ML23044A105
| ML23044A105 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/13/2023 |
| From: | James Kim NRC/NRR/DORL/LPL1 |
| To: | Carr E Public Service Enterprise Group |
| References | |
| EPID L-2022-LLA-0133 | |
| Download: ML23044A105 (22) | |
Text
March 13, 2023 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 ISSUANCE OF AMENDMENT NOS. 345 AND 326 RE: RELOCATE TECHNICAL SPECIFICATIONS REQUIREMENTS FOR REACTOR HEAD VENTS TO TECHNICAL REQUIREMENTS MANUAL (EPID L-2022-LLA-0133)
Dear Mr. Carr:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 345 and 326 to Renewed Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station, Unit Nos. 1 and 2, respectively. These amendments consist of changes to the technical specifications (TSs) in response to your application dated August 31, 2022.
The amendments relocated TS 3/4.4.12 limiting condition for operation, associated Action Statements, and Surveillance Requirements for the Reactor Coolant System Head Vents from the TS to the Technical Requirements Manual for the Salem Nuclear Generating Station, Unit Nos. 1 and 2.
E. Carr A copy of the related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
James S. Kim, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosures:
- 1. Amendment No. 345 to DPR-70
- 2. Amendment No. 326 to DPR-75
- 3. Safety Evaluation cc: Listserv PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 345 Renewed License No. DPR-70 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees), dated August 31, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-70 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 345, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: March 13, 2023 Hipolito J.
Gonzalez Digitally signed by Hipolito J. Gonzalez Date: 2023.03.13 13:22:09 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 345 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following page of Renewed Facility Operating License No. DPR-70 with the attached revised page as indicated. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 3
3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert V
V XII XII 3/4 4-35 3/4 4-35 Renewed License No. DPR-70 Amendment No. 345 (4)
PSEG Nuclear 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; (5)
PSEG Nuclear 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 (6)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 345, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.
(3)
Deleted Per Amendment 22, 11-20-79 (4)
Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this renewed license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this renewed license.
(5)
PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS Normal Operation................................................................................................ 3/4 4-1 Hot Standby......................................................................................................... 3/4 4-2 Hot Shutdown...................................................................................................... 3/4 4-3 Cold Shutdown.................................................................................................. 3/4 4-3b 3/4.4.2.1 SAFETY VALVES - SHUTDOWN.......................................................................... 3/4 4-4 3/4.4.2.2 SAFETY VALVES - OPERATING........................................................................ 3/4 4-4a 3/4.4.3 RELIEF VALVES.................................................................................................... 3/4 4-5 3/4.4.4 PRESSURIZER...................................................................................................... 3/4 4-6 3/4.4.5 STEAM GENERATOR (SG) TUBE INTEGRITY................................................... 3/4 4-7 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection System................................................................................ 3/4 4-14 Operational Leakage......................................................................................... 3/4 4-15 Primary Coolant System Pressure Isolation Valves........................................ 3/4 4-16a 3/4.4.7 DELETED 3/4.4.8 SPECIFIC ACTIVITY........................................................................................... 3/4 4-20 3/4.4.9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System.................................................................................... 3/4 4-24 Pressurizer......................................................................................................... 3/4 4-29 Overpressure Protection Systems..................................................................... 3/4 4-30 3/4.4.10 DELETED............................................................................................................ 3/4 4-32 3/4.4.11 INTENTIONALLY BLANK................................................................................... 3/4 4-34 3/4.4.12 DELETED............................................................................................................ 3/4 4-35 SALEM - UNIT 1 V
Amendment No. 345
INDEX BASES SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE AND 3/4.3.2 ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION.......................................................................... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION..................................................B 3/4 3-1c 3/4.3.4 TURBINE OVERSPEED PROTECTION............................................. B 3/4 3-4 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.................................................................................... B 3/4 4-1 3/4.4.2 SAFETY VALVES................................................................................B 3/4 4-1a 3/4.4.3 RELIEF VALVES.................................................................................B 3/4 4-1a 3/4.4.4 PRESSURIZER................................................................................... B 3/4 4-2 3/4.4.5 STEAM GENERATOR (SG) TUBE INTEGRITY................................. B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE........................................B 3/4 4-4a 3/4.4.7 DELETED 3/4.4.8 SPECIFIC ACTIVITY........................................................................... B 3/4 4-5 3/4.4.9 PRESSURE/TEMPERATURE LIMITS............................................. B 3/4 4-6 3/4.4.10 DELETED.............................................................................................B 3/4 4-17 3/4.4.11 BLANK..................................................................................................B 3/4 4-17 3/4.4.12 DELETED..................................................B 3/4 4-17 SALEM - UNIT 1 XII Amendment No. 345
3/4.4.12 DELETED SALEM - UNIT 1 3/4 4-35 Amendment No. 345 PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 326 Renewed License No. DPR-75 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees), dated August 31, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 326, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: March 13, 2023 Hipolito J.
