Text

Issuance of Amendment No. 274 to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
	ML24128A224
Person / Time
Site:	Columbia
Issue date:	05/31/2024
From:	Mahesh Chawla; Plant Licensing Branch IV
To:	Schuetz R; Energy Northwest
	Chawla M
References
	EPID L-2023-LLA-0170
	Download: ML24128A224 (1)
	v • d • e

May 31, 2024

Mr. Robert Schuetz Chief Executive Officer Energy Northwest MD 1023 76 North Power Plant Loop P.O. Box 968 Richland, WA 99352

SUBJECT:

COLUMBIA GENERATING STAT ION - ISSUANCE OF AMENDMENT NO. 274 TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-584, ELIMINATE AUTOMATIC RWCU SYSTEM ISOLATION ON SLC INITIATION (EPID L-2023-LLA-0170)

Dear Robert Schuetz:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 274 to Renewed Facility Operating License No. NPF-21 for the Columbia Generating Station (Columbia). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 5, 2023.

The amendment revises Columbia TS 3.3.6.1, P rimary Containment Isolation Instrumentation, to remove the requirement that the reactor water cleanup (RWCU) system automatically isolate on manual initiation of the standby liquid control (SLC) system. The SLC system is manually actuated in response to an anticipated transient without scram event. The amendment is based on NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation.

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. 274 to NPF-21

2. Safety Evaluation

3. Notices and Environmental Findings

cc: Listserv

ENERGY NORTHWEST

DOCKET NO. 50-397

COLUMBIA GENERATING STATION

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 274 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 December 5, 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.

Enclosure 1

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. 274 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 90 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: May 31, 2024 ATTACHMENT TO LICENSE AMENDMENT NO. 274

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 3.3.6.1-3 3.3.6.1-3 3.3.6.1-9 3.3.6.1-9 3.3.6.1-10 3.3.6.1-10

(2) Technical Specifications and Environmental Protection Plan

The Technical Specifications contained in Appendix A, as revised through Amendment No. 274 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.

Renewed License No. NPF-21 Amendment No. 274 Primary Containment Isolation Instrumentation 3.3.6.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

H. Required Action and H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition F or G AND not met.

H.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR

As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

I. As required by RequiredI.1 Initiate action to restore Immediately Action C.1 and channel to OPERABLE referenced in status.

Table 3.3.6.1-1.

SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

Columbia Generating Station 3.3.6.1-3 Amendment No. 149,169 225 238 264 270 274 Primary Containment Isolation Instrumentation 3.3.6.1

Table 3.3.6.1-1 (page 4 of 6)

Primary Containment Isolation Instrumentation

APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

4. RWCU System Isolation

e. Heat Exchanger 1, 2, 3 1 F SR 3.3.6.1.3 70F Room Area SR 3.3.6.1.4 Ventilation SR 3.3.6.1.6 Differential Temperature - High

f. Pump Room Area 1, 2, 3 1 per room F SR 3.3.6.1.3 180F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

g. Pump Room Area 1, 2, 3 1 per room F SR 3.3.6.1.3 100F Ventilation SR 3.3.6.1.4 Differential SR 3.3.6.1.6 Temperature - High

h. RWCU/RCIC Line 1, 2, 3 1 F SR 3.3.6.1.3 180F Routing Area SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6

i. RWCU Line Routing 1, 2, 3 1 per room F SR 3.3.6.1.3 Area Temperature - SR 3.3.6.1.4 High SR 3.3.6.1.6

Room 409, 509 175F Areas

Room 408, 511 180F Areas

j. Reactor Vessel 1, 2, 3 2 F SR 3.3.6.1.2 -58 inches Water Level - Low SR 3.3.6.1.4 Low, Level 2 SR 3.3.6.1.6

k. Manual Initiation 1, 2, 3 2 G SR 3.3.6.1.6 NA

(c) Deleted

Columbia Generating Station 3.3.6.1-9 Amendment No. 161,169 225 251 253 270 274 Primary Containment Isolation Instrumentation 3.3.6.1

Table 3.3.6.1-1 (page 5 of 6)

