Text

Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
	ML22046A022
Person / Time
Site:	Oconee, Mcguire, Catawba, Robinson, McGuire
Issue date:	06/14/2022
From:	Natreon Jordan; Plant Licensing Branch II
To:	Hamilton T; Duke Energy Corp
	Jordan N
References
	EPID L-2021-LLA-0111
	Download: ML22046A022 (74)
	v • d • e

June 14, 2022

Ms. Tanya Hamilton Senior Vice President - Nuclear Corporate Duke Energy Corporation 526 South Church Street, EC-07H Charlotte, NC 28202

SUBJECT:

CATAWBA NUCLEAR STATION, UNITS 1 AND 2; MCGUIRE NUCLEA R STATION, UNITS 1 AND 2; OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3; AND H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENTS TO ADOPT TSTF-439, ELIMINATE SECOND COMPLETION TIMES LIMITING TIME FROM DISCOVERY O F FAILURE TO MEET AN LCO (EPID L-2021-LLA-0111)

Dear Ms. Hamilton:

The U.S. Nuclear Regulatory Commi ssion (NRC) has issued the fol lowing enclosed amendments: Amendment Nos. 312 and 308 to Renewed Facility Operating License (RFOL)

Nos. NPF-35 and NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively; Amendment Nos. 322 and 301 to RFOL Nos. NPF-9 and NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively; Amendment Nos. 423, 425, and 424 to RFOL Nos. DPR-38, DPR-47, and DPR-55 for the Oconee Nuclear Station, Units 1, 2, and 3, respectively; and Amendment No. 270 to RFOL No. DPR-23 for the H. B. Robinson Steam Electric Plant, Unit 2.

These amendments are issued in response to your June 9, 2021 ap plication, which was supplemented on July 16, 2021. They would revise the facilities technical specifications to adopt approved Technical Specifications Task Force Traveler TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO [Limiting Condition for Operation].

T. Hamilton

A copy of the NRC staffs Safety Evaluation is also enclosed. T he Notice of Issuance will be included in the Commissions monthly Federal Register notice.

If you have any questions, please contact me at (301) 415-7410 or by e-mail at Natreon.Jordan@nrc.gov.

Sincerely,

/RA/

Natreon Jordan, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-413, 50-414, 50-369, 50-370, 50-269, 50-270, 50-287, and 50-261

Enclosures:

1. Amendment No. 312 to NPF-35

2. Amendment No. 308 to NPF-52

3. Amendment No. 322 to NPF-9

4. Amendment No. 301 to NPF-17

5. Amendment No. 423 to DPR-38

6. Amendment No. 425 to DPR-47

7. Amendment No. 424 to DPR-55

8. Amendment No. 270 to DPR-23

9. Safety Evaluation

cc: See next page

T. Hamilton

cc: Mr. Robert T. Simril Mr. Thomas Ray Site Vice President Site Vice President Catawba Nuclear Station McGuire Nuclear Station Duke Energy Carolinas, LLC Duke Energy Carolinas, LLC 4800 Concord Road 12700 Hagers Ferry Road York, SC 29745 Huntersville, NC 28078-8985

Mr. Steven M. Snider Mr. Ernest J. Kapopoulos, Jr.

Site Vice President Site Vice President Oconee Nuclear Station H. B. Robinson Steam Electric Plant Duke Energy Carolinas, LLC Duke Energy Progress, LLC 7800 Rochester Highway 3581 West Entrance Road, RNPA01 Seneca, SC 29672-0752 Hartsville, SC 29550

Ms. Kim Maza Mr. John A. Krakuszeski Site Vice President Site Vice President Duke Energy Progress, LLC Brunswick Steam Electric Plant Shearon Harris Nuclear Power Plant, Unit 1 Duke Energy Progress, LLC 5413 Shearon Harris Road, M/C HNP01 8470 River Rd., SE (M/C BNP001)

New Hill, NC 27562-0165 Southport, NC 28461

Additional Distribution by Listserv

DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-413

CATAWBA NUCLEAR STATION, UNIT 1

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 312 Renewed License No. NPF-35

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. NPF-35 filed b y the Duke Energy Carolinas, LLC (licensee), dated June 9, 2021, as supple mented by letter dated July 16, 2021, with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules a nd 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 1

- 2 -

2. Accordingly, the license is amended by changes to the Technical Specif ications, as indicated in the attachment to this license amendment, and Para graph 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 312 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-35 and Technical Specifications

Date of Issuance: J une 14, 2022 DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-414

CATAWBA NUCLEAR STATION, UNIT 2

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 308 Renewed License No. NPF-52

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Renewed Facility Operating License No. NPF-52 filed b y the Duke Energy Carolinas, LLC (licensee), dated June 9, 2021, as supple mented by letter dated July 16, 2021, complies with the standards and requiremen ts 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 2

- 2 -

2. Accordingly, the license is amended by changes to the Technical Specif ications, as indicated in the attachment to this license amendment, and Para graph 2.C.(2) of Renewed Facility Operating License No. NPF-52 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 308, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-52 and the Technical Specifications

Date of Issuance: J une 14, 2022 ATTACHMENT TO

CATAWBA NUCLEAR STATION, UNITS 1 AND 2

LICENSE AMENDMENT NO. 312

RENEWED FACILITY OPERATING LICENSE NO. NPF-35

DOCKET NO. 50-413

AND LICENSE AMENDMENT NO. 308

RENEWED FACILITY OPERATING LICENSE NO. NPF-52

DOCKET NO. 50-414

Replace the following pages of the Renewed Facility Operating L icenses and the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area s of change.

Remove Insert

License License NPF-35, Page 4 NPF-35, Page 4 NPF-52, Page 4 NPF-52, Page 4

Technical Specifications Technical Specifications 1.3-3 1.3-3 1.3-7 1.3-7 1.3-8 1.3-8 3.7.5-1 3.7.5-1 3.8.1-2 3.8.1-2 3.8.1-4 3.8.1-4 3.8.1-7 3.8.1-7 3.8.9-1 3.8.9-1 3.8.9-2 3.8.9-2

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 312 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report

The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4),

following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(4) Antitrust Conditions

Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.

(5) Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated September 25, 2013; as supplemented by letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016; and, January 26, 2017, as approved in the SE dated February 8, 2017. 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.

Renewed License No. NPF -35 Amendment No. 312

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 308 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report

The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4),

following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(4) Antitrust Conditions

Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.

(5) Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated September 25, 2013; as supplemented by letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016; and, January 26, 2017, as approved in the SE dated February 8, 2017. 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.

Renewed License No. NPF-52 Amendment No. 308 Completion Times 1.3

1.3 Completion Times (continued)

DESCRIPTION (continued) The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery..."

