ML17240A354

McGuire Nuclear Station, Units 1 and 2 - Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-269-A, Revision 2 (CAC Nos. MF9114 and MF9115)

ML17240A354
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/18/2017
From:	Michael Mahoney Plant Licensing Branch II
To:	Capps S D Duke Energy Carolinas
Mahoney M
References
CAC MF9114, CAC MF9115
Download: ML17240A354 (17)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985 September 18, 2017

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1AND2-ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-269-A, REVISION 2 (CAC NOS. MF9114 AND MF9115)

Dear Mr. Capps:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 298 to Renewed Facility Operating License No. NPF-9 and Amendment No. 277 to Renewed Facility Operating License No. NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively.

The amendments are in response to your application dated January 11, 2017. The January 11, 2017, application included a request to adopt multiple Technical Specifications Task Force (TSTF) Travelers.

This letter only applies to the request related to TSTF-269-A, Revision 2, "Allow administrative means of position verification for locked or sealed valves."

The amendments modify Technical Specification (TS) 3.6.3, "Containment Isolation Valves,"

to add a Note to Required Actions A.2, C.2, and E.2 to allow isolation devices that are locked, sealed, or otherwise secured to be verified by use of administrative means. The changes are consistent with NRG-approved TSTF-269-A, Revision

2.

S. Capps A copy of the related Safety Evaluation is also enclosed.

Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket Nos. 50-369 and 50-370

Enclosures:

1. Amendment No. 298 to NPF-9 2. Amendment No. 277 to NPF-17 3. Safety Evaluation cc w/enclosures:

Distribution via Listserv Michael Mahoney, Pr ct Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 298 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 Duke Energy Carolinas, LLC (the licensee),

dated January 11, 2017, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations 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. 298, 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.

Attachment:

FOR THE NUCLEAR REGULATORY COMMISSION A ' . i; 0. -** "' .t-c-.r Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to Renewed License No. NPF-9 and Technical Specifications Date of Issuance:

Sep tern ber 18, 201 7 UNITED STATES NUCLEAR REGULATORY COMMISSION 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. 277 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 January 11, 2017, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 1 O 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. 277, 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.

Attachment:

FOR THE NUCLEAR REGULATORY COMMISSION

JJMU.w--Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to Renewed License No. NPF-17 and Technical Specifications Date of Issuance:

Sep tern be r 18, 201 7 ATTACHMENT TO MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT NO. 298 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 277 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 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 NPF-9, page 3 NPF-17, page 3 Insert NPF-9, page 3 NPF-17, page 3 Replace the following pages of the Appendix A Technical Specifications (TS) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove TS 3.6.3-2 TS 3.6.3-3 TS 3.6.3-4 Insert TS 3.6.3-2 TS 3.6.3-3 TS 3.6.3-4 (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 1 O 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 1 O 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. 298, 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. 298 (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. 277, 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. 277 ACTIONS CONDITION A. (continued)

A.2 B. ------------NOTE------------

B.1 Only applicable to penetration flow paths with two containment isolation valves. --------------------------------

One or more penetration flow paths with two containment isolation valves inoperable except for purge valve or reactor building bypass leakage not within limit. McGuire Units 1 and 2 Containment Isolation Valves 3.6.3 REQUIRED ACTION COMPLETION TIME ------------NOTES--------------

1. Isolation devices in high radiation areas may be verified by use of administrative means. 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. -----------------------------------

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated.

outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. (continued) 3.6.3-2 Amendment Nos. 298/277 ACTIONS (continued)

CONDITION C. ------------NOTE------------

C.1 Only applicable to penetration flow paths with only one containment isolation valve and a closed system. --------------------------------

AND One or more penetration C.2 flow paths with one containment isolation valve inoperable.

D. Reactor building bypass D.1 leakage not within limit. E. One or more penetration E.1 flow paths with one or more containment purge valves not within purge valve leakage limits. AND McGuire Units 1 and 2 Containment Isolation Valves 3.6.3 REQUIRED ACTION COMPLETION TIME Isolate the affected 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. -----------N 0 TES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means. 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. ----------------------------------

Verify the affected Once per 31 days penetration flow path is isolated.

Restore leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit. Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. (continued) 3.6.3-3 Amendment Nos. 298/277 ACTIONS CONDITION E. (continued)

E.2 AND E.3 F. Required Action and F.1 associated Completion Time not met. AND F.2 McGuire Units 1 and 2 Containment Isolation Valves 3.6.3 REQUIRED ACTION COMPLETION TIME

1. Isolation devices in high radiation areas may be verified by use of administrative means. 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. -----------------------------------

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated.

outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Perform SR 3.6.3.6 for the Once per resilient seal purge valves 92 days closed to comply with Required Action E.1. Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 3.6.3-4 Amendment Nos. 298/277 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 298 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AND AMENDMENT NO. 277 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 to the United States Nuclear Regulatory Commision (NRC) dated January 11, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17025A069),

Duke Energy Carolinas, LLC (Duke Energy) submitted an application to seek approval to change the Technical Specification (TSs) for McGuire Nuclear Station, Units 1 and 2 (McGuire).

