwood), Units 1 and 2, and Byron Station (Byron), Unit Nos. 1 and 2.
The licensees proposed changes to the TSs would remove extraneous details in several Limiting Conditions of Operations (LCOs) related to a specific software used in the power distribution monitoring system (PDMS), which would bring the TSs into closer alignment with NUREG-1431, Revision 5, Standard Technical Specifications - Westinghouse Plants. In addition, the licensee proposes to delete LCO 3.2.5, Departure from Nucleate Boiling Ratio (DNBR).
The supplemental letter dated December 10, 2024, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on July 9, 2024, (89 FR 56440).
2.0 REGULATORY EVALUATION
2.1
System Description
As described in a prior Safety Evaluation for Byron, Unit Nos. 1 and 2, dated February 13, 2001 (ML010510325), the Best Estimate Analyzer for Core Operations - Nuclear (BEACON') PDMS is a non-safety related system used to augment core power distribution surveillances. The BEACON' system was developed by Westinghouse to improve operational support for pressurized-water reactors (PWRs). It is a core monitoring and support package that uses Westinghouse standard instrumentation in conjunction with an analytical methodology for online generation of three-dimensional power distributions. The system provides core monitoring, core measurement reduction, core analysis, and core predictions. As further described in an NRC technical evaluation report evaluating the accuracy and reliability of BEACON', dated February 16, 1994 (ML19346E687), as part of the continuous core monitoring, the fuel and DNBR limits are calculated by BEACONTM PDMS using standard Westinghouse methods approved by the NRC.
The Departure from Nucleate Boiling Ratio (DNBR) is a safety limit used to analyze transient and accident conditions in PWRs. The DNBR indicates how close the reactor coolant is to transition boiling. Transition boiling reduces the heat transfer rate from the fuel. The reduced heat transfer rate results in an increase in fuel cladding surface temperature. The elevated surface temperatures that occur may cause fuel cladding damage or failure. A DNBR above 1.0 indicates that transition boiling is not likely to occur. During day-to-day operation of a PWR, fuel cladding damage is prevented using the limits on axial flux difference, quadrant power tilt ratio, heat flux hot channel factor, nuclear enthalpy rise hot channel factor, and control rod bank insertion.
2.2 Description of Proposed TS Changes The licensees proposed changes will remove extraneous details specifically related to the PDMS core monitoring system software from the TSs. Specifically, the proposed changes remove all PDMS references in the Braidwood and Byron TSs in the following LCOs:
LCO 3.1.4 - Rod Group Alignment Limits Removes the exception to the normal "time zero" for beginning the allowed outage time from the completion time (CT) associated with required actions (RAs) B.2 and C.2 reverting to the previous CT of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, respectively, with no dependence on PDMS operability. Additionally, RA B.4 is revised to replace the current determine action with a requirement to perform the Surveillance Requirements (SRs) that determine the referenced parameters of Heat Flux Hot Channel Factor and Nuclear Enthalpy Rise Hot Channel Factor. These SRs are SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1. This proposed change aligns the Braidwood and Byron TS with the Standard Technical Specifications (STS) in NUREG-1431. RA C.3 to restore rod(s) to within alignment limit when PDMS is OPERABLE is deleted. This proposed change also includes the removal of reference to RA C.3 from Condition D.
LCO 3.2.1 - Heat Flux Hot Channel Factor The proposed change adds a Note to Conditions A and B to ensure the respective RAs to perform SRs 3.2.1.1 and 3.2.1.2 are performed during each entry into the Condition.
Proposed change to the CTs for Condition A include added clarification that the RAs need to be performed after each FQC(Z) determination. This is consistent with STS NUREG-1431, LCO 3.2.1B. RAs B.3, B.4, and B.5 are revised to reflect the reduction of the maximum allowable power of the AFD limits, which is consistent with STS NUREG-1431, LCO 3.2.1B. The proposed change deletes SR 3.2.1.1 Note 2 and SR 3.2.1.2 Note 3. SR 3.2.1.1 Note 1 and SR 3.2.1.2 Note 1 are moved to the beginning of the section as a single generic note to the SRs section of LCO 3.2.1. SR 3.2.1.2 Note 2 includes an option to increase FQW(Z) by a factor of 1.02. SR 3.2.1.3 and SR 3.2.1.4 are deleted from this LCO. These changes restore the SRs to pre-BEACON implementation wording.
LCO 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor The current RA A.1 is revised to reflect restoring FNH to within the COLR limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (proposed RA A.1.1), or to reduce thermal power to <50% RTP (proposed RA A.1.2.1) and reduce the Power Range Neutron Flux - High to 55% RTP (proposed RA A.1.2.2). RAs A.2 and A.3 are updated to reflect completion of SR 3.2.2.1.
SR 3.2.2.1 Note and SR 3.2.2.2 are deleted.
LCO 3.2.4 - Quadrant Power Tilt Ratio (QPTR)
Reference to an inoperable PDMS is deleted from the LCO 3.2.4 Applicability section.
RA A.2 is revised to delete the following action, and reduce thermal power 3% from RTP for each 1% of QPTR >1.00. CTs A.4, A.5, and A.6 contain editorial changes in specification of the limit of RA A.1. These changes are consistent with NUREG-1431.
