ML25098A308
| ML25098A308 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 05/28/2025 |
| From: | Samson Lee Plant Licensing Branch IV |
| To: | Gerfen P Pacific Gas & Electric Co |
| Lee S, 301-415-3158 | |
| References | |
| EPID L-2024-LLA-0176 | |
| Download: ML25098A308 (20) | |
Text
May 28, 2025 Ms. Paula Gerfen Senior Vice President, Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424
SUBJECT:
DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 250 AND 252 RE: REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-541 (EPID L-2024-LLA-0176)
Dear Ms. Gerfen:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 250 to Facility Operating License No. DPR-80 and Amendment No. 252 to Facility Operating License No. DPR-82 for the Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Diablo Canyon), respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 24, 2024.
The amendments revise Diablo Canyon TSs to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, which is an approved change to the Standard Technical Specifications.
P. Gerfen Copies of the related Safety Evaluation and Notices and Environmental Findings are also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Samson S. Lee, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323
Enclosures:
- 1. Amendment No. 250 to DPR-80
- 2. Amendment No. 252 to DPR-82
- 3. Safety Evaluation
- 4. Notices and Environmental Findings cc: Listserv
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 250 License No. DPR-80
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas and Electric Company (the licensee), dated December 24, 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 Facility Operating License No. DPR-80 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 250 are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Tony Nakanishi, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Facility Operating License No. DPR-80 and the Technical Specifications Date of Issuance: May 28, 2025 TONY NAKANISHI Digitally signed by TONY NAKANISHI Date: 2025.05.28 12:45:36 -04'00'
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 252 License No. DPR-82
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas and Electric Company (the licensee), dated December 24, 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 Facility Operating License No. DPR-82 is hereby amended to read as follows:
(2)
Technical Specifications (SSER 32, Section 8)* and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 252, are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 180 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Tony Nakanishi, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Facility Operating License No. DPR-82 and the Technical Specifications Date of Issuance: May 28, 2025 TONY NAKANISHI Digitally signed by TONY NAKANISHI Date: 2025.05.28 12:46:02 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 250 TO FACILITY OPERATING LICENSE NO. DPR-80 AND LICENSE AMENDMENT NO. 252 TO FACILITY OPERATING LICENSE NO. DPR-82 DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-275 AND 50-323 Replace the following pages of the Facility Operating License Nos. DPR-80 and DPR-82 and the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License No. DPR-80 REMOVE INSERT Facility Operating License No. DPR-82 REMOVE INSERT Technical Specifications REMOVE INSERT 3.7-19 3.7-19 3.7-22 3.7-22 3.7-24 3.7-24
Amendment No. 250 (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.
This 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 Pacific Gas and Electric Company is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 250 are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
(3)
Initial Test Program The Pacific Gas and Electric Company shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Pacific Gas and Electric Companys Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
- a.
Elimination of any test identified in Section 14 of PG&Es Final Safety Analysis Report as amended as being essential;
Amendment No. 252 (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.
This 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 Pacific Gas and Electric Company is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications (SSER 32, Section 8)* and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 252 are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
(3)
Initial Test Program (SSER 31, Section 4.4.1)
Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
CRVS 3.7.10 DIABLO CANYON - UNITS 1 & 2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
Two CRVS trains inoperable in MODE 5 OR 6, or during movement of recently irradiated fuel assemblies.
OR E.1 Suspend movement of recently irradiated fuel assemblies.
Immediately One or more CRVS trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of recently irradiated fuel assemblies.
F.
Two CRVS trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
F.1 Enter LCO 3.0.3.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRVS train for 15 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.2 Verify that each CRVS redundant fan is aligned to receive electrical power from a separate OPERABLE vital bus.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.3 Perform required CRVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with VFTP SR 3.7.10.4 Verify each CRVS train automatically switches into the pressurization mode of operation on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.5 Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.
In accordance with the Control Room Envelope Habitability Program 3.7-19 Unit 1 - Amendment No. 135,142,163,184,200,201, Unit 2 - Amendment No. 135,142,165,186,201,202, 250 252
ABVS 3.7.12 DIABLO CANYON - UNITS 1 & 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 This surveillance shall verify that each ABVS train is aligned to receive electrical power from a separate OPERABLE vital bus.
Operate each ABVS train for 15 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.7.12.2 Perform required ABVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP
NOTE-------------------------------
SR is not applicable to a specific ABVS train when that ABVS train is configured and performing its safety function.
SR 3.7.12.3 Verify each ABVS train actuates on an actual or simulated actuation signal and the system realigns to exhaust through the common HEPA filter and charcoal adsorber, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.7.12.4 Not Used.