(continued)

Catawba Units 1 and 2 1.3-3 Amendment Nos.312/308 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. OneA.1 Restore Function X7 days Function X train to OPERABLE train status.

inoperable.

B. OneB.1 Restore Function Y72 hours Function Y train to OPERABLE train status.

inoperable.

C. OneC.1 Restore Function X72 hours Function X train to OPERABLE train status.

inoperable.

OR AND

One C.2 Restore Function Y72 hours Function Y train to OPERABLE train status.

inoperable.

(continued)

Catawba Units 1 and 2 1.3-7 Amendment Nos. 312/308 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

(continued)

Catawba Units 1 and 2 1.3-8 Amendment Nos. 312/308 AFW System 3.7.5

3.7 PLANT SYSTEMS

3.7.5 Auxiliary Feedwater (AFW) System

LCO 3.7.5 Three AFW trains shall be OPERABLE.

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

Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

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

LCO 3.0.4.b is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One steam supply to A.1 Restore affected equipment7 days turbine driven AFW to OPERABLE status.

pump inoperable.

OR

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

Only applicable if Mode 2 has not been entered following refueling.

One turbine driven AFW pump inoperable in MODE 3 following refueling.

B. One AFW trainB.1 Restore AFW train to72 hours inoperable in MODE 1, 2 OPERABLE status.

or 3 for reasons other than Condition A.

(continued)

Catawba Units 1 and 2 3.7.5-1 Amendment Nos. 312/308 AC Sources - Operating 3.8.1

ACTIONS

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

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One LCO 3.8.1.a offsiteA.1 Perform SR 3.8.1.1 for1 hour circuit inoperable. required OPERABLE offsite circuit(s). AND

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter

AND

A.2 Declare required feature(s)24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power discovery of no available inoperable when offsite power to one its redundant required train concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND

A.3 Restore offsite circuit to72 hours OPERABLE status.

Catawba Units 1 and 2 3.8.1-2 Amendment Nos. 312/308 AC Sources - Operating 3.8.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

B. (continued)B.5 Evaluate availability of1 hour Emergency Supplemental Power Source (ESPS). AND

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter

AND

B.6 Restore DG to OPERABLE72 hours from status. discovery of unavailable ESPS

AND

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of Condition B entry 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months concurrent with unavailability of ESPS

AND

14 days

Catawba Units 1 and 2 3.8.1-4 Amendment Nos. 312/308 AC Sources - Operating 3.8.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

D. (continued)D.4.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) is not inoperable due to common cause failures.

OR

D.4.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

AND

D.5 Evaluate availability of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ESPS.

AND

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND

D.6 Restore LCO 3.8.1.d DG to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from OPERABLE status. discovery of unavailable ESPS

AND

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of Condition D entry 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months concurrent with unavailability of ESPS

AND

14 days

Catawba Units 1 and 2 3.8.1-7 Amendment Nos. 312/308 Distribution Systems - Operating 3.8.9

3.8 ELECTRICAL POWER SYSTEMS

3.8.9 Distribution Systems Operating

LCO 3.8.9 Train A and Train B AC, four channels of DC, DC Train A and Train B and four AC vital buses electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more ACA.1 Restore AC electrical8 hours electrical power power distribution distribution subsystem(s) subsystem(s) to inoperable. OPERABLE status.

B. One AC vital busB.1 Restore AC vital bus2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. subsystem to OPERABLE status.

(continued)

Catawba Units 1 and 2 3.8.9-1 Amendment Nos. 312/308 Distribution Systems - Operating 3.8.9

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

C. One channel of DCC.1 Restore channel of DC2 hours electrical power electrical power distribution distribution subsystems subsystems to OPERABLE inoperable. status.

D. One train of DCD.1 Restore DC electrical2 hours electrical power power distribution distribution subsystems subsystem to OPERABLE inoperable. status.

E. Required Action andE.1 Be in MODE 3.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

E.2 Be in MODE 5.36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

F. Two trains withF.1 Enter LCO 3.0.3.Immediately inoperable distribution subsystems that result in a loss of safety function.

Catawba Units 1 and 2 3.8.9-2 Amendment Nos. 312/308 DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-369

MCGUIRE NUCLEAR STATION, UNIT 1

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 322 Renewed License No. NPF-9

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Renewed Facility Operating License No. NPF-9, filed by the Duke Energy Carolinas, LLC (licensee), dated June 9, 2021, as supple mented by letter dated July 16, 2021, complies with the standards and requiremen ts 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 3

- 2 -

2. Accordingly, the license is amended by changes to the Technical Specif ications, as indicated in the attachment to this license amendment, and Para graph 2.C.(2) of Renewed Facility Operating License No. NPF-9 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 322, are hereby incorporated into this renewed operating license. The licensee shall operate the faci lity in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-9 and the Technical Specifications

Date of Issuance: J une 14, 2022 DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-370

MCGUIRE NUCLEAR STATION, UNIT 2

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 301 Renewed License No. NPF-17

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated June 9, 2021, as su pplemented by letter dated July 16, 2021,complies with the standards and requ irements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis sions 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 4

- 2 -

2. Accordingly, the license is amended by changes to the Technical Specif ications, as indicated in the attachment to this license amendment, and Para graph 2.C.(2) of Renewed Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 301, are hereby incorporated into this renewed operating license. The licensee shall operate the faci lity in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-17 and the Technical Specifications

Date of Issuance: J une 14, 2022 ATTACHMENT TO

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2

LICENSE AMENDMENT NO. 322

RENEWED FACILITY OPERATING LICENSE NO. NPF-9

DOCKET NO. 50-369

AND

LICENSE AMENDMENT NO. 301

RENEWED FACILITY OPERATING LICENSE NO. NPF-17

DOCKET NO. 50-370

Replace the following pages of the Renewed Facility Operating L icenses and the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area s of change.

Remove Insert

License License NPF-9, Page 3 NPF-9, Page 3 NPF-17, Page 3 NPF-17, Page 3

Technical Specifications Technical Specifications 1.3-3 1.3-3 1.3-7 1.3-7 1.3-8 1.3-8 3.7.5-1 3.7.5-1 3.8.1-2 3.8.1-2 3.8.1-4 3.8.1-4 3.8.9-1 3.8.9-1 3.8.9-2 3.8.9-2

(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components;

(5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and;

(6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level

The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 322, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report

The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than June 12, 2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed License No. NPF-9 Amendment No. 322

(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components;

(5) Pursuant to the Act and 10 CFR Parts, 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as my be produced by the operation of McGuire Nuclear Station, Units 1 and 2; a nd,

(6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such by product material as may be produced by the Duke Training and Technology Center.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or thereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level

The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 301 are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report

The Updated Final Safety Analysis Report supplement submitted p ursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.