Primary Containment Isolation Instrumentation

APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

5. Residual Heat Removal (RHR) Shutdown Cooling (SDC) System Isolation

a. Pump Room Area 3 1 per room F SR 3.3.6.1.3 150F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

b. Pump Room Area 3 1 per room F SR 3.3.6.1.3 70F Ventilation SR 3.3.6.1.4 Differential SR 3.3.6.1.6 Temperature - High

c. Heat Exchanger 3 1 per room F SR 3.3.6.1.3 Area Temperature - SR 3.3.6.1.4 High SR 3.3.6.1.6

Room 505 Area 140F

Room 507 Area 160F

Room 605 Area 150F

Room 606 Area 140F

d. Reactor Vessel 3 2 I SR 3.3.6.1.1 9.5 inches Water Level - Low, SR 3.3.6.1.2 Level 3 SR 3.3.6.1.4 SR 3.3.6.1.6

e. Reactor Vessel 1, 2, 3 1 F SR 3.3.6.1.2 135 psig Pressure - High SR 3.3.6.1.4 SR 3.3.6.1.6

f. Manual Initiation 1, 2, 3 2 G SR 3.3.6.1.6 NA

(d) Deleted

Columbia Generating Station 3.3.6.1-10 Amendment No. 208,220 225 270 274 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 274 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397

Application Safety Evaluation Date December 5, 2023, ML23339A124 May 31, 2024 Principal Contributor to Safety Evaluation Tarico Sweat

1.0 PROPOSED CHANGE

S

Energy Northwest (the licensee) requested changes to the technical specifications (TSs) for Columbia Generating Station (Columbia) by lic ense amendment request (LAR, application),

dated December 5, 2023. The proposed amendment would revise the primary containment isolation instrumentation technical specification based on Technical Specifications Task Force (TSTF) Traveler TSTF-584, Revision 0, Eliminate Automatic RWCU [Reactor Water Cleanup]

System Isolation on SLC [Standby Liquid Control] Initiation (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22054A292), and the associated U.S.

Nuclear Regulatory Commission (NRC, the Commission), staff safety evaluation (SE) of TSTF-584 (ML23206A076). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP).

Columbia Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation, would be revised to remove the requirement that the RWCU system automatically isolate on manual initiation of the SLC system. The SLC system is manually actuated in response to an anticipated transient without scram (ATWS) event. Additionally, the licensee confirmed that the emergency operating procedures only credit manual initiation of the SLC system.

Enclosure 2

Reactor Water Cleanup System

The following automatic signals to the RWCU system supply and/or return isolation valves indicate that the RWCU piping or components have been breached:

Low reactor vessel water level; RWCU system high differential flow; Main steam tunnel penetration area temperature high; and RWCU heat exchanger/pump/filter demineralizer unit area high temperature.

The TSs require the above functions to be operable. The automatic closure of the supply and/or return isolation valves, coupled with the dual check valves in each RWCU system return line isolates the RWCU system from the reactor coolant pressure boundary. The automatic signal for RWCU system isolation on SLC system initiation, which is proposed to be removed, is not used to indicate any breach of RWCU piping or components.

Standby Liquid Control System

During an ATWS event, the SLC system would bring the reactor from full power to a subcritical condition without crediting the control rods. The SLC system injects a quantity of borated water into the reactor core that adds negative reactivity sufficient to compensate for all of the various positive reactivity effects that could occur during shutdown. The licensee confirmed that the plant response to an ATWS event, which requires SLC system actuation, would also result in automatic isolation of RWCU.

1.1 Proposed TS Changes to Adopt TSTF-584

In accordance with the NRC staff-approved TSTF-584 under the CLIIP by letter dated July 31, 2023 (ML23206A124), the licensee proposed changes that would revise TS 3.3.6.1, Primary Containment Isolation Instrumentation for Columbia. Specifically, the licensee proposed the following changes to adopt TSTF-584:

Technical Change:

Table 3.3.6.1-1, Function 4.k, RWCU System Isolation - Standby Liquid Control (SLC)

System Initiation, is deleted.

Editorial changes needed for consistency:

Table 3.3.6.1-1, Function 4.l, Manual Initiation, is renumbered as Function 4.k.

Table 3.3.6.1-1, Function 5.d, reference to Action J is revised to reference Action I.

TS 3.3.6.1, Action I, which is only referenced in Function 4.k, is deleted.

TS 3.3.6.1, Action J, is renumbered Action I.