SR 3.7.12.5 Not Used.
SR 3.7.12.6 Verifying that leakage through the ABVS Dampers M2A and M2B is less than or equal to 5 cfm when subjected to a Constant Pressure or Pressure Decay Leak Rate Test in accordance with ASME N510-1989. The test pressure for the leak rate test shall be based on a maximum operating pressure as defined in ASME N510-1989, of 8 inches water gauge.
In accordance with the Surveillance Frequency Control Program 3.7-22 Unit 1 - Amendment No. 135,163,200,219, Unit 2 - Amendment No. 135,165,201,221, 250 252
FHBVS 3.7.13 DIABLO CANYON - UNITS 1 & 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each FHBVS train for 15 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.7.13.2 Perform required FHBVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.13.3 Verify each FHBVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.7.13.4 Verify one FHBVS train can maintain a pressure
-0.125 inches water gauge with respect to atmospheric pressure during the post accident mode of operation.
In accordance with the Surveillance Frequency Control Program SR 3.7.13.5 Verify damper M-29 can be closed, except if the damper is locked, sealed, or otherwise secured in the closed position.
In accordance with the Surveillance Frequency Control Program 3.7-24 Unit 1 - Amendment No. 135 142 200 Unit 2 - Amendment No. 135 142 201 250 252
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 250 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 252 TO FACILITY OPERATING LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-275 AND 50-323 Application (i.e., initial and supplements)
Safety Evaluation Date December 24, 2024, Agencywide Documents Access and Management System (ADAMS)
Accession No. ML24359A003 May 28, 2025 Principal Contributor to Safety Evaluation Mark Schwieg
1.0 PROPOSED CHANGE
S Pacific Gas and Electric Company (PG&E, the licensee) requested changes to the technical specifications (TSs) for Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Diablo Canyon) by license amendment request (LAR, application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendments under the Consolidated Line Item Improvement Process. The proposed amendments are based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (ML19240A315), and the associated NRC staff safety evaluation (SE) of TSTF-541 (ML19323E926).
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications, states that each operating license issued by the Commission includes TSs and that TSs include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings, (2) limiting conditions for operation (LCOs), (3) surveillance requirements (SRs), (4) design features, (5) administrative controls, (6) decommissioning, (7) initial notification, and (8) written reports. LCOs identify the lowest functional capability or performance levels of equipment required for safe operation of the facility. SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
Several existing Diablo Canyon SRs require the licensee to verify that each train of specified trains actuates on an actual or simulated actuation signal. When the trains actuate, valves and dampers within the trains will, if needed, reposition to their actuated position, which is the position appropriate to respond to the transient or accident that caused the actuation. The proposed amendments would eliminate the need to verify that a damper or valve has repositioned if the damper or valve is secured in its actuated position by adding a phrase to each SR as described in section 1.2 of this SE.
The proposed amendments are based on TSTF-541, Revision 2, and the associated NRC staff SE of TSTF-541. Section 1.1 of the NRC staffs SE of TSTF-541 discusses the reason for the proposed changes.
1.1 System Descriptions The Diablo Canyon control room ventilation system (CRVS) provides a protected environment from which operators can control the units from the common control room following an uncontrolled release of radioactivity, chemicals, or toxic gas. The CRVS consists of two independent, redundant trains that recirculate and filter the control room air (one train from each unit). Each CRVS train consists of a heater, a prefilter, a high efficiency particulate air (HEPA) filter, an activated charcoal adsorber section for removal of gaseous activity (principally iodine),
and one pressurization supply fan, one filter booster fan, and one main supply fan. Ductwork, dampers, and instrumentation also form part of the system. The CRVS is an emergency system, parts of which may also operate during normal unit operations. Upon receipt of an actuating signal, the normal air supply to the control room is isolated, and the stream of outside ventilation air from the pressurization system and recirculated control room air is passed through the system filter. The pressurization system draws outside air from either the north end or the south end of the Turbine Building based upon the wind direction or the absence of releases at the inlet. The prefilters remove any large particles in the air to prevent excessive loading of the HEPA filters and charcoal adsorbers. The purpose of SR 3.7.10.4 is to verify that each train/subsystem starts and operates on an actual or simulated actuation signal.
