Text

Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10
	ML22346A148
Person / Time
Site:	Hatch
Issue date:	02/09/2023
From:	Dawnmathews Kalathiveettil; Plant Licensing Branch II
To:	Gayheart C; Southern Nuclear Operating Co
	Kalathiveettil, D
References
	EPID L-2022-LLA-0045
	Download: ML22346A148 (19)
	v • d • e

February 9, 2023 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS NOS. 320 AND 265, REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-208, EXTENSION OF TIME TO REACH MODE 2 IN LCO 3.0.3, AND ADMINISTRATIVE CORRECTION FOR DUPLICATE TECHNICAL SPECIFICATIONS 3.4.10 (EPID L-2022-LLA-0045)

Dear Ms. Gayheart:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 320 to Renewed Facility Operating License No. DPR-57 and Amendment No. 265 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated March 25, 2022, as supplemented by letters dated May 17 and October 14, 2022.

The proposed license amendment request would revise TSs for Hatch, Units 1 and 2, to adopt Technical Specification Task Force (TSTF) Traveler TSTF-208, Extension of Time to Reach Mode 2 in LCO 3.0.3, that would increase the time to reach MODE 2 in Limiting Condition for Operation (LCO) 3.0.3 from 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . These amendments also delete duplicate TS Page 3.4-25 in the TS for Hatch, Units 1 and 2.

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/

Dawnmathews T. Kalathiveettil, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 320 to DPR-57

2. Amendment No. 265 to NPF-5

3. Safety Evaluation cc w/encls: Listserv

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 320 Renewed License No. DPR-57

1.

The Nuclear Regulatory Commission (NRC, the Commission) has found that:

A.

The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 1 (the facility) Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated March 25, 2022, as supplemented by letters dated May 17 and October 14, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as 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 set forth in 10 CFR Chapter I;

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 hereby amended by page 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-57 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 320, are hereby incorporated in the renewed license. Southern Nuclear 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 from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-57 and Technical Specifications Date of Issuance: February 9, 2023 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2023.02.09 14:49:26 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 320 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License 4

4 TSs TSs 3.0-1 3.0-1 3.4-25 Renewed License No. DPR-57 Amendment No. 320 for sample analysis or instrument calibration, or associated with radioactive apparatus or components (6)

Southern Nuclear, 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions specified or incorporated below:

(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady-state reactor core power levels not in excess of 2,804 megawatts thermal.

(2)

Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 320, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed immediately upon implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated before the time and condition specified:

SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.

(3)

Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated April 4, 2018, supplemented by letters dated May 28, August 9, October 7, and December 13, 2019, and February 5, and March 13, 2020, and as approved in the NRC safety evaluation (SE) dated June 11, 2020. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

LCO Applicability 3.0 HATCH UNIT 1 3.0-1 Amendment No. 320 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7, and LCO 3.0.8.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a.

MODE 2 within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ;

b.

MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c.

MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified Condition in the Applicability shall only be made:

a.

When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time,

b.

After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk (continued)

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 265 Renewed License No. NPF-5

1.

The Nuclear Regulatory Commission (NRC, the Commission) has found that:

A.

The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 2 (the facility) Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated March 25, 2022, as supplemented by letters dated May 17 and October 14, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as 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 set forth in 10 CFR Chapter I;

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 hereby amended by page 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-5 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 265 are hereby incorporated in the renewed license. Southern Nuclear 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 from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-5 and Technical Specifications Date of Issuance: February 9, 2023 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2023.02.09 14:50:19 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 265 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License 4

4 TSs TSs 3.0-1 3.0-1 3.4-25

Renewed License No. NPF-5 Amendment No. 265 (6)

Southern Nuclear, 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions2 specified or incorporated below:

(1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at steady sate reactor core power levels not in excess of 2,804 megawatts thermal, in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B); as revised through Amendment No. 265 are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.

