ML17277A313
| ML17277A313 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/31/2017 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Mahoney M, NRR/DORL/LPL2-1, 415-3867 | |
| References | |
| CAC MF9117, CAC MF9118, EPID L-20!7-LLA-0169 | |
| Download: ML17277A313 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 31, 2017 Mr. Steven 0. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1AND2 - ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-340-A, REVISION 3 (CAC NOS. MF9117 AND MF9118; EPID L-20!7-LLA-0169)
Dear Mr. Capps:
The U.S. Nuclear Regulatory Commission (NRG, the Commission) has issued the enclosed Amendment No. 304 to Renewed Facility Operating License No. NPF-9 and Amendment No. 283 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 amendments modify TS 3.7.5, "Auxiliary Feedwater (AFW) System," Limiting Condition for Operation {LCO) Condition A and Required Action A.1. The proposed changes expand Condition A by adding an OR statement to include a condition when one turbine driven AFW pump is inoperable in MODE 3, following refueling. A NOTE is also added to clarify that this expanded condition is only applicable if MODE 2 has not been entered, following refueling.
Required Action A.1 is revised to replace "steam supply" with "affected equipment" for Condition A operability.
The changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-340-A, Revision 3, "Allow 7 day Completion Time for a turbine-driven AFW pump inoperable."
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.
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Mi~~a;I ~honey, Pr~ct Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-367 and 50-370
Enclosures:
- 1. Amendment No. 304 to NPF-9
- 2. Amendment No. 283 to NPF-17
- 3. Safety Evaluation cc w/enclosures: Distribution via Listserv
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. 304 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. 304, 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 ll-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed License No. NPF-9 and Technical Specifications Date of Issuance: October 31, 2017
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. 283 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 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 1 O 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. 283, 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 Renewed License No. NPF-17 and Technical Specifications Date of Issuance: October 31, 2017
ATTACHMENT MCGUIRE NUCLEAR STATION, UNITS 1AND2 LICENSE AMENDMENT NO. 304 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 LICENSE AMENDMENT NO. 283 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 Insert NPF-9, page 3 NPF-9, page 3 NPF-17, 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 Insert TS 3.7.5-1 TS 3.7.5-1
(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduc~ 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°/o).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 304, 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. 304
(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 ls 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°/o).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 283, are hereby incorporated into this renewed operating license. The licensee shalt 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. 283
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------------------------------------------
On 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 B.1 Restore AFW train to 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s*
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. 304/283
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 304 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AMENDMENT NO. 283 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DUKE ENERGY CAROLINAS LLC MCGUIRE NUCLEAR STATION, UNITS 1AND2 DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated January 11, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17025A069), Duke Energy Carolinas, LLC (Duke, the licensee) submitted an application for approval to change the Technical Specifications (TSs) for McGuire Nuclear Station, Units 1 and 2 (McGuire).
The amendments modify TS 3.7.5, "Auxiliary Feedwater (AFW) System," Limiting Condition for Operation (LCO) Condition A and Required Action A. i. The proposed changes expand Condition A by adding an OR statement to include a condition when one turbine driven AFW pump is inoperable in MODE 3, following refueling. A NOTE is also added to clarify that this expanded condition is only applicable if MODE 2 has not been entered, following refueling.
Required Action A.1 is revised to replace "steam supply" with "affected equipment" for Condition A operability.
The licensee stated that the proposed changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-340-A, Revision 3, "Allow 7 day Completion Time for a turbine-driven AFW pump inoperable" (ADAMS Accession No. ML003687327). The NRG approved TSTF-340-A, Revision 3, by letter dated March 16, 2000 (ADAMS Accession No. ML003694199).
Enclosure 3
2.0 REGULATORY EVALUATION
2.1 Applicable Regulations and Guidance In Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical Specifications," the NRG established its regulatory requirements related to the content of TSs.
Pursuant to 10 CFR 50.36(c), TSs are required to include items in the following categories related to plant operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) surveillance requirements; (4) design features; and (5) administrative controls. However, the regulation does not specify the particular requirements to be included in a plant's TSs. The LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, the licensee shall follow any remedial actions permitted by the TS until the condition can be met or shall shut down the reactor.
Guidance for staff review of TSs is contained in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor]
Edition-Technical Specifications" (NUREG-0600, Chapter 16) (ADAMS Accession No. ML100351425). The NRC staff has prepared standard technical specifications (STSs) for each of the light-water reactor nuclear steam supply systems and associated balance-of-plant equipment systems. The guidance specifies that the NRG staff review of proposed TSs should determine whether their content and format are consistent with the applicable reference TSs (i.e., the current STSs). Where proposed TSs depart from the applicable reference TSs, the staff determines whether the proposed differences are justified by uniqueness in plant design or other considerations. The applicable current STSs for McGuire are contained in NUREG-1431, "Standard Technical Specifications - Westinghouse Plants," Revision 4.0 (ADAMS Accession No. ML12100A222).
The NRC incorporated TSTF-340-A, Revision 3, into NUREG-1431, Revision 2, and has maintained that change through the current revision, NUREG-1431, Revision 4.0.
