Text

Issuance of Amendment Nos. 316 and 295 to Correct Editorial Error in Technical Specification 3.0 and Remove Expired Footnotes from TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1, and 3.8.4
	ML19184A585
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/08/2019
From:	Michael Mahoney; Plant Licensing Branch II
To:	Teresa Ray; Duke Energy Carolinas
	Mahoney M, NRR/DORL/LPL2-1, 415-3867
References
	EPID L-2019-LLA-0022
	Download: ML19184A585 (30)
	v • d • e

August 8, 2019 Mr. Thomas D. Ray Site Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 316 AND 295 TO CORRECT EDITORIAL ERROR IN TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 3.0.5 AND REMOVE EXPIRED FOOTNOTES FROM TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7,

3. 7.9, 3. 7.11, 3.8.1, AND 3.8.4 (EPID L-2019-LLA-0022)

Dear Mr. Ray:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 316 and 295 to Renewed Facility Operating License Nos. NPF-9 and NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively. The amendments revise the Technical Specifications (TSs) in response to the application from Duke Energy Carolinas, LLC dated February 5, 2019.

The amendments correct an editorial error in section 3.0, "SR [Surveillance Requirement]

APPLICABILITY," specifically, SR 3.0.5. The amendments also modify Technical Specification (TS) 3.5.2, "ECCS [Emergency Core Cooling System] - Operating," TS 3.6.6, "Containment Spray System," TS 3.7.5, "Auxiliary Feedwater (AFW) System," TS 3.7.6, "Component Cooling Water (CCW) System," TS 3.7.7, "Nuclear Service Water System (NSWS)," TS 3.7.9, "Control Room Area Ventilation System (CRAVS)," TS 3.7.11, "Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)," TS 3.8.1, "AC [Alternating Current] Sources - Operating," and TS 3.8.4, "DC [Direct Current] Sources - Operating" to remove expired TS footnotes.

A copy of the related Safety Evaluation is also enclosed.

T. Ray A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Michael Mahoney, ProJect Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosures:

1. Amendment No. 316 to NPF-9

2. Amendment No. 295 to NPF-17

3. Safety Evaluation cc: Listserv

UNITED STATES DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 316 Renewed License No. NPF-9

1. The U.S. 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 Duke Energy Carolinas, LLC (the licensee), dated February 5, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

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

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 316, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed License and Technical Specifications Date of Issuance: August 8, 2019

UNITED STATES WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS. LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 295 Renewed License No. NPF-17

1. The U.S. 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 February 5, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 2

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

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 295, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed License and Technical Specifications Date of Issuance: August 8, 201 9

ATTACHMENT AMENDMENT NO. 316 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AMENDMENT NO. 295 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NOS. 50-369 AND 50-370 Operating Licenses Replace the following pages of the Renewed Facility Operating Licenses with the attached

revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 Appendix A, "Technical Specifications," of Operating Licenses Replace the following pages of the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert TS 3.0-6 TS 3.0-6 TS 3.5.2-1 TS 3.5.2-1 TS 3.6.6-1 TS 3.6.6-1 TS 3.7.5-1 TS 3.7.5-1 TS 3.7.5-2 TS 3.7.5-2 TS 3.7.6-1 TS 3.7.6-1 TS 3.7.7-1 TS 3.7.7-1 TS 3.7.7-2 TS 3.7.7-2 TS 3.7.9-1 TS 3.7.9-1 TS 3.7.9-3 TS 3.7.9-3 TS3.7.11-1 TS 3.7.11-1 TS 3.8.1-4 TS 3.8.1-4 TS 3.8.4-1 TS 3.8.4-1

(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. 316, 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. 316

(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; and, (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 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 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. 295, 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 March 3, 2023, 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-17 Amendment No. 295

SR Applicability 3.0 3.0 SR APPLICABILITY (continued)

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

SR 3.0.5 Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO 3.0.9 for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will be identified in parentheses or footnotes.