Gonzalez Digitally signed by Hipolito J. Gonzalez Date: 2023.03.13 13:22:37 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 326 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following page of Renewed Facility Operating License No. DPR-75 with the attached revised page as indicated. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 3
3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert V
V XII XII 3/4 4-34 3/4 4-34 Renewed License No. DPR-75 Amendment No. 326 (3)
PSEG Nuclear 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; (4)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source or 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; (5)
PSEG Nuclear 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 (6)
PSEG Nuclear 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 PSEG Nuclear LLC is authorized to operate the facility at steady state reactor core power levels not in excess of 3459 megawatts (thermal).
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 326, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation............................................................... 3/4 4-1 Hot Standby.......................................................................................... 3/4 4-2 Hot Shutdown....................................................................................... 3/4 4-3 Cold Shutdown............................................................................... 3/4 4-4a 3/4.4.2 SAFETY VALVES - SHUTDOWN......................................................... 3/4 4-5 3/4.4.3 SAFETY VALVES - OPERATING......................................................... 3/4 4-6 3/4.4.4 PRESSURIZER..................................................................................... 3/4 4-7 3/4.4.5 RELIEF VALVES................................................................................... 3/4 4-8 3/4.4.6 STEAM GENERATOR (SG) TUBE INTEGRITY.................................... 3/4 4-9 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection System................................................................. 3/4 4-16 Operational Leakage.......................................................................... 3/4 4-17 3/4.4.8 DELETED 3/4.4.9 SPECIFIC ACTIVITY........................................................................... 3/4 4-23 3/4.4.10 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System..................................................................... 3/4 4-27 Pressurizer......................................................................................... 3/4 4-30 Overpressure Protection Systems...................................................... 3/4 4-31 3/4.4.11 DELETED........................................................................................... 3/4 4-33 3/4.4.12 DELETED........................................................................................... 3/4 4-34 SALEM - UNIT 2 V
Amendment No. 326
INDEX BASES SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE AND AND 3/4.3.2 ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION........................................................................ B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.... B 3/4 3-1c 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.................................................................................. B 3/4 4-1 3/4.4.2 and SAFETY VALVES.............................................................................. B 3/4 4-2 3/4.4.3 3/4.4.4 PRESSURIZER................................................................................. B 3/4 4-2 3/4.4.5 RELIEF VALVES............................................................................... B 3/4 4-2 3/4.4.6 STEAM GENERATOR (SG) TUBE INTEGRITY................................ B 3/4 4-3 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE...................................... B 3/4 4-4 3/4.4.8 DELETED 3/4.4.9 SPECIFIC ACTIVITY......................................................................... B 3/4 4-6 3/4.4.10 PRESSURE/TEMPERATURE LIMITS............................................... B 3/4 4-7 3/4.4.11 DELETED........................................................................................ B 3/4 4-18 3/4.4.12 DELETED........................................................................................ B 3/4 4-18 SALEM - UNIT 2 XII Amendment No. 326
3/4.4.12 DELETED SALEM - UNIT 2 3/4 4-34 Amendment No. 326 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 345 AND 326 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By application dated August 31, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22249A228), PSEG Nuclear LLC (the licensee) submitted a license amendment request for the Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem).