Duke shall complete these activities no later than March 3, 2023, and shall notify the NRC in writing when implementation of these activ ities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior C ommission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise compl ies with the requirements in that section.

Renewed License No. NPF-17 Amendment No. 301 Completion Times 1.3

1.3 Completion Times

DESCRIPTION The above Completion Time extension does not apply to a Completion (continued) Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery..."

(continued)

McGuire Units 1 and 2 1.3-3 Amendment Nos. 322/301 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. OneA.1 Restore Function X7 days Function X train to OPERABLE train status.

inoperable.

B. OneB.1 Restore Function Y72 hours Function Y train to OPERABLE train status.

inoperable.

C. OneC.1 Restore Function X72 hours Function X train to OPERABLE train status.

inoperable.

OR AND

One C.2 Restore Function Y72 hours Function Y train to OPERABLE train status.

inoperable.

(continued)

McGuire Units 1 and 2 1.3-7 Amendment Nos. 322/301 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be in consistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that r esult in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropr iately extended.

(continued)

McGuire Units 1 and 2 1.3-8 Amendment Nos. 322/301 AFW System 3.7.5

3.7 PLANT SYSTEMS

3.7.5 Auxiliary Feedwater (AFW) System

LCO 3.7.5 Three AFW trains shall be OPERABLE.

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

Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

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

LCO 3.0.4.b is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One steam supply toA.1 Restore affected equipment7 days turbine driven AFW to OPERABLE status.

pump inoperable.

OR

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

Only applicable if MODE 2 has not been entered following refueling.

One turbine driven AFW pump inoperable in MODE 3 following refueling.

B. One AFW trainB.1 Restore AFW train to72 hours inoperable in MODE 1, 2 OPERABLE status.

or 3 for reasons other than Condition A.

(continued)

McGuire Units 1 and 2 3.7.5-1 Amendment Nos. 322/301 AC Sources - Operating 3.8.1

ACTIONS

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

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One LCO 3.8.1.a offsiteA.1 Perform SR 3.8.1.1 for1 hour circuit inoperable. required OPERABLE offsite circuit(s). AND

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter

AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from A.2 Declare required feature(s)discovery of no with no offsite power offsite power to one available inoperable when train concurrent with its redundant required inoperability of feature(s) is inoperable. redundant required feature(s)

AND

A.3 Restore offsite circuit to72 hours OPERABLE status.

McGuire Units 1 and 2 3.8.1-2 Amendment No. 322/301 AC Sources - Operating 3.8.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

B. (continued)B.5 Evaluate availability of1 hour Emergency Supplemental Power Source (ESPS). AND

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter

AND

B.6 Restore DG to OPERABLE72 hours from status. discovery of unavailable ESPS

AND

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of Condition B entry 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months concurrent with unavailability of ESPS

AND

14 days

McGuire Units 1 and 2 3.8.1-4 Amendment No. 322/301 Distribution Systems - Operating 3.8.9

3.8 ELECTRICAL POWER SYSTEMS

3.8.9 Distribution Systems Operating

LCO 3.8.9 Train A and Train B AC, four channels of DC, and four AC vital buses electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more ACA.1 Restore AC electrical8 hours electrical power power distribution distribution subsystem(s) subsystem(s) to inoperable. OPERABLE status.

B. One AC vital busB.1 Restore AC vital bus2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. subsystem to OPERABLE status.

(continued)

McGuire Units 1 and 2 3.8.9-1 Amendment No. 322/301 Distribution Systems - Operating 3.8.9

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

C. One channel of DCC.1 Restore DC channel of2 hours electrical power electrical power distribution distribution subsystem subsystem to OPERABLE inoperable. status.

D. Required Action andD.1 Be in MODE 3.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

D.2 Be in MODE 5.36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

E. Two trains withE.1 Enter LCO 3.0.3.Immediately inoperable distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.9.1 Verify correct breaker alignments and voltage to AC, DC, In accordance with and AC vital bus electrical power distribution subsystems. the Surveillance Frequency Control Program

McGuire Units 1 and 2 3.8.9-2 Amendment No. 322/301 DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-269

OCONEE NUCLEAR STATION, UNIT 1

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 423 Renewed License No. DPR-38

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 1 (ONS-1, the facility), Renewed Facility Operating License No. DPR-38, f iled by Duke Energy Carolinas, LLC (the licensee), dated June 9, 2021, as su pplemented by letter dated July 16, 2021, complies with the standards and req uirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis sions 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 5

- 2 -

2. Accordingly, the license is hereby amended by page changes to the Techn ical Specifications as indicated in the attachment to this license a mendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-38 are hereby amended to read as follows:

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revise d through Amendment No. 423 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Spe cifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed License No. DPR-38 and the Technical Specifications

Date of Issuance: J une 14, 2022 DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-270

OCONEE NUCLEAR STATION, UNIT 2

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 425 Renewed License No. DPR-47

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 2 (ONS-2, the facility), Renewed Facility Operating License No. DPR-47, f iled by Duke Energy Carolinas, LLC (the licensee), dated June 9, 2021, as su pplemented by letter dated July 16, 2021, complies with the standards and req uirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis sions 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 6

- 2 -

2. Accordingly, the license is hereby amended by page changes to the Techn ical Specifications as indicated in the attachment to this license a mendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revise d through Amendment No. 425 are hereby incorporated into the license. Th e licensee shall operate the facility in accordance with the Tech nical Specifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed License No. DPR-47 and the Technical Specifications

Date of Issuance: J une 14, 2022 DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-287

OCONEE NUCLEAR STATION, UNIT 3

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 424 Renewed License No. DPR-55

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 3 (ONS-3, the facility), Renewed Facility Operating License No. DPR-55, f iled by Duke Energy Carolinas, LLC (the licensee), dated June 9, 2021, as su pplemented by letter dated July 16, 2021, complies with the standards and req uirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis sions 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 7

- 2 -

2. Accordingly, the license is hereby amended by page changes to the Techn ical Specifications as indicated in the attachment to this license a mendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revise d through Amendment No. 424 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Spe cifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed License No. DPR-55 and the Technical Specifications

Date of Issuance: J une 14, 2022 ATTACHMENT TO

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3

LICENSE AMENDMENT NO. 423

RENEWED FACILITY OPERATING LICENSE NO. DPR-38

DOCKET NO. 50-269

LICENSE AMENDMENT NO. 425

RENEWED FACILITY OPERATING LICENSE NO. DPR-47

DOCKET NO. 50-270

LICENSE AMENDMENT NO. 424

RENEWED FACILITY OPERATING LICENSE NO. DPR-55

DOCKET NO. 50-287

Replace the following pages of the Renewed Facility Operating L icenses and the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area s of change.