McGuire Units 1 and 2 3.0-6 Amendment Nos. 316/295

EGGS-Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

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

1n MODE 3, both safety injection (SI) pump or RHR pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to perform pressure isolation valve testing per SR 3.4.14.1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.

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 not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months McGuire Units 1 and 2 3.5.2-1 Amendment Nos. 316/295

Containment Spray System 3.6.6 3.6 CONTAINME NT SYSTEMS 3.6.6 Containment Spray System LCO 3.6.6 Two containment spray 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 spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train inoperable. 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 not met. AND B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months SURVEILLANCE REQUIREMEN TS SURVEILLAN CE FREQUENCY SR 3. 6. 6. 1 -----------------------------------NO TE--------------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual and power In accordance with operated valve in the flow path that is not locked, sealed, the Surveillance or otherwise secured in position is in the correct position. Frequency Control Pro ram (continued)

McGuire Units 1 and 2 3.6.6-1 Amendment Nos. 316/295

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--------------------------------------------

0 n ly 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 equipment 7 days turbine driven AFW to OPERABLE status.

pump inoperable. AND OR 10 days from discovery of

NOTE------------ failure to Only applicable if MODE meet the LCO 2 has not been entered following refueling.

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

B. One AFW train 8.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable in MODE 1, 2 OPERABLE status.

or 3 for reasons other AND than Condition A.

10 days from discovery of failure to meet the LCO (continued)

McGuire Units 1 and 2 3.7.5-1 Amendment Nos. 316/295

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AND or B not met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Two AFW trains inoperable in MODE 1, 2, or 3.

D. Three AFW trains D. 1 -------------NO TE-------------

inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately one AFW train to OPERABLE status.

E. Required AFW train E.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.

McGuire Units 1 and 2 3.7.5-2 Amendment Nos. 316/295

CCW System 3.7.6

3. 7 PLANT SYSTEMS 3.7.6 Component Cooling Water (CCW) System LCO 3.7.6 Two CCW trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW train A.1 -------------NO TE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MOD E 4,"

for residual heat removal loops made inoperable by ccw.

Restore CCW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months McGuire Units 1 and 2 3.7.6-1 Amendment Nos. 316/295

NSWS 3.7.7

3. 7 PLANT SYSTEMS 3.7.7 Nuclear Service Water System (NSWS)

LCO 3.7.7 Two NSWS trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One NSWS train A.1 -------------NO TES------------

inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources- Operating,"

for emergency diesel generator made inoperable by NSWS.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," for residual heat removal loops made inoperable by NSWS.

Restore NSWS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and 8.1 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. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months McGuire Units 1 and 2 3.7.7-1 Amendment Nos. 316/295

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7. 7. 1 --------------------------------NO TE----------------------------------

1so lati on of NSWS flow to individual components does not render the NSWS inoperable.

Verify each NSWS manual, power operated, and In accordance with automatic valve in the flow path servicing safety related the Surveillance equipment, that is not locked, sealed, or otherwise Frequency Control secured in position, is in the correct position. Program SR 3.7.7.2 Verify each NSWS automatic valve in the flow path In accordance with servicing safety related equipment, that is not locked, the Surveillance sealed, or otherwise secured in position, actuates to the Frequency Control correct position on an actual or simulated actuation Program signal.

SR 3.7.7.3 Verify each NSWS pump starts automatically on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program McGuire Units 1 and 2 3.7.7-2 Amendment Nos. 316/295

CRAVS 3.7.9

3. 7 PLANT SYSTEMS 3.7.9 Control Room Area Ventilation System (CRAVS)

LCO 3.7.9 Two CRAVS trains shall be OPERABLE.

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

Th e control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies, During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRA VS train A.1 Restore CRAVS train to 7 days inoperable for reasons OPERABLE status.

other than Condition B.

B. One or more CRAVS B.1 Immediately trains inoperable due to Initiate action to implement inoperable CRE mitigating actions.

boundary in MODE 1,2,3, or 4.

AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND 90 days B.3 Restore CRE boundary to OPERABLE status.

C. Required Action and C.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 or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

McGuire Units 1 and 2 3.7.9-1 Amendment No. 316/295

CRAVS 3.7.9 This page has been deleted McGuire Units 1 and 2 3.7.9-3 Amendment No. 316/295

ABFVES 3.7.11

3. 7 PLANT SYSTEMS

3. 7.11 Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)

LCO 3.7.11 Two ABFVES shall be OPERABLE .

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

The Auxiliary Building pressure boundary may be opened intermittently under administrat ive controls.

APPLICAB ILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITIO N REQUIRED ACTION COMPLETI ON TIME A. OneABFVE S A.1 Restore ABFVES to 7 days inoperable. OPERABLE status.

B. Two ABFVES B.1 Restore one ABFVES to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable. OPERABLE status.

C. Required Action and C.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 C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months McGuire Units 1 and 2 3.7.11-1 Amendmen t Nos. 316/295

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) 8.5 Evaluate availability of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 8.6 Restore DG to OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from status. discovery of unavailable ESPS 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of Condition B entry 2!

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months concurrent with unavailability of ESPS 14 days 17 days from discovery of failure to meet LCO 3.8.1.a or LCO 3.8.1.b McGuire Units 1 and 2 3.8.1-4 Amendme nt No. 316/295

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources- Operating LCO 3.8.4 The four channels of DC sources shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel of DC A.1 Restore channel of DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months source inoperable. source to OPERABLE status.

OR A.2.1 Verify associated bus tie 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months breakers are closed between DC channels.

AND A.2.2 Restore channel of DC 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months source 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 not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months McGuire Units 1 and 2 3.8.4-1 Amendment Nos. 314/295

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 316 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AND AMENDMENT NO. 295 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370

1.0 INTRODUCTION

By letter dated February 5, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML19042A117), Duke Energy Carolinas, LLC (the licensee) submitted a license amendment request to change the Technical Specifications (TSs) for the McGuire Nuclear Station (McGuire), Units 1 and 2. The amendments correct an editorial error in section 3.0, "SR [Surveillance Requirement] APPLICABILITY," specifically, SR 3.0.5.

The proposed amendments also revise TS 3.5.2, "ECCS [Emergency Core Cooling System] -

Operating," TS 3.6.6, "Containment Spray System," TS 3.7.5, "Auxiliary Feedwater (AFW)

System," TS 3.7.6, "Component Cooling Water (CCW) System," TS 3.7.7, "Nuclear Service Water System (NSWS)," TS 3.7.9, "Control Room Area Ventilation System (CRAVS)," TS 3.7.11, "Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)," TS 3.8.1, "AC

[Alternating Current] Sources - Operating," and TS 3.8.4, "DC [Direct Current] Sources -

Operating" to remove expired TS footnotes.

2.0 REGULATORY EVALUATION

2.1 Licensee's Proposed Changes Current TS SR 3.0.5 is as follows:

Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO [limiting condition for operation] 3.0.8 for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will identified by parentheses or footnotes.

Enclosure 3

The licensee proposed to revise TS SR 3.0.5 as follows:

Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO 3.0.9 for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will identified by parentheses or footnotes.

The licensee proposed to delete the following two footnotes from TS 3.5.2:

'A' Train ECCS is allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS

[McGuire Nuclear Station] LAR submittal correspondence letter MNS-17-031.

t For Unit 1 only, the Completion Time for Required Action A.1 may be extended one-time to 10 days during the 1A RHR AHU repair evolution and is contingent on meeting the compensatory measures described in MNS correspondence letter MNS-15-093. Upon completion of the repair evolution, this footnote is no longer applicable and will expire on March 31, 2016.

The licensee proposed to delete the following footnote from TS 3.6.6:

'A' Train Containment Spray is allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS-17-031.

