ML17003A019
| ML17003A019 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/08/2017 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Capps S D Duke Energy Carolinas |
| Miller G E, NRR/DORL/LPL2-1, 415-2481 | |
| References | |
| CAC MF7682, CAC MF7683 | |
| Download: ML17003A019 (15) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 8, 2017 Mr. Steven D. Capps 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NUCLEAR STATION, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS REGARDING CHANGE TO TECHNICAL SPECIFICATIONS (TS), REMOVAL OF SUPERSEDED TS REQUIREMENTS (CAC NOS. MF7682 AND MF7683)
Dear Mr. Capps:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 293 to Renewed Facility Operating License No. NPF-9 and Amendment No. 272 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 May 5, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16134A068), as supplemented by letter dated June 16, 2016 (ADAMS Accession No. ML 16180A 179). The amendments modify the Technical Specifications (TS) by removing a footnote from TS Table 3.3.2-1, which is no longer applicable, and by removing an expired footnote from TS 3.8.1. A copy of the related Safety Evaluation is also enclosed. The 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. 293 to NPF-9 2. Amendment No. 272 to NPF-17 3. Safety Evaluation cc w/enclosures: Distribution via Listserv Sincerely, /1 I I ! 1 f / //Ul{' 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. 293 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 (licensee), dated May 5, 2016, as supplemented by letter dated June 16, 2016, 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. 293, 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 30 days of issuance.
Attachment:
Changes to License No. NPF-9 and Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: March 8, 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. 272 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 May 5, 2016, as supplemented by letter dated June 16, 2016, 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 1 O 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. 272, 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 30 days of issuance.
Attachment:
Changes to License No. NPF-17 and Technical Specifications Date of Issuance: March 8, 201 7 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 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT NO. 293 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 272 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 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove 3.3.2-14 3.8.1-3 Insert 3.3.2-14 3.8.1-3 (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. 293 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-9 Amendment No. 293 (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. 272 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 1 O 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. 272 Table 3.3.2-1 {page 5 of 6) Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 6. Auxiliary Feedwater (continued) e. Trip of all Main Feedwater Pumps f. Auxiliary Feedwater Pump Suction Transfer on Suction Pressure -Low 7. Automatic Switchover to Containment Sump a. Refueling Water Storage Tank (RWST) Level -Low 1,2 1,2,3 1,2,3 REQUIRED SURVEILLANCE CHANNELS CONDITIONS REQUIREMENTS 1 per MFW pump 2 per MOP, 4 perTDP 3 K N,O P,S SR 3.3.2.7 SR 3.3.2.9 SR 3.3.2.7(a)(b) SR 3.3.2.8(a)(b) SR 3.3.2.9 SR 3.3.2.1 SR 3.3.2.3(a)(b) SR 3.3.2.8(a)(b) SR 3.3.2.9 ESFAS Instrumentation 3.3.2 ALLOWABLE VALUE NA 6.5 psig 7.5 psig (2A MOP only) 92.3 inches NOMINAL TRIP SETPOINT NA 7.0 psig 8.0 psig (2A MOP only) 95inches Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements. (continued) (a) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. (b) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR. NOTE 1: The Trip Setpoint for the Containment Pressure Control System start permissive/termination (SPIT) shall be 0.3 psig and.:::, 0.4 psig. The allowable value for the SPIT shall 0.25 psig and.:::, 0.45 psig. McGuire Units 1 and 2 3.3.2-14 Amendment Nos. 293/272 ACTIONS CONDITION B. (continued) B.4 C. Two offsite circuits C.1 inoperable. AND C.2 AC Sources -Operating 3.8.1 REQUIRED ACTION COMPLETION TIME Restore DG to OPERABLE 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s** status. AND 6 days from discovery of failure to meet LCO Declare required feature(s) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from inoperable when its discovery of redundant required Condition C feature(s) is inoperable. concurrent with inoperability of redundant required feature(s) Restore one offsite circuit 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to OPERABLE status. (continued) ** 'A' Train EDGs are allowed to be inoperable for a total of 14 days for the correction of a degraded condition on the 'A' Train 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 1, 2017 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 and Commitments as described in MNS LAR submittal correspondence letter MNS-16-005. McGuire Units 1 and 2 3.8.1-3 Amendment No. 293, 272 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 293 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AND AMENDMENT NO. 272 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 U.S. Nuclear Regulatory Commission (NRC, the Commission) dated May 5, 2016, as supplemented by letter dated June 16, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 16134A068 and ML 