1.2 Additional Proposed TS Changes

In addition to the changes proposed consistent with the traveler as discussed in section 1.1 above, the licensee proposed the following editorial variation:

The licensee noted that Columbia TSs have different numbering and titles than standard technical specifications (STSs).

2.0 REGULATORY EVALUATION

The categories of items required to be in the TSs are listed in Title 10 of the Code of Federal Regulations (10CFR) Section50.36(c). The regulation at 10CFR50.36(c)(2) requires that TSs include limiting conditions for operation (LCOs). The regulation at 10 CFR 50.36(c)(2)(i), states, in part that LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation further states, in part, that [w]hen 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 condition can be met.

The regulation at 10 CFR 50.62(b) defines an ATWS as an anticipated operational occurrence as defined in appendix A of this part followed by the failure of the reactor trip portion of the protection system specified in General Design Criterion 20 of appendix A of this part.

The NRC staffs guidance for the review of TSs is in Chapter16.0, Revision 3, Technical Specifications, of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition (SRP), dated March2010 (ML100351425). Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the traveler TSTF-584, which was approved under the CLIIP.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-584

The NRC staff compared the licensee s proposed TS changes in section1.1 of this SE against the changes approved in TSTF-584. In accordance with the SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-584 are applicable because Columbia is a boiling water reactor (BWR) design plant, and the NRC staff approved the TSTF-584 changes for BWR designs. The NRC staff finds that the licensees proposed changes to the Columbia TSs in section1.1 of this SE are consistent with those found acceptable in TSTF-584.

In the NRC SE of TSTF-584, the NRC staff concluded that the proposal to eliminate automatic isolation of the RWCU system on the initiation of the SLC system by deleting table 3.3.6.1-1, Function4.k is acceptable because the specified acceptable fuel design limits will not be affected during an ATWS event. Therefore, 10 CFR 50.62(b) will continue to be met.

Additionally, 10 CFR 50.36(c)(2)(i) will continue to be met because TS 3.3.6.1 continues to provide remedial actions and shuts down the reactor if the remedial actions cannot be met.

Thus, the proposed changes continue to meet the requirements of 10 CFR 50.62(b) and 10 CFR50.36(c)(2)(i) as discussed in section3.0 of the NRC staffs SE of TSTF-584.

3.2 Additional Proposed TS Changes

3.2.1 Editorial Variations

The licensee proposed renumbering and deletion of Func tions and Actions in TS 3.3.6.1, which are described above in section 1.2. These changes are acceptable because they are conforming changes resulting from the deletion of table 3.3.6.1-1, Function 4.k, and do not alter

the way the TSs are implemented. Furthermore, the NRC staff finds this change is acceptable since it is editorial and provides the correct numbering sequence.

The licensee noted that Columbia TSs have different numbering and titles than STS. The NRC staff finds that the different TS numbering and title 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 amendment 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. 274 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397

Application Safety Evaluation Date December 5, 2023, ML23339A124 May 31, 2024

1.0 INTRODUCTION

Energy Northwest (the licensee) requested changes to the technical specifications (TSs) for Columbia Generating Station by license amendment request (application), dated December 5, 2023. The proposed amendment would revise the primary containment isolation instrumentation TS based on Technical Specifications Task Force (TSTF) Traveler TSTF-584, Revision 0, Eliminate Automatic RWCU [Reactor Water Cleanup] System Isolation on SLC [Standby Liquid Control] Initiation (Agencywide Docum ents Access and Management System (ADAMS)

Accession No.ML22054A292), and the associated U.S. Nuclear Regulatory Commission (NRC, the Commission), staff safety evaluation (SE) of TSTF-584 (ML23206A076). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP).

2.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Washington State official was notified of the proposed issuance of the amendment on May 6, 2024. The State official had no comments.

3.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to 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 as published in the Federal Register on February 20, 2024 (89 FR 12875), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for catego rical 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.

Enclosure 3

ML24128A224 *concurrence via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC*

NAME MChawla PBlechman SMehta DATE 5/13/2024 5/13/2024 5/3/2024 OFFICE OGC - NLO NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME MASpencer JRankin MChawla DATE 5/23/2024 5/31/2024 5/31/2024

v t e Letter Sequence Approval
EPID:L-2023-LLA-0170, TSTF-584 (Approved, Closed)
Initiation Request Acceptance Administration Questions Answers Results Approval Other:
MONTHYEAR2024-01-05 [Table View]

ML24128A224