2.2 Description of Auxiliary Feedwater System The McGuire AFW system is described in Section 10.4.10 of the McGuire Updated Final Safety Analysis Report (UFSAR). The AFW assures there is sufficient feedwater supply to the steam generators (SGs) to remove energy stored in the core and primary coolant, in the event of the loss of the normal feedwater system. The AFW system is designed to start automatically in the event of a loss of offsite power, a trip of all operating main feedwater pumps, a safety injection signal, or a low-low SG level.
Each unit at Catawba has a dedicated AFW system consisting of one turbine-driven AFW pump, two motor-driven AFW pumps, and associated piping, valves, and instrumentation. The motor-driven pumps normally each deliver flow to two SGs. The turbine-driven pump receives steam supplied via separate lines from the B and C SGs, and the motor-driven pumps receive electrical power from separate electrical divisions.
The AFW system is credited in accident analyses for a loss of offsite power, a loss of normal feedwater, and cooldown following a loss-of-coolant accident trough a small break, including an SG tube rupture. The alternating current (AC) power-independent turbine-driven AFW pump is relied upon to deliver adequate feedwater to cool the primary system following a loss of all onsite and offsite AC electrical power.
2.3 Licensee's Proposed Changes Current TS LCO 3. 7.5, Condition A, states:
CONDITION REQUIRED ACTION COMPLETION TIME
~. One steam supply to ,, 1 Restore steam supply 7 days turbine driven AFW to OPERABLE status.
pump inoperable. AND 10 Days from discovery of failure to meet the LCO Revised TS LCO 3. 7 .5, Condition A, would state:
CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore affected 7 days turbine driven AFW equipment to pump inoperable. OPERABLE status. AND OR 10 Days from discovery of failure to
NOTE ------------ meet the LCO Only applicable if MODE 2 has not been entered following refueling.
One turbine driven AFW pump inoperable in MODE 3 following refueling.
3.0 TECHNICAL EVALUATION
3.1 NRG Staff's Technical Evaluation of Licensee's Proposed Changes The NRC approved this change to the STS in NUREG-1431, Revision 1, on March 16, 2000.
This traveler revised Westinghouse Owners Group (WOG) STS 3.7.5, "Auxiliary Feedwater (AFW) System," to extend Condition A Completion Time to 7 days to restore an inoperable turbine-driven AFW steam supply, and to expand Condition A by adding an OR statement and a NOTE in the Condition. The added statement states, "One turbine driven AFW pump inoperable in MODE 3 following refueling," and the NOTE states, "Only applicable if MODE 2 has not been entered following refueling."
The McGuire TS LCO 3.7.5 currently allows a Completion Time of 7 days and 10 days from discovery of failure to meet the LCO; therefore, this part of the TSTF-340-A, Revision 3, change is not adopted by the licensee.
However, the licensee proposes to modify McGuire TS LCO 3.7.5, Condition A, so as to allow a 7-day Completion Time for the turbine-driven AFW pump being inoperable in MODE 3, immediately following a refueling outage, if MODE 2 has not been entered. This change was proposed on the basis that it could reduce the number of unnecessary mode changes by providing added flexibility in MODE 3 to repair and test the turbine-driven AFW pump, if the pump were to be declared inoperable following a refueling outage. In the proposed condition, there is minimal decay heat for the AFW system to have to remove through the SGs due to the time that irradiated fuel has decayed during the refueling outage and the replacement of irradiated fuel with un-irradiated fuel.
Based on the above, the NRC staff concludes that the proposed change would maintain the safe operation of the facility, given the redundant capabilities afforded by the AFW system, the time needed to perform repairs and testing on the turbine-driven AFW pump, and the low probability of an accident occurring during this time period that would require the operation of the turbine-driven AFW pump. In addition, there are alternate methods, such as feed and bleed, available to remove decay heat if necessary.
3.2 NRG Staff's Conclusion The NRC staff evaluated the proposed changes to McGuire TS LCO 3. 7.5 against the applicable regulations and guidance and found that the changes are consistent with those in the previously NRG-approved TSTF-340-A, Revision 3, and continue to ensure safe operation of the facility. The NRC staff concludes that the proposed changes continue to meet the requirements of 10 CFR 50.36 and, therefore, 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 October 2, 2017. The State official confirmed on October 16, 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 and Combined Licenses and Proposed No Significant Hazards Consideration Determination," in the Federal Register associated with the proposed amendment request (82 FR 23621). 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 proposed no significant hazards consideration determination or to the proposed amendment request. 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 NRG 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 published in the Federal Regis/er on May 23, 2017 (82 FR 23621). 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: M. Hamm, NRR S. Jones, NRR Date of issuance: October 31, 2017
ML17277A313 *b memorandum OFFICE DORULPL2-1/PM DORL/LPL2-1/LA DSS/STSB/BC(A)* DSS/SBPB/Bc*
NAME MMahoney KGoldstein JWhitman RDennig DATE 10/16/17 10/16/17 08/07/17 OGG /NLO subject to OFFICE email comment DORL/LPL2-1/BC DORL/LPL2-1/PM NAME JWachutka MMarkley MMahoney DATE 10/19/17 10/31/17 10/31/17