This license amendment request (LAR) modifies TS 3.6.3, "Containment Isolation Valves,"

to add a Note to Required Actions A.2, C.2, and E.2 to allow isolation devices that are locked, sealed, or otherwise secured to be verified by use of administrative means. The licensee stated that this change is consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-269-A, Revision 2, "Allow administrative means of position verification for locked or sealed valves" (ADAMS Accession No. ML040620100).

The NRC approved TSTF-269, Revision 2 in a letter dated July 26, 1999 (ADAMS Legacy Accession No. 9907300113).

2.0 REGULATORY EVALUATION In Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, the Commission established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following categories related to station operation:

(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.

The regulation does not specify the particular requirements to be included in a plant's TSs. The NRC staff used Revision 3 of the WOG STS (ADAMS Accession No. ML041830612) in its review of the TS changes proposed for McGuire.

Enclosure 3 2.1 Licensee's Proposed Changes Current TS LCO 3.6.3, Condition A states, "One or more penetration flow paths with one containment isolation valve inoperable except for purge valve or reactor building bypass leakage not within limit." Required Action A.2 states, Verify the affected penetration flow path is isolated.

With a Completion Time of: Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment.

Current TS LCO 3.6.3, Condition C states, "One or more penetration flow paths with one containment isolation valve inoperable."

Required Action C.2 states, Verify the affected penetration flow path is isolated.

With a Completion Time of: Once per 31 days. Current TS LCO 3.6.3, Condition E states, "One or more penetration flow paths with one or more containment purge valves not within purge valve leakage limits."

Required Action E.2 states, Verify the affected penetration flow path is isolated.

With a Completion Time of: Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment.

Revised TS LCO 3.6.3 would add the following NOTE (as NOTE 2) under Required Actions A.2, C.2, and E.2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. The current NOTE for TS LCO 3.6.3 Required Actions A.2, C.2, and E.2 would be renumbered to be NOTE 1. 3.0 TECHNICAL EVALUATION TSTF-269-A, Revision 2, revised WOG STS 3.6.3, "Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)," by adding a note under Required Actions A.2, C.2, and E.2 that isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. Periodic verification is required for a penetration with an inoperable isolation valve in order to detect and correct inadvertent repositioning of the isolation device. Because the purpose of locking, sealing or securing components is to prevent inadvertent repositioning, the licensee proposed that periodic re-verification should be a verification of the administrative controls that ensure that the component remains in the required state. TS LCO 3.6.3 states, "Each containment isolation valve shall be OPERABLE."

The OPERABILITY requirements for isolation valves ensure that components are capable of performing their safety functions within the time limits assumed in the safety analyses.

Updated Final Safety Analysis Report Section 6.2.1.6.2 states that during plant operation certain tests and inspections are conducted to ensure the functional capability of containment and associated structures,

systems, and components (including the containment isolation valves).

It is reasonable to assume that the initial establishment of component status (i.e., closing of an isolation valve) was performed sufficiently, and subsequent, periodic re-verification of the administrative control is thus sufficient to demonstrate continued isolation.

Additionally, it is undesirable to remove the lock, seal, or other means of securing the component solely to perform an active verification of the components required state, as it would increase the possibility of mis-positioning the component due to frequent manipulations.

The NRC staff has reviewed the proposed changes to TS LCO 3.6.3 and has determined that the licensee's proposed use of administrative controls provides adequate assurance that the valves are maintained in the positions required by the plant safety analyses when primary and secondary containment are required to be operable.

3.1 NRC Staff's Conclusion Based on the above, the NRC staff concludes that the proposed TS changes, consistent with TSTF-269-A, Revision 2, would continue to meet the requirements of 10 CFR 50.36(c)(2)(i) and is, therefore, acceptable, since the proposed administrative controls provide reasonable assurance of plant safety.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the NRC staff notified the South Carolina State official of the proposed issuance of the amendments on August 16, 2017. The State official confirmed on September 6, 2017, that the State of North Carolina had no comments.

5.0 PUBLIC COMMENTS On May 23, 2017, 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 associated with the proposed amendment request (82 FR 23619). 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-2017-0120-0002.

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. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on this finding (82 FR 23619). 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.

7.0 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:

A. Smith, NRR Date: September 18, 2017 S.Capps

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-269-A, REVISION 2 (CAC NOS, MF9114 AND MF9115) DATED SEPTEMBER 18, 2017 DISTRIBUTION:

PUBLIC LPL2-1 R/F RidsACRS_MailCTR Resource RidsNrrLpl2-1 Resource RidsNrrDssStsb Resource RidsNrrDeEpnb Resource RidsNrrDssSbpb Resource RidsNrrPMMcGuire Resource RidsRgn2MailCenter Resource RidsNrrLALKGoldstein Resource ASmith, NRR ADAMS A ccess1on N ML17240A354 o.: OFFICE DORL/LPL2-1

/PM DORL/LPL2-1/LA NAME MMahoney KGoldstein DATE 08/30/17 08/30/17 OFFICE DSS/SBPB/BC OGC-NLO RDennig JGillespie NAME DATE 09/06/17 09/13/17

• b d 1y memoran um DSS/STSB/BC*

DE/EPNB/BC JWhitman DAiiey 06/06/17 09/05/17 DORL/LPL2-1/BC DORL/LPL2-1

/PM MMarkley (SWilliams for) MMahoney 09/15/17 09/18/17 OFFICIAL RECORD COPY