ML24099A223
| ML24099A223 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/12/2024 |
| From: | Mahesh Chawla Plant Licensing Branch IV |
| To: | Schuetz R Energy Northwest |
| Chawla M | |
| References | |
| EPID L-2023-LLA-0128 | |
| Download: ML24099A223 (11) | |
Text
June 12, 2024 Robert Schuetz Chief Executive Officer Energy Northwest MD 1023 76 North Power Plant Loop P.O. Box 968 Richland, WA 99352
SUBJECT:
COLUMBIA GENERATING STATION - ISSUANCE OF AMENDMENT NO. 275 TO ADOPT TSTF-230, REVISION 1, ADD NEW CONDITION B TO LCO 3.6.2.3, RHR SUPPRESSION POOL COOLING (EPID L-2023-LLA-0128)
Dear Robert Schuetz:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 275 to Renewed Facility Operating License No. NPF-21 for the Columbia Generating Station (Columbia). The amendment consists of changes to the Technical Specifications (TS) in response to your application dated August 29, 2023.
The amendment modifies Columbia TS 3.6.2.3, Residual Heat Removal (RHR) Suppression Pool Cooling, to allow two RHR suppression pool cooling subsystems to be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The amendment is consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-230, Revision 1, Add New Condition B to LCO [Limiting Conditions of Operation] 3.6.2.3, RHR Suppression Pool Cooling.
R. Schuetz A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosures:
- 1. Amendment No. 275 to NPF-21
- 2. Safety Evaluation cc: Listserv ENERGY NORTHWEST DOCKET NO. 50-397 COLUMBIA GENERATING STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 275 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Energy Northwest (the licensee), dated August 29, 2023, 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-21 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. 275 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-21 and the Technical Specifications Date of Issuance: June 12, 2024 Jennivine K.
Rankin Digitally signed by Jennivine K. Rankin Date: 2024.06.12 10:02:11 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 275 RENEWED FACILITY OPERATING LICENSE NO. NPF-21 COLUMBIA GENERATING STATION DOCKET NO. 50-397 Replace the following pages of Renewed Facility Operating License No. NPF-21 and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT Technical Specification REMOVE INSERT 3.6.2.3-1 3.6.2.3-1
Renewed License No. NPF-21 Amendment No. 275 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 275 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
a.
For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.
(3)
Deleted.
(4)
Deleted.
(5)
Deleted.
(6)
Deleted.
(7)
Deleted.
(8)
Deleted.
(9)
Deleted.
(10)
Deleted.
(11)
Deleted.
(12)
Deleted.
(13)
Deleted.
RHR Suppression Pool Cooling 3.6.2.3 Columbia Generating Station 3.6.2.3-1 Amendment No. 149,169,225,230,236 245 270 275 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 Two RHR suppression pool cooling subsystems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression pool cooling subsystem inoperable.
A.1 Restore RHR suppression pool cooling subsystem to OPERABLE status.
7 days OR In accordance with the Risk Informed Completion Time Program B. Required Action and associated Completion Time of Condition A not met.
B.1
NOTE--------------
LCO 3.0.4.a is not applicable when entering MODE 3.
Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. Two RHR suppression pool cooling subsystems inoperable.
C.1 Restore one RHR suppression pool cooling subsystem to OPERABLE status.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. Required Action and associated Completion Time of Condition C not met.
D.1 Be in MODE 3.
AND D.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 275 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397
1.0 INTRODUCTION
By application dated August 29, 2023 (Agencywide Documents Access and Management System Accession No. ML23241B044), Energy Northwest (the licensee) requested changes to the Technical Specifications (TSs) for the Columbia Generating Station (Columbia).
The proposed amendment would revise Columbia TS 3.6.2.3, Residual Heat Removal (RHR)
Suppression Pool Cooling, to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-230, Revision 1, Add New Condition B to LCO [Limiting Condition for Operation] 3.6.2.3, RHR Suppression Pool Cooling (ML040570110). The licensees proposed change would modify Columbia TS 3.6.2.3 to allow up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> be given to restore one RHR suppression pool cooling subsystem to operable status in the event that two RHR suppression pool cooling subsystems are inoperable. There are no variations from TSTF-230 in the proposed Columbia TS changes.
In the application, the licensee refers to TSTF-230-A as a basis for the requested amendment.