The licensee proposed to delete the following footnote from TS 3.7.5:

'A' Train AFW is allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively

or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman

until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS-17-031.

The licensee proposed to delete the following footnote from TS 3.7.6:

'A' Train CCW is allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS-17-031.

The licensee proposed to delete the following footnote from TS 3. 7. 7:

'A' Train NSWS is allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS-17-031.

The licensee proposed to delete the following footnote from TS 3.7.9:

'A' Train CRAVS is allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned

to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS-17-031.

Note that subsequent to this proposed license amendment request, TS 3.7.9 was revised by amendment nos. 313 and 292, issued on April 18, 2019 (ADAMS Accession No. ML19050A297). TS 3.7.9, Limiting Condition for Operation, Condition G, "One or more CRAVS train(s) heater inoperable," and its associated Required Actions and Completion Times were deleted.

The licensee proposed to delete the following footnote from TS 3. 7 .11:

'A' Train ABFVES is allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS-17-031.

The licensee proposed to delete the following footnote from TS 3.8.1:

'A' Train EDGs are allowed to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS-17-031.

Note that subsequent to this proposed license amendment request, TS 3.8.1 was revised by amendment nos. 314 and 293, issued on June 28, 2019 (ADAMS Accession No. ML19126A030). Required Action B.4 was renamed to B.6 in those license amendments, as well as other changed to TS 3.8.1.

The licensee proposed to delete the following footnote from TS 3.8.4:

The Completion Time that one channel of DC source can be inoperable as specified by Required Action A.2.2 may be extended beyond the "72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months " for up to 14 days as part of the battery replacement project. This allowance may be used one-time for each of the four DC channels. Upon completion of the battery replacement project, this footnote is no longer applicable and will expire on December 31, 2016.

2.2 Applicable Regulations and Guidance In Title 1O of the Code of Federal Regulations (CFR) 50.36, the Commission established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TS are required to include items in the following five specific categories related to station operation:

(1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) Surveillance Requirements (SRs); (4) design features; and (5) administrative controls.

3.0 TECHNICAL EVALUATION

3.1 Change to SR 3.0.5 By letter dated March 29, 2007 (ADAMS Accession Package No. ML063100507), the NRC approved license Amendment Nos. 238 and 220, which added a new TS Limiting Condition for Operation (LCO) 3.0.8. The existing TS LCO 3.0.8 at that time was renumbered to TS LCO 3.0.9. However, the licensee inadvertently failed to provide the corresponding change to SR 3.0.5, which referenced the old TS LCO 3.0.8 (now TS LCO 3.0.9).

The proposed change to SR 3.0.5 would correct an editorial error and correct the reference LCO 3.0.8 (which should be LCO 3.0.9) in SR 3.0.5. The addition of LCO 3.0.8 was inserted as part of NRG-approved license amendments. The licensee inadvertently failed to provide the corresponding change to SR 3.0.5, and the NRC staff concludes that the proposed change corrects the editorial oversight and is, therefore, acceptable.

3.2 Deletion of TS Footnotes By letter dated September 10, 2014 (ADAM Accession No. ML14231A634), the NRC approved license Amendment Nos. 27 4 and 254, which allowed temporary changes for TS 3.8.4.

Specifically, the license amendments added a TS footnote which allowed a one-time extension to the CT for Required Action 2.2, to support replacement of the existing shared 125 Vdc vital batteries. The TS footnote expired on December 31, 2016. The NRC staff concludes that removal of the expired footnote is administrative in nature and is, therefore, acceptable.

By letter dated February 3, 2016 (ADAM Accession No. ML16004A352), the NRC approved license Amendment No. 281 for McGuire, Unit 1, which allowed temporary changes for TS 3.5.2. Specifically, the license amendments added a TS footnote which allowed a one-time extension to the Completion Time (CT) of Required Action A.1 to support maintenance on Residual Heat Removal (RHR) air handler unit 1A. The TS footnote associated with the one-time extension to the CT of Required Action A.1 to support maintenance on RHR air handler

unit 1A expired on March 31, 2016. The NRC staff concludes that removal of the expired footnote is acceptable.

