ML18222A296

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Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263)
ML18222A296
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 08/29/2018
From: Hall J
Plant Licensing Branch II
To: Gayheart C
Southern Nuclear Operating Co
Hall J
References
CAC MF9997, CAC MF9998, EPID L-2017-LLA-0263
Download: ML18222A296 (17)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 29, 2018 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company, Inc.

P. 0. Box 1295, Bin 038 Birmingham, AL 35201-1295

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS TO REVISE TECHNICAL SPECIFICATION 3.7.7, "ECCS -

OPERATING" (CAC NOS. MF9997 AND MF9998; EPID L-2017-LLA-0263)

Dear Ms. Gayheart:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 292 to Renewed Facility Operating License No. DPR-57 and Amendment No. 237 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (HNP), respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated July 10, 2017.

The amendments revise the TSs by: (1) adding a Note to the Surveillance Requirements (SRs) of TS 3. 7. 7 to clarify that the SRs are not required to be met when the Limiting Condition for Operation (LCO) does not require the Main Turbine Bypass System to be operable; (2) clarifying that LCO 3.2.3, "LINEAR HEAT GENERATION RATE," also has limits for an inoperable Main Turbine Bypass System that are made applicable as specified in the Core Operating Limits Report; and (3) deleting an outdated footnote for LCO 3.2.3.

C. A Gayheart A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, a' /)

LW-f~.

rJRM~c J R. Hall, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 292 to DPR-57
2. Amendment No. 237 to NPF-5
3. Safety Evaluation cc: Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 292 Renewed License No. DPR-57

1. The Nuclear Regulatory Commission (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 July 10, 2017, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is hereby amended by page changes 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. 292, 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 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~-;.~

Michael T. Markley, Chief Plant Licensing Branch 11-1 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: August 29, 2018

ATTACHMENT TO LICENSE AMENDMENT NO. 292 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 3.2-4 3.2-4 3.7-18 3.7-18

for sample analysis or instrumentation 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 2804 megawatts thermal.

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 292, 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 shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained in the updated Fire Hazards Analysis and Fire Protection Program for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, which was originally submitted by letter dated July 22, 1986. Southern Nuclear may make changes to the fire protection program without prior Commission approval only if the changes Renewed License No. DPR-57 Amendment No. 292

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER~ 24% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within limits. A.1 Restore LHGR(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> within limits.

8. Required Action and 8.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< 24% ATP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the Once within limits specified in the COLA. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after

.!: 24% RTP In accordance with the Surveillance Frequency Control Program HATCH UNIT 1 3.2-4 Amendment No. 2 9 2

Main Turbine Bypass System 3.7.7

3. 7 PLANT SYSTEMS

OR LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," and LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are made applicable.

APPLICABILITY: THERMAL POWER.:: 24% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO.

B. Required Action and 8.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< 24% ATP.

Time not met.

SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

Not required to be met when the Main Turbine Bypass System is not required to be OPERABLE SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify one complete cycle of each main turbine In accordance with bypass valve. the Surveillance Frequency Control Program SR 3.7.7.2 Perform a system functional test. In accordance with the Surveillance Frequency Control Program SR 3.7.7.3 Verify the TURBINE BYPASS SYSTEM In accordance with RESPONSE TIME is within limits. the Surveillance Frequency Control Program HATCH UNIT 1 3.7-18 Amendment No. 2 9 2

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 237 Renewed License No. NPF-5

1. The Nuclear Regulatory Commission (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 July 10, 2017, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

Enclosure 2

2. Accordingly, the license is hereby amended by page changes 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. 237, 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 90 days from its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 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: August 29, 2018

ATTACHMENT TO LICENSE AMENDMENT NO. 237 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 3.2-4 3.2-4 3.7-18 3.7-18

(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 2 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, 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. 237, 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 shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained 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.

Renewed License No. NPF-5 Amendment No. 237

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLA.

APPLICABILITY: THERMAL POWER<!: 24% ATP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within limits. A.1 Restore LHGR(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> within limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< 24% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the Once within limits specified in the COLA. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after

.::: 24% RTP In accordance with the Surveillance Frequency Control Program HATCH UNIT 2 3.2-4 Amendment No. 2 3 7

Main Turbine Bypass System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Main Turbine Bypass System LCO 3.7.7 The Main Turbine Bypass System shall be OPERABLE.

OR LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," and LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLA, are made applicable.

APPLICABILITY: THERMAL POWER 2: 24% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< 24% ATP.

Time not met.

SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

Not required to be met when the Main Turbine Bypass System is not required to be OPERABLE SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify one complete cycle of each main turbine In accordance with bypass valve. the Surveillance Frequency Control Program SR 3.7.7.2 Perform a system functional test. In accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT2 3.7-18 Amendment No. 2 3 7

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 292 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 237 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

By application dated July 10, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML171918163), Southern Nuclear Operating Company, Inc. (SNC, the licensee) requested changes to the Technical Specifications (TSs) for the Edwin I. Hatch Nuclear Plant (HNP), Unit Nos. 1 and 2. The proposed changes would: (1) add a Note to the Surveillance Requirements (SRs) of TS 3.7.7, "Main Turbine Bypass System" clarifying that the SRs are not required to be met when the Limiting Condition for Operation (LCO) does not require the Main Turbine Bypass System (TBS) to be OPERABLE, (2) clarify that LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," also has limits for an inoperable TBS that are made applicable as specified in the Core Operating Limits Report (COLR), and (3) delete an outdated footnote for LCO 3.2.3.