The amendment proposed to relocate the Technical Specifications (TS) 3/4.4.12 Limiting Condition for Operation (LCO), associated Action Statements, and Surveillance Requirements (SRs) for the Reactor Coolant System Head Vents from the Salem TS to the Technical Requirements Manual (TRM).
2.0 REGULATORY EVALUATION
2.1
System Description
The Reactor Head Vents (RHVs) are one of three principal high points in the Reactor Coolant System (RCS). The RHVs are provided to exhaust non-condensable gases and/or steam from the RCS which could inhibit natural circulation core cooling following any event requiring long-term cooling, such as a loss of coolant accident. Their function and capabilities conform to the post-TMI [Three Mile Island] requirements discussed in NUREG-0737, Clarification of TMI
[Action Plan Requirements, (ML102560051). The RHVs are also used to vent the RCS during normal RCS fill and vent operations following completion of a refueling outage.
Four individual vent valves are arranged in a redundant series-parallel grouping that is cross-tied to form four distinct vent paths. The vent paths are designed to minimize the probability of inadvertent or irreversible actuation while also ensuring that a single failure of a vent valve or power supply will not prevent establishment of a vent path. The vent line downstream of the valves discharges to the pressurizer relief tank. The vent piping and associated vent valves are stainless steel and are classified as Seismic Category I and Nuclear Safety class 2. The RHVs are located behind the pressurizer missile shield to prevent inadvertent damage from a missile in the pressurizer area.
The RHVs are not credited for any design basis accident mitigation function in Chapter 15 of the facilitys Updated Final Safety Analysis Report (UFSAR). There is no automated actuation or permissive logic associated with the RHVs and each of the four valves are remote-manually operated by the reactor operator, using individual key lock switches in the main control room after an event has occurred, and is only required when there is indication that natural circulation has degraded or is not occurring. Open and Close indications for each of the solenoid valves are provided in the main control room with both visual and audible alarms.
2.2 Description of Changes The current TS associated with this change is TS 3/4.4.12, Head Vents.
The licensee has proposed the following changes.
Section 3/4.4.12 of the TS Index page - HEAD VENTS will be replaced with DELETED.
Section 3/4.4.12 of the TS Bases Index - REACTOR VESSEL HEAD VENT will be replaced with DELETED.
All LCOs, Actions, and SRs will be deleted in their entirety in TS Section 3/4.4.12. The sections title HEAD VENTS will be replaced with DELETED.
All the text within the associated TS Bases will be deleted in its entirety. The sections titled HEAD VENTS will be replaced with DELETED.
These specifications would be relocated in their entirety to the TRM without change to the provisions currently contained within these specifications. The Bases associated with these TS would also be relocated to the TRM to support the proposed revision. As part of the relocation, associated SRs would be modified to remove references to the subject TS.
2.3 Applicable Regulatory Requirements On July 22, 1993, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued a Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors (Final Policy Statement) (58 FR 39132). The Final Policy Statement encouraged licensees to implement a voluntary program to update their TSs to be consistent with improved vendor-specific standard technical specifications (STSs) issued by the NRC. In the Final Policy Statement, the NRC developed criteria to determine which of the TS requirements should be retained and which requirements could be relocated to licensee-controlled documents. The four screening criteria contained in the Final Policy Statement were subsequently incorporated into the regulations by an amendment to 10 CFR 50.36(c)(2)(ii) (60 FR 36953). As discussed in the Federal Register notice for the final rule dated July 19, 1995 (60 FR 36955):
LCOs [limiting conditions for operation] that do not meet any of the criteria, and their associated actions and surveillance requirements, may be proposed for relocation from the technical specifications to licensee-controlled documents, such as the FSAR [Final Safety Analysis Report]. The criteria may be applied to either standard or custom technical specifications.
The regulations in 10 CFR 50.36 establishes the regulatory requirements related to the contents of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) SRs; (4) design features; and (5) administrative controls.