Remove Insert

License License

DPR-38, Page 3 DPR-38, Page 3 DPR-47, Page 3 DPR-47, Page 3 DPR-55, Page 3 DPR-55, Page 3

Technical Specifications Technical Specifications

1.3-3 1.3-3 1.3-6 1.3-6 1.3-7 1.3-7 3.6.5-1 3.6.5-1 3.7.5-1 3.7.5-1 3.8.1-3 3.8.1-3 3.8.1-7 3.8.1-7

- 3 -

A. Maximum Power Level

The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2610 megawatts thermal.

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 4 23 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest.In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability ofparticipating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶ 1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of

Renewed License No. DPR-38 Amendment No. 423

A. Maximum Power Level

The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2610 megawatts thermal.

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 4 25 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest.In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability ofparticipating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶ 1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of

Renewed License No. DPR-47 Amendment No. 4 25

A. Maximum Power Level

The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2610 megawatts thermal.

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 4 24 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest.In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability ofparticipating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶ 1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of

Renewed License No. DPR-55 Amendment No. 4 24

Completion Times 1.3

1.3 Completion Times

DESCRIPTION The above Completion Time extension does not apply to a Completion (continued) Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery..."

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

B. RequiredB.1 Be in MODE 3.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5.36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

OCONEE UNITS 1, 2, & 3 1.3-3 Amendment Nos. 423, 425, & 424 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One A.1 Restore Function X7 days Function X train to OPERABLE train status.

inoperable.

B. One B.1 Restore Function Y72 hours Function Y train to OPERABLE train status.

inoperable.

C. One C.1 Restore Function X72 hours Function X train to OPERABLE train status.

inoperable.

OR AND C.2 Restore Function Y72 hours One train to OPERABLE Function Y status.

train inoperable.

OCONEE UNITS 1, 2, & 3 1.3-6 Amendment Nos. 423, 425, & 424 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be in consistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that r esult in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropr iately extended.

OCONEE UNITS 1, 2, & 3 1.3-7 Amendment Nos. 423, 425, & 424 Reactor Building Spray and Cooling Systems 3.6.5

3.6 CONTAINMENT SYSTEMS

3.6.5 Reactor Building Spray and Cooling Systems

LCO 3.6.5 Two reactor building spray trains and three reactor building cooling trains shall be OPERABLE.

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

Only one train of reactor building spray and two trains of reactor building cooling are required to be OPERABLE during MODES 3 and 4.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NO TE--------------------------------------------------------

LCO 3.0.4 is not applicable for Unit 2.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One reactor buildingA.1 Restore reactor 7 days spray train inoperable in building spray train to MODE 1 or 2. OPERABLE status.

B. One reactor buildingB.1 Restore reactor 7 days cooling train inoperable building cooling train to in MODE 1 or 2. OPERABLE status.

(continued)

OCONEE UNITS 1, 2, & 3 3.6.5-1 Amendment Nos. 423, 425, & 424 EFW System 3.7.5

3.7 PLANT SYSTEMS

3.7.5 Emergency Feedwater (EFW) System

LCO 3.7.5 The EFW System shall be OPERABLE as follows:

a. Three EFW pumps shall be OPERABLE, and

b. Two EFW flow paths shall be OPERABLE.

NO TE------------------------------------------

Only one motor driven emergency feedwater (MDEFW) pump and one EFW flow path are required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

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

LCO 3.0.4.b is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One MDEFW pumpA.1 Restore MDEFW pump 7 days inoperable in MODE 1, to OPERABLE status.

2, or 3.

B. Turbine driven EFWB.1 Restore turbine driven 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pump inoperable in EFW pump and EFW MODE 1, 2, or 3. flow path to OPERABLE status.

OR

One EFW flow path inoperable in MODE 1, 2, or 3.

(continued)

OCONEE UNITS 1, 2, & 3 3.7.5-1 Amendment Nos. 423, 425, & 424 AC Sources - Operating 3.8.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

C. KHU or its required C.1 Perform SR 3.8.1.3 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if not performed in overhead emergency OPERABLE KHU. previous 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months power path inoperable due to reasons other AND than Condition A.

Once per 7 days thereafter

AND

C.2.1 Restore the KHU and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months its required overhead emergency power path to OPERABLE status.

OR

C.2.2.1 Energize both standby 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months buses from LCT via isolated power path. AND

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from subsequent discovery of deenergized standby bus

AND

C.2.2.2 Suspend KHU 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months generation to grid except for testing.

AND (continued)

OCONEE UNITS 1, 2, & 3 3.8.1-3 Amendment Nos. 423, 425, & 424 AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

D. (continued) AND

D.3 Restore KHU and its 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months required underground emergency power path to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for one unit associated Completion Time not met for AND Required Action D.2.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for other unit(s)

AND

E.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months

F. Zone overlap protectionF.1 Restore zone overlap 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuitry inoperable protection circuitry to when overhead OPERABLE status.

electrical disconnects for KHU associated with OR the underground power path are closed. F.2 Open overhead 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months electrical disconnects for KHU associated with the underground power path.

G. Both emergency power G.1 Restore one breaker to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months paths inoperable due to OPERABLE status.

one inoperable E breaker and one inoperable S breaker on the same main feeder bus.

(continued)

OCONEE UNITS 1, 2, & 3 3.8.1-7 Amendment Nos. 423, 425, & 424 DUKE ENERGY PROGRESS, LLC

DOCKET NO. 50-261

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 270 Renewed License No. DPR-23

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Energy Progress, LLC ( the licensee),

dated June 9, 2021, as supplemented by letter dated July 16, 20 21, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations s et 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.

Enclosure 8

- 2 -

2. Accordingly, the license is amended by changes to the Technical Specif ications, as indicated in the attachment to this license amendment. Paragra ph 3.B. of Renewed Facility Operating License No. DPR-23 is hereby amended to read as follows:

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 270 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuan ce and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed License No. DPR-23 and Technical Specifications

Date of Issuance: J une 14, 2022 ATTACHMENT TO

H.B ROBINSON STEAM ELECTRIC PLANT, UNIT 2

LICENSE AMENDMENT NO. 270

RENEWED FACILITY OPERATING LICENSE NO. DPR-23

DOCKET NO. 50-261

Remove Insert

License License

Page 3 P age 3

Technical Specifications Technical Specifications

1.3-2 1.3-2 1.3-6 1.3-6 1.3-7 1.3-7 3.6-15 3.6-15 3.7-10 3.7-10 3.8-2 3.8-2 3.8-3 3.8-3 3.8-32 3.8-32

3

D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components;

E. 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 operation of the facility.

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

A. Maximum Power Level

The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 270 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.