The NRC staff notes that the -A designation added to TSTF-230 is an industry convention used to indicate that the traveler has been approved by the U.S. Nuclear Regulatory Commission (NRC, the Commission). TSTF-230 and TSTF-230-A are the same document; however, since TSTF-230-A is not an NRC designation, this safety evaluation (SE) refers to the TSTF change traveler as TSTF-230.
2.0 REGULATORY EVALUATION
2.1 Description of RHR Suppression Pool Cooling The licensee provided the following information on the description of the RHR suppression Pool Cooling:
There are two RHR suppression pool cooling subsystems, each containing a pump and a heat exchanger and is manually initiated and independently controlled. The two RHR suppression pool cooling subsystems perform the suppression pool cooling function by circulating water from the suppression pool through the RHR heat exchangers and returning it to the suppression pool.
Standby service water, circulating through the tube side of the heat exchangers, exchanges heat with the suppression pool water and discharges this heat to the ultimate heat sink.
Following a design-basis accident (DBA), the RHR suppression pool cooling system removes heat from the suppression pool. The suppression pool is designed to absorb the sudden input of heat from the primary system. In the long term, the pool continues to absorb residual heat generated by fuel in the reactor core. Some means must be provided to remove heat from the suppression pool so that the temperature inside the primary containment remains within design limits. This function is provided by two redundant RHR suppression pool cooling subsystems.
The heat removal capability of one RHR subsystem is sufficient to meet the overall DBA pool cooling requirement to limit peak temperature to 2200F
[degrees Fahrenheit] for loss of coolant accidents (LOCAs) and transient events such as a turbine trip without bypass or a stuck open safety/relief valve (SRV).
SRV leakage and Reactor Core Isolation Cooling (RCIC) System testing increase suppression pool temperature more slowly. The RHR suppression pool cooling system is also used to lower the suppression pool water bulk temperature following such events.
2.2 Proposed TS Changes to Adopt TSTF-230 Currently, TS 3.6.2.3 requires two RHR suppression pool cooling subsystems to be operable in Modes 1, 2, and 3, and the Actions table contains three Conditions. Condition A applies when one RHR suppression pool cooling subsystem is inoperable. Condition B applies when the Required Action and associated Completion Time of Condition A are not met. Condition C applies when two RHR suppression pool cooling subsystems are inoperable. The Required Action and associated Completion Time for Condition C requires the unit to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (i.e., Required Action C.1) and in Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (i.e., Required Action C.2).
Consistent with NRC-approved TSTF-230, Revision 1, the licensee proposed changes that would revise the TS related to RHR suppression pool cooling to allow two RHR suppression pool cooling subsystems to be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Specifically, the licensee proposed the following changes to TS 3.6.2.3 Actions:
Revise Required Action for Condition C to remove requirements for Mode changes and add requirements to restore one RHR suppression pool cooling subsystem to operable status (Required Action C.1) with a Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Add new Condition D that applies when the Required Action and associated Completion Time of Condition C is not met. The Required Action and associated Completion Time for Condition D require the unit to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (i.e., Required Action D.1) and in Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (i.e., Required Action D.2).
TSTF-230, Revision 1, was submitted to the NRC on June 15, 1999, and was made available for plant-specific adoption via incorporation into Revision 2 of the Standard TSs (NUREG-1434, Standard Technical Specification General Electric Plants, BWR [Boiling Water Reactor]/6) on June 30, 2001 (Package ML011780537).
2.3 Applicable Regulatory Requirements Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(c)(2) requires that TSs include LCOs. Per 10 CFR 50.36(c)(2)(i), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation also requires that when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the condition can be met.
The regulations in 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, include the following General Design Criteria (GDC) applicable to Columbias design requirements:
GDC 34 - Residual heat removal A system to remove residual heat shall be provided. The system safety function shall be to transfer fission product decay heat and other residual heat from the reactor core at a rate such that specified acceptable fuel design limits and the design conditions of the reactor coolant pressure boundary are not exceeded.
Suitable redundancy in components and features, and suitable interconnections, leak detection, and isolation capabilities shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure.
GDC 38 - Containment heat removal A system to remove heat from the reactor containment shall be provided. The system safety function shall be to reduce rapidly, consistent with the functioning of other associated systems, the containment pressure and temperature following any loss-of-coolant accident and maintain them at acceptably low levels.
Suitable redundancy in components and features, and suitable interconnections, leak detection, isolation, and containment capabilities shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure.