16180A179, respectively), Duke Energy Carolinas, LLC (Duke Energy) submitted an application seeking approval to change the Technical Specifications (TS) for McGuire Nuclear Station, Units 1 and 2 (MNS). The supplement dated June 16, 2016, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 5, 2016 (81 FR 43649). The amendments would modify the MNS TS by removing footnote (c) from TS Table 3.3.2-1, "Engineered Safety Feature Actuation System Instrumentation," which is no longer applicable, and by removing an expired footnote from TS 3.8.1, "AC Sources -Operating." By letter dated September 12, 2013 (ADAMS Accession No. ML 13262A500), as supplemented by letters dated May 20 and July 22, 2014 (ADAMS Accession Nos. ML 14161A231 and ML 14205A440, respectively), Duke Energy submitted a license amendment request (LAR) related to MNS TS 3.3.2, which was needed for plant modifications to install new equipment in support of NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML 12056A045). The NRC issued a license amendment on August 27, 2014 (ADAMS Enclosure 3 Accession No. ML 14211A403) approving the changes requested in the LAR, which included modifying TS Table 3.3.2-1 by adding footnote (c). The final plant modifications in support of EA-12-049 were completed in the fall of 2015 (during the MNS Unit 2 refueling outage). By letter dated June 7, 2007 (ADAMS Accession No. ML071590038), as supplemented by letter dated June 8, 2007 (ADAMS Accession No. ML071640098), Duke Energy submitted a one-time emergency LAR to add a footnote to TS 3.8.1. The LAR was need to support unanticipated repairs on the 1A Emergency Diesel Generator (EOG). The NRC issued a license amendment on June 8, 2007 (ADAMS Accession No. ML071570599) approving the changes. The 1A EOG repairs covered by the amendment have been completed, and the footnote expired on June 15, 2007, and is no longer applicable.
2.0 REGULATORY EVALUATION
In Title 10 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
The proposed changes to TS Table 3.3.2-1 and TS 3.8.1 are administrative, non-technical editorial changes only. The proposed change to TS Table 3.3.2-1 would remove a temporary footnote which was inserted as part of an NRG-approved license amendment to support the staggered implementation of plant modifications needed to comply with EA-12-049. The proposed change to TS 3.8.1 would delete a footnote, since expired, which allowed a one-time extension to the completion time for Required Action B.4 to support unanticipated 1A EOG repairs. 3.1 Licensee's Proposed Changes Duke Energy requests to delete footnote (c) from TS Table 3.3.2-1 related to FUNCTION 6.f. for Auxiliary Feedwater Pump Suction Transfer on Suction Pressure -Low. The footnote to be removed is the following: (c) Prior to completion of the AC independent AFW pump suction transfer scheme modification on the respective Unit, the Allowable Value for this Function is ::::3 psig (::::4 psig 2A MOP only) and the Nominal Trip Setpoint for this Function is 3.5 psig (4.5 psig 2A MOP only). Duke Energy requests to delete a footnote in TS 3.8.1 related to the COMPLETION TIME of REQUIRED ACTION 8.4 for the 1A EOG. The footnote to be removed is the following: *For Unit 1 only, the Completion Time that the 1A EOG can be inoperable as specified by Required Action B.4 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 6 days from discovery of failure to meet the LCO" up to a total of 10 days as part of the 1 A EOG Jacket/lntercooler Water Pump Motor repair. Upon completion of the repair and restoration, this footnote is no longer applicable and will expire at 17 41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> on June 15, 2007.
3.2 NRC Staff Conclusion
The NRC staff finds that the proposed changes to TS Table 3.3.2-1 and TS 3.8.1 are administrative editorial changes which are non-technical in nature. The proposed change to TS Table 3.3.2-1 would remove a temporary footnote which was inserted as part of an approved license amendment to support the staggered implementation of plant modifications needed to comply with EA-12-049. The final plant modifications were completed during the fall 2015 MNS Unit 2 refueling outage. Therefore, the NRC staff concludes the removal of footnote (c) in TS Table 3.3.2-1 is acceptable. The proposed change to TS 3.8.1 would delete a footnote which allowed a one-time extension to the completion time for Required Action 8.4 to support unanticipated 1A EOG repairs. The repairs covered by the footnote have been completed and the footnote is no longer applicable, as the footnote expired on June 15, 2007. Therefore, the NRC staff concludes the removal of the TS 3.8.1 footnote is acceptable. The NRC staff concludes that with the deletion of the footnotes, McGuire Nuclear Station, Units 1 and 2, continue to meet the regulatory requirements of 10 CFR 50.36 and is, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the North Carolina State official was notified of the proposed issuance of the amendments on January 1, 2017. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 1 O 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 (July 5, 2016, 81 FR 43649). 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: March 8, 2017
ML17003A019 OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1 /LA OGC-NLO with edits NAME MMahoney KGoldstein JWachutka DATE 1/12/2017 2/27/2017 1/17/2017 OFFICE NRR/DORL/LPL2-1 /BC NRR/DORL/LPL2-1 /PM NAME MMarkley MMahoney DATE 3/08/2017 3/08/2017