(a)

Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c),

as specified in the licensee amendment request dated April 4, 2018, supplemented by letters dated May 28, August 9, October 7, and December 13, 2019, and February 5, and March 13, 2020, and as approved in the NRC safety evaluation (SE) dated June 11, 2020.

Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would 2

The original licensee authorized to possess, use, and operate the facility with Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.

LCO Applicability 3.0 HATCH UNIT 2 3.0-1 Amendment No. 265 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7, and LCO 3.0.8.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a.

MODE 2 within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ;

b.

MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c.

MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

LCO 3.0.4 When an LCO is not met, entry into a mode or other specified condition in the Applicability shall only be made:

a.

When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time,

b.

After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk (continued)

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 320 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 265 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366

1.0 INTRODUCTION

Southern Nuclear Operating Company (SNC, the licensee) requested changes to the Technical Specifications (TSs) for the Edwin I. Hatch Nuclear Plan, Units 1 and 2 (Hatch) by license amendment request (LAR, application) dated March 25, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22087A169), as supplemented by letters dated May 17 (ML22137A001) and October 14, 2022 (ML22287A183), to adopt Technical Specification Task Force (TSTF) Traveler TSTF-208, Revision 0 (ML040570174), Extension of Time to Reach Mode 2 in LCO 3.0.3 and delete duplicate TSs Page 3.4-25 in each units TSs.

The supplemental letters dated May 17 and October 14, 2022, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on July 15, 2022 (87 FR 42505).

1.1 Proposed Changes The proposed changes would revise the time to reach MODE 2 in Limiting Condition for Operation (LCO) 3.0.3 from 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and delete duplicate TS Page 3.4-25 in TS for Hatch, Units 1 and 2.

The LCO 3.0.3 establishes the actions that must be implemented when an LCO is not met and an associated Required Action and Completion Time is not met, and no other Condition applies; or the condition of the unit is not specifically addressed by the associated actions. This means that no combination of Conditions stated in the actions can be made that exactly corresponds to the actual condition of the unit.

The LCO 3.0.3 delineates the time limits for placing the unit in a safe Mode or other specified condition when operation cannot be maintained within the limits for safe operation as defined by an LCO and its actions.

Upon entering LCO 3.0.3, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is allowed to prepare for an orderly shutdown before initiating a change in unit operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower Modes of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum required equipment is operable. This reduces thermal stresses on components of the reactor coolant system and the potential for a plant upset that could challenge safety systems under conditions to which LCO 3.0.3 applies.

Current Hatch LCO 3.0.3 states:

When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a.

MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b.

MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c.

MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

Revised Hatch LCO 3.0.3 would state:

When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a.

MODE 2 within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ;

b.

MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c.

MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

The TS Page 3.4-25 in both units TSs are duplicate pages for TS 3.4-22 in both units TSs. The licensee proposed deleting TS Page 3.4-25 in the TS for Hatch, Units 1 and 2.

2.0 REGULATORY EVALUATION

On July 11, 1967, the Atomic Energy Commission (AEC) published for public comment in the Federal Register (32 FR 10213), a revised and expanded set of 70 draft GDC. On February 20, 1971, the AEC published in the Federal Register (36 FR 3255) a final rule that added Appendix A (final GDC) to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, which was amended on July 7, 1971 (36 FR 12733). Differences between the 1967 draft GDC and the final GDC included a consolidation from 70 to 64 criteria.

The construction permits of Hatch, Unit 1, and Hatch, Unit 2, were issued on September 30, 1969, and on December 27, 1972, respectively. Consequently, Hatch, Unit 2, is licensed in conformance with 10 CFR Part 50, Appendix A, General Design Criteria. Hatch, Unit 1, is licensed in conformance with the 1967 version of 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plant Construction Permits (ADAMS Accession No. ML043310029).

Hatch, Unit 1, Final Safety Analysis Report (FSAR), Appendix F, Conformance To Atomic Energy Commission Criteria, describes the relevant licensing bases for Hatch, Unit 1. The operating license for Hatch, Unit 1, was issued in 1974, and the operating license for Hatch, Unit 2 was issued in 1978.