Renewed Facility Operating License No. DPR-23 Amendment No. 270 Completion Times 1.3 1.3 Completion Times

DESCRIPTION However, when a subsequent train, subsystem, component, or (continued) variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.

To apply this Completion Time extension, two criteria must first be met.

The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery..."

(continued)

HBRSEP Unit No. 2 1.3-2 Amendment No. 270 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One A.1 Restore Function X7 days Function Xtrain to train OPERABLE status.

inoperable.

B. One B.1 Restore Function Y72 hours Function Ytrain to train OPERABLE status.

inoperable.

C. One C.1 Restore Function X72 hours Function Xtrain to train OPERABLE status.

inoperable.

OR AND C.2 Restore Function Y72 hours One train to Function YOPERABLE status train inoperable.

(continued)

HBRSEP Unit No. 2 1.3-6 Amendment No. 270 Completion Times 1.3

1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be in consistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that r esult in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropr iately extended.

(continued)

HBRSEP Unit No. 2 1.3-7 Amendment No. 270 Containment Spray and Cooling Systems 3.6.6

3.6 CONTAINMENT SYSTEMS

3.6.6 Containment Spray and Cooling Systems

LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One containment spray A.1 Restore containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train inoperable. spray train to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months

C. One containment cooling C.1 Restore containment 7 days train inoperable. cooling train to OPERABLE status.

(continued)

HBRSEP Unit No. 2 3.6-15 Amendment No. 270 AFW System 3.7.4

3.7 PLANT SYSTEMS

3.7.4 Auxiliary Feedwater (AFW) System

LCO 3.7.4 Four AFW flow paths and three AFW pumps shall be OPERABLE.

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

Only one AFW flow path with one motor driven pump is r equired to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is being used for heat removal.

ACTIONS

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

LCO 3.0.4.b is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One AFW pump inoperable A.1 Restore AFW pump or 7 days in MODE 1, 2, or 3. flow path(s) to OPERABLE status.

OR

One or two AFW flow paths inoperable in MODE 1, 2, or 3.

B. Two motor driven AFW B.1 Restore one motor 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pumps inoperable in driven AFW pump or MODE 1, 2, or 3. one flow path to OPERABLE status.

OR

Three motor driven AFW flow paths inoperable in MODE 1, 2, or 3.

(continued)

HBRSEP Unit No. 2 3.7-10 Amendment No. 270 AC Sources-Operating 3.8.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status

B. One DG inoperable. B.1 Perform SR 3.8.1.1 for the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months offsite circuit.

AND

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND

B.2 Declare required feature(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from supported by the discovery of inoperable DG inoperable Condition B when its required concurrent with redundant feature(s) is inoperability of inoperable. redundant required feature(s)

AND

B.3.1 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG

OR

B.3.2.1 Determine OPERABLE DG 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is not inoperable due to common cause failure.

AND

(continued)

HBRSEP Unit No. 2 3.8-2 Amendment No. 270 AC Sources-Operating 3.8.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

B. (continued) ------------------NOTE -------------------

Not required to be performed when the cause of the inoperable DG is pre-planned maintenance and testing.

B.3.2.2 Perform SR 3.8.1.2 for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months OPERABLE DG.

AND

B.4 Restore DG to 7 days OPERABLE status.

C. Two offsite circuits C.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable. feature(s) inoperable discovery of when its redundant Condition C required feature(s) is concurrent with inoperable. inoperability of redundant required features

AND

C.2 Restore one offsite circuit 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to OPERABLE status.

(continued)

HBRSEP Unit No. 2 3.8-3 Amendment No. 270 Distribution Systems-Operating 3.8.9

3.8 ELECTRICAL POWER SYSTEMS

3.8.9 Distribution Systems-Operating

LCO 3.8.9 Train A and Train B AC, DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One AC electrical power A.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months distribution subsystem power distribution inoperable. subsystem to OPERABLE status.

B. One AC instrument bus B.1 Restore AC instrument 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months subsystem inoperable. bus subsystem to OPERABLE status.

C. One DC electrical power C.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months distribution subsystem power distribution inoperable. subsystem to OPERABLE status.

(continued)

HBRSEP Unit No. 2 3.8-32 Amendment No. 270 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATED TO

DUKE ENERGY CAROLINAS, LLC AND DUKE ENERGY PROGRESS, LLC

CATAWBA NUCLEAR STATION, UNITS 1 AND 2

DOCKET NOS. 50-413, 50-414

AMENDMENT NOS. 312 AND 308 TO RENEWED FACILITY OPERATING

LICENSE NOS. NPF-35 AND NPF-52

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2

DOCKET NOS. 50-369, 50-370

AMENDMENT NOS. 322 AND 301 TO RENEWED FACILITY OPERATING

LICENSE NOS. NPF-9 AND NPF-17

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3

DOCKET NOS. 50-269, 50-270, 50-287

AMENDMENT NOS. 423, 425, AND 424 TO RENEWED FACILITY OPERATING

LICENSE NOS. DPR-38, DPR-47, AND DPR-55

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2

DOCKET NO. 50-261

AMENDMENT NO. 270 TO RENEWED FACILITY OPERATING LICENSE NO. DPR -23

1.0 INTRODUCTION

By application dated June 9, 2021, 1 as supplemented by letter dated July 16, 2021, 2 the licensee Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, collectively referred to henceforth as Duke Energy, requested changes to the Technical Specifications (TSs) for Catawba Nuclear Station (CNS), Units 1 and 2; McGuire Nuclear Station (MNS), Units 1 and 2; Oconee Nuclear Station (ONS), Units 1, 2 and 3; and H. B. Robinson Steam Electric Plant (RNP), Unit 2, (collectively, the facilities).

1 Agencywide Documents Access and Management System (ADAMS) Accession No ML21160A008.

2 ADAMS Accession No ML21197A046.

Enclosure 9

The amendment would revise the facilities TSs to adopt with cer tain variances Technical Specifications Task Force (TSTF) Traveler TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO [Limiting Condition for Operation], dated June 20, 2005. 3 The U.S. Nuclear Regulatory Commission (NRC or the Commission) approved the traveler on January 11, 2006 4 generically for plants to adopt through license amendment requests. Specifically, the amendment would d elete second completion times (CTs) from the affected required actions contained in the TSs, would remove the example contained in TS 1.3, Completion Times, and would add a discussion about alternating between TS conditions.

The supplement letter dated July 16, 2021, provided additional information that clarified the application, did not expand the scope of the application as ori ginally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register (FR) on August 10, 2021, (86 FR 43686).

2.0 REGULATORY EVALUATION

2.1 System Description

2.1.1 Completion Times

The CT is the amount of time allowed for completing a required action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an action condition unless otherwise specified, provided the unit is in a mode or specified condition stated in the applicability of the LCO. Required actions must be completed prior to the expiration of the specified CT. An action condition remains in effect, and the required actions apply until the condition no longer exists or the unit is not within the LCO applicability.