SR 3.2.4.1 Note 3 and SR 3.2.4.2 Note 2 are deleted. SR 3.2.4.1 and 3.2.4.2 are revised to remove the explicit numerical QPTR limit since it is defined in the LCO. These proposed changes to the SR are consistent with NUREG-1431.
TS 5.6.5 - Core Operating Limits Report (COLR)
LCO 3.2.5, Departure from Nucleate Boiling Ratio (DNBR) is deleted from the list of LCOs in Section 5.6.5.a. WCAP-12472-P-A is deleted from the list of analytical methods used in Section 5.6.5.b.
2.3 Regulatory Requirements, Licensing Information, Guidance Documents Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications, requires that the operating license of a nuclear power facility include TSs (10 CFR 50.36(b)),
which must contain specific categories of items (10 CFR 50.36(c)), including LCOs and administrative controls.
The regulations at 10 CFR 50.36(c)(2) require that TSs contain LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. 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 TSs until the LCO can be met. Typically, the TSs require restoration of equipment in a timeframe commensurate with its safety significance, along with other engineering considerations. A TS LCO for operation of a nuclear reactor must be established for each item meeting one or more criteria listed in 10 CFR 50.36(c)(2)(ii).
Criterion 2 (10 CFR 50.36(c)(2)(ii)(B)) requires a TS LCO 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.
The regulations at 10 CFR 50.36(c)(5) state, in part, that administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. The COLR is included in the TSs for Braidwood and Byron as an administrative control.
Requirements for instrumentation and the reactor protection system are found in the General Design Criteria (GDC) for Nuclear Power Plants, located at 10 CFR Part 50, Appendix A.
GDC 20, Protection system functions, requires a protection system designed to (1) automatically initiate the operation of appropriate systems to assure that specified acceptable fuel design limits are not exceeded because of anticipated operational occurrences; and (2) sense accident conditions and initiate the operation of systems and components important to safety.
3.0 TECHNICAL EVALUATION
The BEACON' PDMS does not have any direct inputs to the Reactor Trip System (RTS). The RTS is described in the Byron and Braidwood Updated Final Safety Analysis Report, Revision 19, Section 7.2.1.1 (ML22355A537), as the system which automatically keeps the reactor operating within a safe region by shutting down the reactor whenever the limits of the region are approached. The safe operating region is defined by several considerations such as mechanical/hydraulic limitations on equipment, and heat transfer phenomena. In the Safety Evaluation for Braidwood and Byron which approved the implementation of the BEACON' PDMS, dated February 13, 2001 (ML010510325), the NRC staff found that the proposed changes allow for the power distribution surveillances to be performed by [BEACON'] PDMS rather than using the movable incore detector system and the [BEACON'] PDMS does not provide any direct protection [RTS] or control function. The NRC staff thus finds that the removal of BEACON' PDMS will not affect any of the accident analyses in the Byron/Braidwood updated final safety analysis report, and that the RTS will continue to meet its design function as required by GDC 20. For this reason, the NRC staff finds this proposed change to be acceptable.
In the LAR, the licensee states that the process variables that provide initial conditions for accident or transient analysis, such as axial flux difference, quadrant power tilt ratio, heat flux hot channel factor, nuclear enthalpy rise hot channel factor, and control rod bank insertion, will continue to be monitored after the removal of PDMS from the TSs. Monitoring these redundant process variables will fully meet the requirements of Criterion 2 of 10 CFR 50.36(c)(2)(ii). In addition, the requirements of 10 CFR 50.36(c)(5) will continue to be met because only the analytical method that will no longer be used upon removal of the PDMS is being removed. The other analytical methods used to support the COLR continue to be used. Therefore, the NRC staff concludes that LCO 3.2.5 can be removed from the TSs. The removal of DNBR from the technical specifications is also consistent with NUREG-1431, Revision 5, which does not include DNBR in its standard technical specifications. For these reasons, the staff finds this proposed change to be acceptable.
3.1 Technical Conclusion The NRC staff reviewed the licensees proposed changes to remove extraneous references to the BEACON' PDMS and to delete LCO 3.2.5 from the TSs. Parameters required for accident and transient analyses will continue to be monitored, and the licensee will continue to meet the regulatory requirements of 10 CFR 50.36(c)(2). The proposed TS changes would not impact the licensees current compliance with GDC 20. Therefore, the NRC staff concludes that the licensees proposed TS changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendments on November 19, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments do not involve a significant hazards consideration, a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendments meet the eligibility criterion 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 Contributor: CPeabody, NRR NDenney, NRR MHamm, NRR M. Marshall, NRR Date: March 19, 2025
ML24352A075 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NRR/DSS/SNSB NAME JWiebe SRohrer (SLent for)
SMehta CPeabody DATE 12/13/2024 12/30/2024 01/07/2025 10/24/2024 OFFICE OGC - NLO NRR/DORL/LPL3/BC (A) NRR/DORL/LPL3/PM NAME MChwedczuk IBerrios (RKuntz for)
SWall DATE 01/29/2025 03/19/2025 03/19/2025