The Diablo Canyon auxiliary building ventilation system (ABVS) filters air from the area of the active emergency core cooling system (ECCS) components during the recirculation phase of a loss-of-coolant accident. The ABVS, in conjunction with other normally operating systems, also provides environmental control of temperature and humidity in the ECCS pump room area and the auxiliary building. Each ABVS train is powered by a separate vital bus and contains a separate exhaust fan. These trains both provide airflow through a single roughing and HEPA filter, which is common to both trains for normal operations; and a single roughing filter, HEPA filter, and charcoal adsorber bank and a single manually initiated heater are common to both trains for emergency operations. Ductwork, valves or dampers, and instrumentation also form part of the system. If a safety injection signal is generated, the system will automatically realign such that all exhaust flow from the ECCS pump rooms passes through the common HEPA filter/charcoal adsorber bank prior to being exhausted to atmosphere. Whenever a safety injection signal is generated, the operator can manually energize the heater from the control room. The purpose of SR 3.7.12.3 is to verify proper actuation of all train components, including dampers, on an actual or simulated actuation signal.
The Diablo Canyon fuel handling building ventilation system (FHBVS) filters airborne radioactive particulates from the area of the fuel pool following a fuel handling accident. The FHBVS provides environmental control of temperature and humidity in the fuel pool area and for the auxiliary feedwater pump motors. The FHBVS consists of two independent and redundant trains. Each FHBVS train consists of an exhaust prefilter, a HEPA filter, an activated charcoal adsorber section for removal of gaseous activity (principally iodine), and an exhaust fan.
Ductwork, valves or dampers, and instrumentation also form part of the system, as well as demisters, functioning to reduce the relative humidity of the airstream. The system initiates filtered ventilation of the fuel handling building following receipt of a high radiation signal or loss of the normal exhaust fan E-4. The FHBVS is a standby system, parts of which may also be operated during normal plant operations. Upon receipt of the actuating signal, normal air discharges from the fuel handling building are isolated, the normal exhaust fan shuts down, the vital exhaust fans start, and stream of ventilation air is discharged through the system filter trains. The purpose of SR 3.7.13.3 is to verify proper actuation of all train components, including dampers, on an actual or simulated actuation signal. The purpose of SR 3.7.13.5 is to ensure that the system is functioning properly by operating the FHBVS filter bypass damper (damper M-29).
1.2 Description of Proposed TS Changes to Adopt TSTF-541 In accordance with NRC staff-approved TSTF-541, the licensee proposed to revise certain SRs by adding exceptions to the SRs for automatic valves or dampers that are locked, sealed, or otherwise secured in the actuated position. The proposed revisions, therefore, allow the licensee to meet the LCOs without having to test for actuation those values or dampers that are already secured in the actuated position. Specifically, the licensee proposed the following changes to adopt TSTF-541. The proposed new text is shown in italics.
SR 3.7.10.4 Verify each CRVS train automatically switches into the pressurization mode of operation on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
SR 3.7.12.3 Verify each ABVS train actuates on an actual or simulated actuation signal and the system realigns to exhaust through the common HEPA filter and charcoal adsorber, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
SR 3.7.13.3 Verify each FHBVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
SR 3.7.13.5 Verify damper M-29 can be closed, except if the damper is locked, sealed, or otherwise secured in the closed position.
1.3 Additional Proposed TS Changes In addition to the TS changes proposed consistent with TSTF-541 and discussed in section 1.2 of this SE, the licensee proposed the following variations.
1.3.1 Editorial Variations The licensee noted that Diablo Canyon TSs have different numbering, system titles, and nomenclature than the standard technical specifications (STSs).
1.4 Editorial Change to Facility Operating License No. DPR-80 In reviewing the LAR, the NRC staff identified a format error in Facility Operating License No.
DPR-80 for Diablo Canyon, Unit 1. The format error is on page 3 in License Conditions 2.B.(4) and 2.B.(5), which should be aligned with License Conditions 2.B.(1) through 2.B.(3) located on page 2 of Facility Operating License No. DPR-80. This format error was inadvertently introduced in Amendment No. 218, dated July 1, 2015 (ML15162A882).
2.0 REGULATORY EVALUATION
The regulation under 10 CFR 50.36(b) states that:
Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information.] The Commission may include such additional technical specifications as the Commission finds appropriate.
Additionally, under 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. The considerations for issuance of operating licenses in 10 CFR 50.57(a)(3) provide, in part, that there must be reasonable assurance that the activities authorized will not endanger the health and safety of the public. The LAR involves changes to SRs, which are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
Accordingly, to be acceptable, the SRs, as amended to no longer require the verification of valves and dampers that are already in, and secured in, their actuated positions, must continue to provide reasonable assurance that the LCOs will be met and that the health and safety of the public will not be endangered.