The Description section of the facilities TS 1.3, Completion Times, states, in part, that:

Once a condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Time based on initial entry into the Condition, unless otherwise specified.

Certain required actions included a second CT to establish a li mit on the maximum time allowed for any combination of CTs that result in a single, continuous failure to meet the LCO. The intent of these second CTs, such as limits on the period of time from discovery of the failure to meet the LCOs discussed b e l o w, was to prevent repeated entry and exi t from alternating TS required actions.

2.1.2 Containment/Reactor Building Spray and Cooling Systems

The facilities containment/ Reactor Building spray and containment cooling systems provide containment atmosphere cooling to limit post-accident pressure and temperature in containment to less than the design values. In the event of a d esign basis accident (DBA),

3 ADAMS Accession No. ML051860296.

4 ADAMS Accession No. ML060120272.

reduction of containment/Reactor Building pressure and the iodine removal capability of the spray reduces the release of fission product radioactivity from containment to the environment to within limits. Oconee TS LCO 3.6.5, Reactor Building Spray and Cooling Systems, required actions A.1 and B.1, and Robinson TS LCO 3.6.6, Containment Spray and Cooling Systems, Required Actions A.1 and C.1 have a second CT of 14 days and 10 days respectively from discovery of failure to meet the LCO. The Catawba and McGuire TSs do not have a second CT for the analogous LCO for its containment spray system.

2.1.3 Alternating Current ( A C ) Sources - Operating

The facilities Class 1E AC sources consist of the offsite power sources and the onsite standby power sources (diesel generators (DGs)). Catawba, McGuire, Oconee, and Robinson TS LCO 3.8.1, AC Sources - Operating, r equired actions ((A.3 and B.6 for Catawba and McGuire), (C.2.1 and D.3 for Oconee) and (A.3 and B.4 for Robinson)) have a second CT of 17 days from discovery of failure to meet LCO 3.8. 1.a or b for Catawba and McGuire, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from discovery of inoperable KHU [Keowee Hydro Units] for Oconee, and 10 days from discovery of failure to meet LCO for Robinson.

2.1.4 Distribution Systems - Operating

The facilities onsite Class 1E AC and DC electrical power distribution systems are divided into redundant and independent electrical power distribution su bsystems. Catawba, McGuire, and Robinson TS LCO 3.8.9, Distribution Systems-Operating, r equired actions A.1, B.1, C.1, and D.1 for Catawba and A.1, B.1, and C.1 for McGuire and Robinson have a second CT of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet the LCO. The Oconee TSs do not have a second CT for TS LCO 3.8.9.

2.1.5 Auxiliary/Emergency Feedwater (A/E FW) System

The facilities AFW/Emergency System automatically supplies fee dwater to the steam generators to remove decay heat from the Reactor Coolant System upon the loss of normal feedwater supply. Catawba, McGuire, and Oconee TS LCO 3.7.5 (3.7.4 for Robinson),

Auxiliary/Emergency Feedwater System, r equired actions A.1 and B.1 have a second CT of 10 days (8 days for Robinson) from discovery of failure to meet the LCO.

2.2 Proposed TS Changes

The licensee proposed to delete the following statement from th e facilities TS 1.3:

Example 1.3-3 illustrates one use of this type of Completion Ti me. The 10-day Completion Time specified for Condition A and B in Example 1.3-3 may not be extended.

In addition, in Example 1.3-3, for all facilities, the licensee proposed to delete the AND 10 days from discovery of failure t o meet the LCO from the CT of Condition A and Condition B.

Also, the licensee proposed to delete the following statement from the facilities TS 1.3:

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10-day Completion measured from the time it was

discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. The separate Completion Time modified by the phrase from discovery of failure to meet the LCO is designed to prevent indefinite continued operation while not meeting the LCO. This Completion Time allows for an exception to the normal time zero for beginning the Completion Time "clock." In this instance, the Completion Time time zero is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.

For all facilities, the licensee proposed to replace the paragraph above with the following:

It is possible to alternate between Conditions A, B, and C in s uch a manner that operation could continue indefinitely without ever restoring sy stems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to li mit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not i nappropriately extended.

The licensee also proposed to delete the second CTs associated with the following TS LCOs required actions:

Proposed changes to Catawba TSs:

o TS 3.7.5, Auxiliary Feedwater (AFW) System, Required Actions A.1 and B.1 o TS 3.8.1, AC Sources - Operating, Required Actions A.3, B.6, and D.6 o TS 3.8.9, Distribution Systems-Operating, Required Actions A.1, B.1, C.1, and D.1

Proposed changes to McGuire TSs:

o TS 3.7.5, Auxiliary Feedwater (AFW) System, Required Actions A.1 and B.1 o TS 3.8.1, AC Sources - Operating, Required Actions A.3 and B.6 o TS 3.8.9, Distribution Systems-Operating, Required Actions A.1, B.1, and C.1

Proposed changes to Oconee TSs:

o TS 3.6.5, Reactor Building Spray and Cooling Systems, Require d Actions A.1 and B.1 o TS 3.7.5, Emergency Feedwater (EFW) System, Required Actions A.1 and B.1 o TS 3.8.1, AC Sources - Operating, Required Actions C.2.1 and D.3

Proposed changes to Robinson TSs:

o TS 3.6.6, Containment Spray and Cooling Systems, Required Ac tions A.1 and C.1 o TS 3.7.4, Auxiliary Feedwater (AFW) System, Required Actions A.1 and B.1 o TS 3.8.1, AC Sources - Operating, Required Actions A.3 and B.4

o TS 3.8.9, Distribution Systems-Operating, Required Actions A.1, B.1, and C.1

The licensee proposed various variations from TSTF-439, Revision 2, which do not affect its applicability. Specifically, the variations include numbering and format differences as well as plant specific configurations as evaluated in Section 3.2 of this SE.

2.3 Regulatory Requirements and Guidance Documents

The NRC staff reviewed the proposed changes to eliminate TS second CTs against the criteria in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 and the precedent established in NUREG-1430, "Standard Technical Specifications [STS], Babcock

& Wilcox (B&W) Plants," R e v is i o n 55 and NUREG-1431, "Standard Technical Specifications

[STS], Westinghouse Plants," Revision 5.6 The ONS site has three Babcock & Wilcox pressurized water reactors, whereas, CNS, MNS, and RNP have Wes tinghouse pressurized water reactors. Section 50.36 requires applicants for nuclear power plant operating licenses to include TS as part of the license.