2.4 Applicable Guidance 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 standard technical specifications (STSs) for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-1434, Standard Technical Specifications General Electric Plants, BWR/6, Revision 5 (ML21271A582), as modified by NRC-approved travelers. Traveler TSTF-230, Revision 1, revised the STSs related to Completion Times when two RHR suppression pool cooling subsystems are inoperable. The NRC staff approved TSTF-230 on July 26, 1999 (ML19067A141) and it was incorporated into NUREG-1434, Revision 2 (ML011780537).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-230 Columbia TS 3.6.2.3 currently requires two RHR suppression pool cooling subsystems be operable in Modes 1, 2, and 3. When two RHR suppression pool cooling subsystems are inoperable, the current Required Action and Completion Time states to be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The licensee proposed that when two RHR suppression pool cooling subsystems are inoperable, up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> be given to restore one RHR suppression pool cooling subsystem to operable status. If this proposed Required Action cannot be completed within the proposed 8-hour Completion Time, then the licensee will be required to be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. As noted in its application, the licensees basis for the proposed change was NRC-approved Traveler TSTF-230, Revision 1, which was developed to allow this change for all BWR plants (i.e., BWR/4 and BWR/6).
The licensee states that allowing the proposed 8-hour Completion Time for two RHR suppression pool cooling subsystems inoperable is appropriate because an immediate plant shutdown, which is currently required, has the potential to result in a unit scram that could result in steam being discharged to the suppression pool. With both loops of RHR suppression pool cooling inoperable, there would be no available means to remove heat from the suppression pool. The licensee stated that the 8-hour Completion Time would provide some time to restore one of the RHR suppression pool cooling subsystems prior to requiring a unit shutdown. The licensee also noted that the 8-hour Completion Time is consistent with Columbia TS 3.6.1.5, Residual Heat Removal (RHR) Drywell Spray System, Required Action B.1, which allows 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore one RHR drywell spray subsystem to operable status when in a condition where two RHR drywell spray subsystems are inoperable.
The application states that GDCs 34 and 38 as stated in section 2.3 of this SE, would continue to be met after implementation of this amendment. Columbias Updated Final Safety Analysis Report (UFSAR, Amendment 66) (ML21349B375) sections 3.1.2.4.5 and 3.1.2.4.9 discusses the licensing basis for GDCs 34 and 38. The NRC staffs review of the subject UFSAR sections, determined that the proposed changes do not adversely affect the Columbias licensing basis since there is no change to the design or configuration of the RHR system or any components that perform the containment heat removal functions, therefore a compliance with GDCs34 and 38 would continuously be maintained.
3.2 Technical Evaluation The NRC staff reviewed the licensees submittal and plant design described above and in section 2.0 of this safety evaluation. The staff determined that the STS changes approved in TSTF-230 are applicable to Columbia TSs because Columbia is a BWR/6 design, and the staff approved the TSTF-230 changes for BWR/6 designs. The staff compared the licensees proposed TS changes to the NRC-approved changes contained in TSTF-230 and NUREG-1434, Revision 5. Based on this review, the staff determined that the licensees proposed changes conform to TSTF-230 and NUREG-1434, by allowing a Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to return one RHR suppression pool cooling subsystem to operable status in the event two RHR suppression pool cooling subsystems are inoperable and requiring entry into Mode 3 and Mode 4 in the event that the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is not met. The 8-hour Completion Time is considered acceptable due to the low probability of a DBA occurring within this short period. In addition, RHR suppression pool cooling is not needed immediately following a DBA. It is needed for long term cooling following a DBA. Therefore, based on the discussion above, the NRC staff concludes that the licensees proposed changes to the Columbia TSs are acceptable.
As a result, the NRC staff finds that the proposed changes to Columbia TS 3.6.2.3 are adequate remedial actions to be taken until the LCO can be met that provide protection to the health and safety of the public, thereby satisfying the requirements of GDC 34, GDC 38 and 10 CFR 50.36(c)(2)(i).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Washington State official was notified of the proposed issuance of the amendment on March 29, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration published in the Federal Register on October 31, 2023 (88 FR 74531), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: R. Grover Date: June 12, 2024
- SE provided via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC*
NAME MChawla PBlechman SMehta DATE 3/29/2024 4/15/2024 1/29/2024 OFFICE OGC NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME KBernstein JRankin MChawla DATE 5/30/2024 6/6/2024 6/12/2024