2.0 REGULATORY EVALUATION

2.1 Applicable Requirements and Guidance The U.S. Nuclear Regulatory Commission (NRC) staff considered the following regulatory requirements and guidance documents in its review of the proposed amendment:

  • Title 10 of the Code of Federal Regulations (10 CFR) 50.36, "Technical Specifications,"

which details the content and information that must be included in a station's TS. In accordance with 10 CFR 50.36, TSs are required to include ( 1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. As stated in 10 CFR 50.36(c)(2), 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 Enclosure 3

shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. As stated in 10 CFR 50.36(c)(3),

surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.

2.2 System Design and Operation Main Turbine Bypass System (TBS)

The TBS provides operational flexibility to dissipate a portion of the energy of the main steam exiting the reactor in order to reduce the steam load on the turbine during certain plant evolutions. These include reactor heatup and cooldown, evolutions where the turbine is brought up to speed and synchronized with the generator, and during power operation when the reactor system steam generation could exceed turbine limitations. The TBS removes this excess energy by discharging a percentage of rated main steam flow directly to the main condensers, bypassing the turbine. This heat is rejected to the condenser through three bypass (regulating) valves mounted on a valve manifold. The bypass capacity of the TBS at HNP is around 20 percent of the Nuclear Steam Supply System rated steam flow for both Units 1 and 2.

The TBS is not a safety system, because it is not required for safe shutdown. However, the TBS is assumed to function during events crediting the system (e.g., feedwater controller failure -

maximum demand) as discussed in Chapter 15 of the HNP Final Safety Analysis Report (FSAR).

Opening the bypass valves during pressurization events mitigates the increase in reactor vessel pressure and affects the minimum critical power ratio (MCPR) and the linear heat generation rate (LHGR). When the TBS is inoperable, more restrictive limits for these values are applied, to maintain the assumptions in the FSAR Chapter 15 analyses.

3.0 TECHNICAL EVALUATION

TS 3.7.7 LCO Current HNP TS 3.7.7 provides the requirements for the TBS. LCO 3.7.7 is applicable when THERMAL POWER (defined in the TSs as the total reactor core heat transfer rate to the reactor coolant) is greater than or equal to 24 percent of RATED THERMAL POWER (RTP). The LCO 3.7.7 requirements can be met in two ways; either the Main Turbine Bypass System shall be OPERABLE, or LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR, must be applied.

Similar to TS 3.2.2 for MCPR, TS 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR),"

requires that the limits specified in the COLR for LHGRs also must be met when THERMAL POWER is greater than or equal to 24 percent RTP. The Applicability, Conditions, Required Actions, and associated Completion Times for LCOs 3.2.2, 3.2.3, and 3.7.7 are the same. All three LCOs allow two hours to satisfy the requirements of the LCO if it is not met, and then four hours thereafter to reduce THERMAL POWER to less than 24 percent RTP.

The licensee proposes to modify LCO 3.7.7 to add the provision that LCO 3.2.3 limits on LHGR for an inoperable Main Turbine Bypass System, as specified in the COLR, are made applicable, similar to the existing provision regarding MCPR limits. This change clarifies that the requirements of LCO 3.2.3 also apply when considering whether LCO 3.7.7 requirements are

met, when the TBS is inoperable and THERMAL POWER is greater than or equal to 24 percent RTP. The NRC staff also notes that this change is consistent with NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Revision 4.0, April 2012. The NRC staff considers this to be an editorial change that clarifies the existing HNP TS requirements, and finds it acceptable.

TS 3.7.7 SR Note The proposed change to add a Note to TS 3.7.7, would clarify that the SRs are not required to be met when the LCO does not require the TBS to be operable. The TS 3.7.7 SRs require testing of the main turbine bypass valves and the system itself, and thus are intended to demonstrate that the TBS is operable. However, as written, the SRs could be considered to be applicable even in cases where the TBS is not required to be operable, or is inoperable, when LCO 3.7.7 is met by applying the more restrictive thermal limits of LCOs 3.2.2 and 3.2.3.

The NRC staff agrees that the existing TS 3.7.7 SRs do not apply when LCO 3.7.7 is met by applying the more restrictive thermal limits of LCOs 3.2.2 and 3.2.3 for an inoperable TBS.

These more restrictive limits ensure that the assumptions in the FSAR Chapter 15 analyses will be met without reliance on the TBS. The proposed Note would clarify that the SRs do not apply when the TBS is not required to be operable and would thus remove any existing ambiguity regarding their applicability. Therefore, the NRC staff finds the proposed change acceptable.

TS 3.2.3 Footnote Both HNP Units 1 and 2 have an outdated footnote for TS 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)." The footnotes cite the respective operating cycles for which the current TS requirements became effective. Because these dates have passed, the deletions of the respective footnotes have no meaningful impact. Therefore, the NRC staff finds this change acceptable.

Technical Evaluation Conclusion The NRC staff evaluated the license amendment request and determined that the proposed changes are primarily editorial in nature and that the applicable regulatory requirements will continue to be met. Therefore, the NRC staff concludes that the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Georgia State official was notified of the proposed issuance of the amendments on August 15, 2018 and 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 surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative

occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on November 21, 2017 (82 FR 55412).

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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Fred Forsaty, NRR Da~: August 29, 2018

ML18222A296 *via memorandum **via e-mail OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1/LA NRR/DSS/SRXB/BC NRR/DSS/STSB/BC NAME JHall KGoldstein JWhitman* VCusumano**

DATE 8/15/18 8/13/18 6/7/18 8/17/18 OFFICE OGC - NLO NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME DRoth** MMarkley JHall DATE 8/24/18 8/29/18 8/29/18

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