These TS are derived from the plant safety analyses. In 10 CFR 50.36, the NRC established its regulatory requirements related to the content of the TS, which include ( 1) safety limits, limiting safety systems settings and control settings, (2) LCOs, (3) surveillan ce requirements, (4) design features, and (5) administrative controls.

In NUREG-1430 and NUREG-1431, a second CT was included in the STS for certain r equired actions to establish a limit on the maximum time allowed for any combination of conditions that would result in a single continuous failure to meet the LCO. These CTs (henceforth referred to as second CT) are joined by an AND logical connector to the condition-specific CT and state X days from discovery of failure to meet the LCO (where X varies by specification). The intent of the second CT was to preclude entry into and out of the acti ons for an indefinite period of time without meeting t h e LCO. The second CT provides a limit on the amount of time the LCO would not be met for various combinations of conditions. TSTF-439, Revision 2, deletes these second CTs from the affected STS required actions.

Section 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants and specifically, 10 CFR 50.65(a)(1), the Maintenance Rule, requires each licensee to monitor the performance or condition of structures, systems, and components (SSCs) against licensee-established goals in a manner sufficient to provide reasonable assurance that the SSCs are capable of fulfilling thei r intended functions. These goals must be established commensurate with safety and, where practical, t ake into account industrywide operating experience. When the performance or condition of a st ructure, system, or component does not meet established goals, appropriate corrective action must be taken. Under 10 CFR 50.65(a)(3), the effectiveness of these performance and condition monitoring activities, and associated goals and preventive m a i n t e n a n c e activities, must be evaluated at least every refueling cycle, not to exceed 24 months. The goals must be established commensurate with safety and, where practical, take into account industry-wide op erating experience.

5 ADAMS Accession No. ML21272A363.

6 ADAMS Accession No. ML21259A155.

On January 11, 2006, t h e N R C s t a f f a p p r o v e d TSTF-439 Revision 2, submitted by the TSTF on June 20, 2005, to revise the improved STS for individual plants to voluntarily adopt.

3.0 TECHNICAL EVALUATION

3.1 Evaluation of Proposed Changes to Technical Specifications

The licensee's license amendment request (LAR) stated the follo wing regarding the 10 CFR 50.65 Maintenance Rule (MR):

Under 10 CFR 50.65(a)(4), the risk impact of all inoperable risk-significant equipment is assessed and managed when performing preventative or corrective maintenance. The risk assessments are conducted using the procedures and guidance endorsed by Regulatory Guide 1.160, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. (Reference 5)

Regulatory Guide 1.160 endorses the Revision 4A of NUMARC 93-01, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, (Reference 6). These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to:

plan and conduct other activities in a manner that controls overall risk,

increased risk awareness by shift and management personnel,

reduce the duration of the condition,

minimize the magnitude of risk increases through the establishment of backup success paths or compensatory measures,

and determination that the proposed maintenance is acceptable.

This comprehensive program provides much greater assurance of safe plant operation than the second Completion Times in the TS.

In addition, the licensee's LAR stated the following regarding performance indicators:

Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guideline, describes the tracking and reporting of performance indicators to support the NRC's Reactor Oversight Process (ROP)

(Reference 7). The NEI document is endorsed by Regulatory Issue Summary (RIS) 2001-11, Voluntary Submission of Performance Indicator Data (Reference 8). NEI 99-02, Section 2.2, describes the Mitigating Systems Cornerstone. NEI 99-02 specifically addresses Emergency AC Sources, which encompasses the AC Sources and Distribution System LCOs, and the Auxiliary Feedwater System. Extended unavailability of these systems due to multiple entries into the ACTIONS would affect the NRC's evaluation of the licensee's performance under the ROP.

The licensees LAR stated the following regarding administrative controls:

In addition to these programs, a requirement is added to Section 1.3 of the TS to require licensees to have administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls should consider plant risk and shall limit the maximum contiguous time of failing to meet the LCO. This TS requirement, when considered with the regulatory processes discussed above, provide an equivalent or superior level of plant safety without the unnecessary complication of the TS by second Completion Times on some Specifications.

As part of the implementation process for this TS change, Duke Energy plans to add a statement similar to the following to the approp riate fleet procedure for CNS, MNS, ONS, and RNP.

It is possible to alternate between TS Conditions in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so is inconsistent with the basis of the Completion Times. Therefore, the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO shall be limited.

Prior to the promulgation of 10 CFR 50.65, TS were the primary rules governing operations, including what equipment must normally be in service, how long equipment can be out of service, compensatory actions, and surveillance testing to demonstrate equipment readiness. One goal of TS is to provide adequate assurance of the availability and reliability of equipment needed to prevent and, if necessary, mitigate, accidents and transients. The MR supports this goal by requiring a comprehensive process for performance and condition monitoring activities. As required by 10 CFR 50.65 (b)(1)(2), the licensee assesses and manages inoperable risk-significant equipment. Under the TS, the CT for one system within an LCO is not generally affected by inoperable equipment in another LCO. However, the second CT influenced the CT for one system based on the condition of another system, but only if the two systems were required by the same LCO. Plant-specific MR programs implement risk-based configuration management programs that augment the deterministic CTs in the TS. The performance and condition monitoring activities required by 10 CFR 50.65 identify poor maintenance practices that would result from multiple entries into the actions of the TS which would contribute to unacceptable unavailability of these SSCs.

The NRC staff finds the proposed changes to all facilities TS 1.3 acceptable because administrative control requirements were added in Example 1.3-3 of all facilities TS to limit the maximum time allowed for any combination of conditions that result in a single continuous occurrence of failing to meet the LCO and ensuring CTs are not inappropriately extended. In addition, the licensees MR program requires the f acilities to monitor the performance or conditions of SSCs in a manner sufficient to provide reasonable assurances that SSCs can fulfill their specified safety functio ns and thus preventing indefinite operation without restoration of the systems.

The licensee also proposes to delete the second CT associated with the TS LCOs required actions described in Section 2.2 of this SE. These additional secondary CTs were specified for these instances to prevent repeated entry and exit from alternating TS required actions.

Administrative controls will replace second CTs as described in the licensee's LAR. The NRC staff finds the proposed deletion of second CTs acceptable since multiple, continuous entries into TS conditions, without meeting the LCO, will be adequately controlled by: (1) the licensee's administrative controls, (2) the configuration risk management programs as implemented to meet the requirements of the MR to assess and manage risk and performance indicators, and (3) the requirements of Section 1.3 of the TS, Completion Times. In addition, the NRC staff finds the MR provides adequate assurance against inappropriate use of combinations of TS conditions that result in a single continuous occurrence of failing to meet the LCO. Accordingly, consistent with TSTF-439, Revision 2, the NRC staff finds the proposed changes to all facilities T S to delete the secondary CTs described in Section 2.2 of this SE t o b e a c c e p t a b l e.