The NRC staffs 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), dated 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 NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, dated September 2021 (ML21259A155 and ML21259A159, respectively), as modified by NRC-approved travelers.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-541 The NRC staff compared the licensees proposed TS changes described in section 1.2 of this SE against the changes approved in TSTF-541. In accordance with SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-541 are applicable to the Diablo Canyon TSs because Diablo Canyon, Units 1 and 2 are Westinghouse pressurized-water reactors (PWRs) and the NRC staff approved the TSTF-541 changes for Westinghouse PWR designs. Therefore, the NRC staff concludes that the licensees proposed changes to the Diablo Canyon TSs described in section 1.2 of this SE are consistent with TSTF-541.
As defined in Diablo Canyon TS 1.1, a system, subsystem, train, component, or device shall be operable or have operability when:
it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
The SRs, as proposed to be amended, would exclude the need to verify the actuation of dampers and valves that do not, in fact, actuate (e.g., change position) in response to an actuation signal. The licensees LAR contains the following statements:
While the proposed exceptions permit automatic valves and dampers that are locked, sealed, or otherwise secured in the actuated position to be excluded from the SR in order to consider the SR met, the proposed changes will not permit a system that is made inoperable by locking, sealing, or otherwise securing an automatic valve or damper in the actuated position to be considered operable. As stated in the SR 3.0.1 Bases, Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when: a. The systems or components are known to be inoperable, although still meeting the SRs.
PG&E acknowledges that under the proposed change, the affected valves and dampers may be excluded from the SR when locked, sealed or otherwise secured in the actuated position. However, if the safety analysis assumes movement from the actuated position following an event, or the system is rendered inoperable by locking, sealing, or otherwise securing the valve or damper in the actuated position, then the system cannot perform its specified safety function and is inoperable regardless of whether the SR is met.
PG&E acknowledges for components for which the SR allowance can be utilized, the SR must be verified to have been met within its required Frequency after removing the valve or damper from the locked, sealed or otherwise secured status. If the SR exception is utilized to not test the actuation of a valve or damper and the specified Frequency of the SR is exceeded without testing the component, the SR must be performed on the component when it is returned to service in order to meet the SR.
Given the above statements provided on the docket for this LAR, the NRC staff determined that there is reasonable assurance that the licensee will continue to properly control affected equipment in accordance with existing regulations and requirements when using the exceptions proposed to be added to the respective SRs.
The SRs, as proposed to be amended, will continue to require the licensee to verify that valves and dampers that must actuate perform their safety functions and support functions by being able to change position. However, the NRC staff finds that it is not necessary to verify the actuation of valves and dampers that are already in their actuated positions, and are locked, sealed, or otherwise secured in those positions Therefore, the NRC staff determined that the Diablo Canyon TSs, as amended, will continue to meet 10 CFR 50.36(c)(3) because the SRs, as amended, will continue to ensure that the necessary quality of systems and components is maintained and that the LCOs will be met.
Thus, the proposed changes will continue to meet the requirements of 10 CFR 50.36(c)(3) as discussed in Section 3.0 of the NRC staffs SE of TSTF-541 and will not endanger the health and safety of the public.
3.2 Additional Proposed TS Changes 3.2.1 Editorial Variations The licensee noted that the Diablo Canyon TSs have different numbering, system titles, and nomenclature than the STS. In addition, the change to correct a formatting error on page 3 of Facility Operating License No. DPR-80 for Diablo Canyon, Unit 1 only changes the alignment of certain license conditions. The NRC staff finds that the different TS numbering, system titles, and nomenclature changes and the alignment changes are acceptable because they do not substantively alter TS requirements.
3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are therefore acceptable.
4.0 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.
NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 250 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 252 TO FACILITY OPERATING LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-275 AND 50-323 Application (i.e., initial and supplements)
Safety Evaluation Date
December 24, 2024, Agencywide Documents Access and Management System (ADAMS)
Accession No. ML24359A003 May 28, 2025
1.0 INTRODUCTION
Pacific Gas and Electric Company (the licensee) requested changes to the technical specifications for Diablo Canyon Nuclear Power Plant, Units 1 and 2 by license amendment request (LAR, application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendments under the Consolidated Line Item Improvement Process. The proposed amendments are based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (ML19240A315), and the associated NRC staff safety evaluation of TSTF-541 (ML19323E926).
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the California State official was notified of the proposed issuance of the amendments on March 12, 2025. The State official had no comments.
3.0 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 and change surveillance requirements. 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, as published in the Federal Register on March 18, 2025 (90 FR 12571), 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.
- concurrence by email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC*
OGC NAME SLee PBlechman SMehta JWachutka DATE 4/8/2025 4/17/2025 3/17/2025 4/29/2025 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME TNakanishi SLee DATE 5/28/2025 5/28/2025