Section 3.0, Design of Structures, Components, Equipment, and Systems, of the NRC safety evaluation report related to the operation of Hatch Unit 1, describes the NRC staffs evaluation of the facilitys conformance with the GDC for the original facility operating license. Hatch Unit 1 was designed and constructed in accordance with the GDC issued for comment in July of 1967.

The NRC safety evaluation report concluded that there was reasonable assurance that the plant met the intent of the GDC published in the FR in 1971.

Section 3.0, Design of Structures, Components, Equipment, and Systems, of the NRC safety evaluation report (NUREG-0411) related to the operation of Hatch Unit 2, describes the NRC staffs evaluation of the facilitys conformance with the GDC for the original facility operating license. Hatch Unit 2 was designed and constructed in accordance with the amended GDC dated July 7, 1971, and the NRC safety evaluation report concluded that the plant design conformed to the amended criteria.

10 CFR Section 50.36(b) states that technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34.

The categories of items required to be in the TSs are provided in 10 CFR 50.36(c). As required by 10 CFR 50.36(c)(2)(i), the TSs will include LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation at 10 CFR 50.36(c)(2)(i) 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 TSs until the condition can be met.

The NRC staff assesses proposed remedial actions in accordance with the general standards for license amendments. Under 10 CFR 50.92(a), determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses or construction permits to the extent applicable and appropriate. Both the common standards for licenses and construction permits in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public.

Hatch TS 1.3, Completion Times, establishes the Completion Time (CT) convention and provides guidance for its use. Usage rules for LCOs are in TS Section 3.0, Limiting Condition for Operation (LCO) Applicability. LCO 3.0.3, it delineates the time limits for placing the unit in a safe mode or other specified condition when operation cannot be maintained within the limits for safe operation as defined by an LCO and its actions. LCO 3.0.3 constitutes a license requirement on plant operation as the TSs are Appendix A to the Renewed Facility Operating License for each unit..

The NRC staffs guidance for the review of TSs is in Chapter 16, 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, dated March 2010 (ML100351425).

As described therein, as part of the regulatory standardization effort, the NRC staff has prepared Standard Technical Specifications (STS) for each of the LWR nuclear designs. The applicable STS for Hatch are contained in NUREG 1433, Standard Technical Specifications, General Electric BWR/4 Plants, Revision 5.0, Volume 1, Specifications and Volume 2, Bases, dated September 2021 (ML21272A357 and ML21272A358, respectively). Chapter 16 of NUREG 0800 specifies that the NRC staff review, whether the content and format of proposed TSs conform to the applicable STS. Where TS provisions depart from the reference TSs, the NRC staff determines whether proposed differences are justified by uniqueness in plant design or other considerations.

3.0 TECHNICAL EVALUATION

3.1 Deletion of Page 3.4-25 in Hatch TSs The staff reviewed page 3.4-25 in each Units TSs. The staff confirmed that TS pages 3.4-25 duplicates the requirements on page 3.4-22 in the TS for Hatch, Units 1 and 2. The staff determined deletion of the duplicate pages is acceptable because the TS, as amended, will continue to retain the requirements and is, therefore, administrative in nature and would not constitute a change in TS requirements.

3.2 Adoption of TSTF-208 The model TSs supporting TSTF-208, Revision 0, revised NUREG-1433 Section 3.0, Limiting Condition for Operation (LCO) Applicability, by adding brackets to the specified 7-hour time interval of LCO 3.0.3 for reaching MODE 2. In addition, TSTF-208 added a reviewers note to LCO 3.0.3, stating, The brackets around the time provided to reach MODE 2 allow a plant to extend the time from 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to a plant specific time. Before the time can be changed, plant specific data must be provided to support the extended time. The changes to STS made by TSTF-208 was incorporated into Revision 2 of NUREG-1433 and carried forward into all successive revisions through the current NUREG-1433, Revision 5.