By letter dated February 5, 2018 (ADAMS Accession No. ML18030A682), the NRC approved license Amendment Nos. 308 and 287, which allowed temporary changes for TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, and 3.8.1. Specifically, the license amendments added a TS footnote to the subject TSs which permitted the 'A' Train of NSWS to be inoperable for a total of 14 days to address a non-conforming condition on the NSWS 'A' Train supply piping from the Standby Nuclear Service Water Pond (SNSWP). The TS footnote expired on March 31, 2019.

The NRC staff concludes that removal of the expired footnotes is an administrative change and is, therefore, acceptable.

The proposed changes to TSs 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1 and 3.8.4 would remove temporary TS footnotes which were inserted as part of NRG-approved license amendments. The TS footnotes have expired; therefore, the NRC staff concludes the removal of TS footnotes TSs 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1 and 3.8.4 is acceptable.

3.3 NRC Staff Conclusion

The NRC staff finds that the proposed changes to TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1 and 3.8.4 and SR 3.0.5 are administrative changes which are non-technical in nature.

The NRC staff concludes that with the deletion of the expired TS footnotes in TSs 3.5.2, 3.6.6, 3.7.5, 3. 7.6, 3. 7. 7, 3. 7.9, 3.7.11, 3.8.1 and 3.8.4 and the correction of the editorial error in SR 3.0.5, McGuire, Units 1 and 2, continue to meet the regulatory requirements of 10 CFR 50.36 and is, therefore, the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the NRC staff notified the North Carolina State official of the proposed issuance of the amendments on July 2, 2019 (ADAMS Accession No. ML19183A476). The NRC staff confirmed on July 3, 2019, that the North Carolina State official had no comments.

5.0 PUBLIC COMMENTS On April 23, 2019 the NRC staff published a "Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing," in the Federal Register, regarding the license amendment request (84 FR 16893). In accordance with the requirements in 10 CFR 50.91, the notice provided a 30-day period for public comment on the proposed no significant hazards consideration determination. One comment from a member of the public was received, however it was not related to the no significant hazards consideration determination nor the LAR. The comment can be found at www.regulations.gov, reference NRC-2019-0099-0002.

6.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change inspections or SRs. The NRC staff has determined that the amendments involve no significant

increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there was one public comment on this finding, however it was not related to the no significant hazards consideration determination nor the license amendment request (84 FR 16893; April 23, 2019). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: M. Mahoney, NRR Date: August 8, 2019

T. Ray

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2- ISSUANCE OF AMENDMENT NOS. 316 AND 295 TO CORRECT EDITORIAL ERROR IN TECHNICAL SPECIFICATION 3.0 AND REMOVE EXPIRED FOOTNOTES FROM TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1, AND 3.8.4 (EPID L-2019-LLA-0022) DATED AUGUST 8, 2019 DISTRIBUTION:

PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrLAKGoldstein Resource RidsNrrLpl2-1 Resource RidsNrrPMMcGuire Resource RidsRgn2MailCenter Resource ADAMS Access1on No.: ML19184A585 *B,y E-ma1*1 OFFICE DORL/LPL2-1 /PM DORL/LPL2-1/LA* OGC-NLO*

NAME MMahoney KGoldstein JScro DATE 07/15/19 07/12/19 08/01/19 OFFICE DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME MMarkley MMahoney DATE 08/08/19 08/08/19 OFFICIAL RECORD COPY

v t e Letter Sequence Approval
EPID:L-2019-LLA-0022, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other: ML19224A038
MONTHYEAR2019-08-26 [Table View]

ML19184A585

Text

SUBJECT:

Dear Mr. Ray:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

3.3 NRC Staff Conclusion

4.0 STATE CONSULTATION

6.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

SUBJECT:

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