3.2 Evaluation of Variations

The LAR identified variations from TSTF-439 associated with numbering differences and site-specific features as discussed below:

3.2.1 Catawba Nuclear Stations variations from TSTF-439

For CNS, Units 1 and 2, the licensee proposed to make changes to delete the second CT associated with the following TS LCO Required Actions and bases : TS 3.8.1, A.3, B.6, and D.6; and TS 3.8.9, A.1, B.1, C.1, and D.1. In its supplement dated J uly 16, 2021, the licensee discusses the variations from TSTF-439, that LCO 3.8.1.a and LCO 3.8.1.b were added for clarification by Amendment Nos. 304 and 300. The variation from TSTF-439 to delete a maximum CT (i.e., second CT) that has the clarifiers of LCO 3.8.1.a and 3.8.1.b instead of LCO is administrative and does not affect the applicability of TSTF-439 to the 17-day CT of CNS TS 3.8.1, Required Action A.3 and B.6. Similarly, the LCO 3.8.1.c and LCO 3.8.1.d were added to clarify opposite unit AC sources by Amendment Nos. 304 and 300 and is therefore administrative and does not affect the applicability of TSTF-439 to the 17-day CT of CNS TS 3.8.1, Required Action D.6. Based on the information in the supplement, the NRC staff concludes that the variations are administrative and do not aff ect the applicability of TSTF-439, and thus, the NRC staff finds the variations acceptable.

3.2.2 McGuire Nuclear Stations variations from TSTF-439

For MNS, Units 1 and 2, the licensee proposed to make changes to delete the second CT associated with the following TS LCO Required Actions and bases : TS 3.8.1, A.3 and B.6; TS 3.8.9, A.1, B.1, and C.1. In its supplement dated July 16, 2021, the licensee discusses the variations from TSTF-439, that LCO 3.8.1.a and LCO 3.8.1.b were added for clarification by Amendment Nos. 314 and 293. The variation from TSTF-439 to dele te a maximum CT (i.e.,

second CT) that has the clarifiers of LCO 3.8.1.a and 3.8.1.b instead of LCO is administrative and does not affect the applicability of TSTF-439 to the 17-day CT of MNS TS 3.8.1, Required Action A.3 and B.6. Based on the information in the supplement, the NRC staff concludes that the variations are administrative and do not aff ect the applicability of TSTF-439, and thus, the NRC staff finds the variations acceptable.

3.2.3 Oconee Nuclear Station variations from TSTF-439

For ONS, Units 1, 2 and 3, the licensee proposed to make changes to delete the second CT associated with the following TS LCO Required Actions and bases : TS 3.8.1, C.2.1 and D.3. In

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its supplement dated July 16, 2021, the licensee discusses the variations from TSTF-439, that discovery of an inoperable KHU is a failure to meet ONS LCO 3.8.1 because the LCO requires two KHUs to be OPERABLE. Therefore, stating from discovery of inoperable KHU instead of from discovery of failure to meet the LCO does not affect the applicability of TSTF-439 to the second CTs of ONS TS 3.8.1, Required Actions C.2.1 and D.3. Based on the information in the supplement, the NRC staff concludes that the variations do not affect the applicability of TSTF-439, and t hus, the NRC staff finds the variations acceptable.

3.2.4 H. B. Robinson Steam Electric Plant variations from TSTF-439

For RNP, Unit 2, the licensee proposed to make changes to delet e the second CT associated with the following TS LCO Required Actions and bases: TS 3.8.1, A.3 and B.4; and TS 3.8.9, A.1, B.1, and C.1. The NRC staff evaluated the deletion of the second CTs listed above and determined that the licensees administrative controls would ad equately limit the maximum time allowed for any combination of Conditions that result in a single continuous occurrenc e of failing to meet the LCO. The NRC staff noted that these changes a re consistent with NRC-approved Traveler TSTF-439, Revision 2. Additionally, the NRC staff finds that the proposed change to TS 1.3 that requires administrative co ntrols to ensure that the CTs are not inappropriat ely extended and the ROP coupled with the maintenance rule provide adequate assurance against inappropriate use of combinations of TS conditions that result in a single continuou s occurrence of failing to meet the LCO. Accordingly, the NRC staff finds th e that the proposed variations are acceptable.

3.3 Technical Evaluation Conclusion

The NRC staff reviewed the proposed changes to the TSs and foun d they are consistent with the approved TSTF-439, Revision 2 and meet the standards for TSs in 10 CFR 50.36. As required by 10 CFR 50.36(c)(2), the LCOs specify the lowest fun ctional capability or performance levels of equipment required for safe operation of the facility. The proposed changes assure that 1) the necessary quality of systems and components is maintained, 2) facility operation will be within safety limits, and 3) the LCOs will be met. Specifically, the NRC staff evaluated the deletion of the second CTs listed above and determined that the licensees administrative controls would adequately limit the maximum time allowed for any combination of Conditions that result in a single continuous occurrence of fai ling to meet the LCO. Additionally, the NRC staff finds that the ROP, coupled with the maintenance rule, provide adequate assurance against inappropriate use of combinations of TS condi tions that result in a single continuous occurrence of failing to meet the LCO. Accordingly, the NRC staff finds the proposed TS changes acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, officials of t he States of North Carolina and South Carolina were notified of the proposed issuance of the amendments on February 23, 2022. The State officials had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with re spect 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

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significant increase in individual or cumulative occupational or public radiation exposure. The Commission has previously issued a proposed finding that the am endments involve no significant hazards consideration, published in the Federal Register on August 10, 2021, (86 FR 43686) and there has been no public comment on such find ing. Accordingly, the amendments meet the eligibility cr iteria for categorical exclus ion 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 these amend ments.

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: R. Grover, NRR N.Khan, NRR

Date: June 14, 2022

ML22046A022 *bymemoML22025A205 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/STSB/BC*

NAME AHon RButler VCusumano DATE 02/14/2022 02/23/2022 01/26/2022 OFFICE NRR/DSS/SCPB(A) NRR/DEX/EEEB/BC OGC/NLO NAME SJone WMorton JEzell DATE 02/02/2022 02/14/2022 03/28/2022 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona NJordan (LHaeg for)

DATE 06/09/2022 06/14/2022

v t e Letter Sequence Approval
EPID:L-2021-LLA-0111, TSTF-439 (Approved, Closed)
Initiation Request Acceptance... Supplement Administration Questions Answers Results Approval Other: ML21200A158
MONTHYEAR2021-07-16 [Table View]

ML22046A022

Text

SUBJECT:

Dear Ms. Hamilton:

Enclosures:

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Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

2.2 Proposed TS Changes

3.0 TECHNICAL EVALUATION

3.3 Technical Evaluation Conclusion

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

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