The regulation does not specify the particular requirements to be included in a plants TSs. The regulation in 10 CFR 50.36(c)(2)(i) states, in part:
Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the LCO can be met.
The regulations in 10 CFR 50.36(c)(2)(ii) list the following four criteria that require the establishment of an LCO:
a.
Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
b.
Criterion 2: 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.
c.
Criterion 3: A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
d.
Criterion 4: A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
TS requirements which fall within or satisfy any of the criteria in 10 CFR 50.36(c)(2)(ii) must be retained in the TS.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensees submittal and evaluated the RHV functions to determine if they meet any of the four criteria contained in 10 CFR 50.36(c)(2)(ii).
In comparing the functions of the RHV to the 10 CFR 50.36(c)(2)(ii) criteria, the NRC staff found the following:
1.
The RHVs are not installed instrumentation that is used to detect and indicate in the control room a significant abnormal degradation of the reactor coolant pressure boundary. Therefore, criterion 1 does not require the RHVs to be included in the TS.
2.
The RHVs do not comprise a process variable that is an initial condition of a DBA or transient analysis that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier. The RHVs are not credited in any analyzed UFSAR Chapter 15 event for protecting a fission product barrier. Therefore, criterion 2 is not satisfied as a basis for TS inclusion.
3.
Although the RHVs may be used to assist in creating conditions conducive to natural circulation, they are not components that are part of the primary success path and which function to mitigate a DBA or transient that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier. Therefore, the RHVs do not satisfy criterion 3.
4.
The design of Westinghouse pressurized-water reactors is such that a buildup of noncondensable gases or steam within the primary system to an extent to inhibit natural circulation core cooling is unlikely. Inadvertent opening of the RHVs would result in a restricted loss of primary coolant based on the size and restricted design of the vent path. The RHVs PRA assessment with respect to multiple spurious openings and fire safe shutdown determined that the risk contribution of these failures in the head vent system is very small and is not a primary contributor to risk. Therefore, the systems operating experience and its probabilistic safety assessment has not shown it to be significant to public health and safety. Therefore, criterion 4 does not require inclusion in the TS.
In addition, the NRC staff notes that the licensee proposes to relocate the TS and Bases described in section 2.2 of this SE to the TRM which is a 10 CFR 50.59 controlled document that provides an appropriate level of review and approval for the revision of requirements that are important to safety but do not satisfy the criteria of 10 CFR 50.36(c)(2)(ii) for TS requirements. The proposed revision would maintain an appropriate level of control of the relocated requirements and are consistent with NUREG-1431, Standard Technical Specifications - Westinghouse Plants, which does not contain requirements for the TS proposed for relocation.
The NRC staff finds that since the RHV functions do not meet the criteria in 10 CFR 50.36(c)(2)(ii) requiring a TS LCO, the RHV TS may be relocated to the TRM, and any subsequent changes will be adequately controlled by the provisions of 10 CFR 50.59. These provisions will continue to be implemented by appropriate station procedures (i.e., operating procedures, maintenance procedures, surveillance and testing procedures, and work control procedures). The staff also finds that the relocation of the RHV TS would align the Salem TS with NUREG-1431.
Additionally, since the request does not result in any physical change to the plant or the manner in which the plant is operated or maintained, the NRC staff finds that there is reasonable assurance that the proposed changes do not diminish the level of safety ensured by operation in accordance with the TS.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New Jersey State official was notified of the proposed issuance of the amendment on February 23, 2023. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change SRs.
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 NSHC, published in the Federal Register on November 1, 2022 (87 FR 65834), and there were no public comments on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: D. Scully, NRR Date: March 13, 2023
ML23044A105 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DSS/SCPB/BC NAME JKim KEntz BWittick DATE 2/13/2023 2/13/2023 2/4/2023 OFFICE NRR/DSS/SNSB/BC NRR/DSS/STSB/BC OGC - NLO NAME DWoodyatt (A)
VCusumano AGhoshNaber DATE 2/22/2023 2/14/2023 2/28/2023 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME HGonzalez JKim DATE 3/13/2023 3/13/2023