In its submittal dated March 25, 2022, the licensee request proposed to adopt TSTF-208 with a deviation involving the deletion of LCO 3.0.3.a. and the current 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months allowed time to reach MODE 2. Following a clarification call with the NRC, the licensee revised the proposed change in its letter dated May 17, 2022. The revision extended Hatchs LCO 3.0.3 allowed time to reach MODE 2 from 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

In response to the NRC Request for Additional Information dated July 26, 2022 (ML22208A133), the licensee submitted a supplement on October 14, 2022 (ML22287A183). In its response, the licensee provided plant operating data required by the Reviewers Note in TSTF-208 to support extension of the LCO completion time. The licensees data analysis indicated that following the plants general operating procedures for Normal Shutdown would require approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and 15 minutes to reach Mode 3 (Hot Shutdown) complete an orderly shutdown to 20 percent power followed by operators inserting a manual reactor Scram.

The NRC staff determined that, assuming a 10 percent uncertainty in this 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and 15-minute completion time for variabilities in plant configuration and operating crew performance, it is very likely that this activity can be reasonably expected to be completed in about 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

Additionally, Figure 1 (Reactor Power vs Clock Time for Hatch Unit 2 Reactor Shutdown, October 9-10, 2022) was also included in the October 14, 2022, supplement. Figure 1 provided data that showed that based on the current 7-hour LCO 3.0.3 CT, when following the general operating procedures, the plant operators would insert a SCRAM from approximately 40 percent power and would expect to incur complicating group isolations based on the automatic level control response from a SCRAM at that power level.

Based on this analysis, the staff concluded that an extension of the TS LCO 3.0.3 completion time from 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months is sufficiently justified, warranted, and appropriate per TSTF-208 in that it provides a tangible operational safety benefit from inserting the SCRAM at 20 percent power instead of at 40 percent power. The NRC staff finds the proposed change acceptable because 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months provides a sufficient time requirement for Hatch to reach MODE 2 while continuing to ensure a timely, yet orderly, shutdown. The change is also consistent with TSTF-208, Revision 0 in that the licensee provided plant specific data to support the extended time.

The staff determined that current TS 1.3 along with modified LCO 3.0.3 will continue to provide time limits for placing the unit in a safe mode or other specified condition when operation cannot be maintained within the limits for safe operation. The staff determined that the Hatch TS, as amended, would also conform to NUREG-1433, Revision 5. The staff determined the TS as amended will continue to meet 10 CFR 50.36(b) because they will continue to be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto.

Based on the above, the staff determined that the TS, as amended, will continue to meet 10 CFR 50.36(c)(2)(i). The license has provided sufficient justification the time to reach MODE 2 in LCO 3.0.3 from 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . The revised LCO 3.0.3 will continue to require 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 TSs until the condition can be met. Therefore, the staff concluded that the proposed change is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the State of Georgia official was notified of the proposed issuance of the amendment on December 12, 2022. The State official confirmed the State of Georgia had no comments on December 13, 2022.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. 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 on July 15, 2022 (87 FR 42505), 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.

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 Commission's 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 Contributors: Matthew Hamm Charley Peabody Date: February 9, 2023

ML22346A148 OFFICE NRR/DORL/LPL2-1/PM*

NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NAME DKalathiveettil KGoldstein VCusumano DATE 12/09/2022 02/08/2023 11/07/2022 OFFICE NRR/DSS/SNSB/BC OGC - NLO NRR/DORL/LPL2-1/BC NAME DWoodyatt LShrum MMarkley DATE 11/07/2022 12/29/2022 02/09/2023 OFFICE NRR/DORL/LPL2-1/PM NAME DKalathiveettil DATE 02/09/2023

v t e Letter Sequence Approval
EPID:L-2022-LLA-0045, TSTF-208 (Approved, Closed)
Initiation Request Acceptance Supplement Administration Questions 26 July 2022 Answers 14 October 2022 Results Approval Other: ML22111A086
MONTHYEAR2022-05-17 [Table View]

ML22346A148

Text

SUBJECT:

Dear Ms. Gayheart:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

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