ML17269A198
| ML17269A198 | |
| 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 | |
| References | |
| CAC MF9100, CAC MF9101 | |
| Download: ML17269A198 (17) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON_ DC 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-352-A, REVISION t (CAC NOS. MF9100 AND MF9101; EPID L-2017-LLA-0170)
Dear Mr. Capps:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 302 to Renewed Facility Operating License No. NPF-9 and Amendment No. 281 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 the limiting condition for operation (LCO) for technical specification (TS) 3.4.10, "Pressurizer Safety Valves," TS 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," and TS 3.7.4, "Steam Generator Power Operated Relief Valves (SG PORVs)."
Specifically, the Completion Times (CTs) for TS LCO 3.4.10, Required Action B.2, and TS LCO 3.7.4, Required Action C.2, are modified from 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the CT for TS LCO 3.4.12, Required Action G.1, is modified from 8 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-352-A, Revision 1, "Provide Consistent Completion Time to Reach MODE 4."
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.
/;;1l(I/~
Michael Mahoney, Project 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. 302 to NPF-9
- 2. Amendment No. 281 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. 302 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. 302, 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-9 and Technical Specifications Date of Issuance: October 31, 2017
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 281 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 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. 281, 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 , 2 O1 7
ATTACHMENT TO MCGUIRE NUCLEAR STATION, UNITS 1AND2 LICENSE AMENDMENT NO. 302 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 281 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 3.4.10-1 TS 3.4.10-1 TS 3.4.12-4 TS 3.4. 12-4 TS 3.7.4-1 TS 3.7.4-1
(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. 302, 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. 302
(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 (100o/o).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 281, 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. 281
Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.1 O Three pressurizer safety valves shall be OPERABLE with lift settings?. 2435 psig and:: 2559 psig.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures> 300°F.
NOTE---------------------------------------------
The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.
B. Required Action and B.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 /> associated Completion Time not met. AND OR B.2 Be in MODE 4 with any 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I RCS cold leg temperatures Two or more pressurizer :'.': 300°F.
safety valves inoperable.
McGuire Units 1 and 2 3.4.10-1 Amendment Nos. 302/281
LTOP System 3.4.12 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. One PORV inoperable in E.1 Suspend all operations Immediately MODE 5 or6. which could lead to a water solid pressurizer.
AND E.2 Restore PORV to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.
F. Required Action and F.1. Verify RCS cold leg 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion temperature> 174°F (Unit Time of Condition E not 1) or > 89"F (Unit 2).
met.
AND F.2 Verify RHR suction relief valve is OPERABLE and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the suction isolation valves are open.
G. Two PORVs inoperable. G.1 Depressurize RCS and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> establish RCS vent of OR ~ 2.75 square inches.
Required Action and associated Completion Time of Condition C, D, or F not met.
OR LTOP System inoperable for any reason other than Condition A, B, C, D, E, or F.
McGuire Units 1 and 2 3.4.12-4 Amendment Nos. 302/281
SG PORVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Steam Generator Power Operated Relief Valves (SG PORVs)
LCO 3.7.4 Three SG PORV lines shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A One required SG PORV A.1 Restore required SG 7 days line inoperable. PORV line to OPERABLE status.
B. Two or more required B.1 Restore all but 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SG PORV lines one required SG PORV line inoperable. to OPERABLE status.
C. Required Action and C.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 /> associated Completion Time not met. AND C.2 Be in MODE 4 without 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reliance upon steam generator for heat removal.
McGuire Units 1 and 2 3.7.4-1 Amendment Nos. 3021281
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 302 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AMENDMENT NO. 281 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 would modify the Limiting Condition for Operation (LCO), Required Action B.2 for TS LCO 3.4.10, "Pressurizer Safety Valves," Required Action C.2 for TS LCO 3.7.4, "Steam Generator Power Operated Relief Valves (SG PORVs)," and Required Action G.1 for TS LCO 3.4.12, "Low Temperature Overpressure Protection {LTOP) System." Specifically, the Completion Times (CTs) for TS LCO 3.4.10, Required Action B.2, and TS LCO 3.7.4, Required Action C.2, would be modified to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) and the CT for TS LCO 3.4.12, Required Action G.1, would be modified to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />).
The licensee stated that the proposed changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-352-A, Revision 1, "Provide Consistent Completion Time to Reach MODE 4" (ADAMS Accession No. ML040630065).
The amendments would adopt previously NRG-approved TSTF-352-A, Revision 1, in order to bring the McGuire TSs into closer alignment with NUREG-1431, Revision 2.0, "Standard Technical Specifications - Westinghouse Plants" (ADAMS Accession No. ML011840223).
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 NRC 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.
The NRC did not issue a letter approving TSTF-352-A, Revision 1; however, this change was incorporated by the NRC into Revision 2.0 of the STS (ADAMS Accession Nos. ML011840211 and ML011840219) and has been maintained through the current revision.
2.2 Licensee's Proposed Changes Current Required Action B.2 of TS LCO 3.4.1 O states, "Be in MODE 4 with any RCS [Reactor Coolant System] cold leg temperatures s 300 °F," and has a CT of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed change would extend the CT to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Current Required Action C.2 of TS LCO 3.7.4, states "Be in MODE 4 without reliance upon steam generator for heat removal," and has a CT of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed change would extend the CT to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Current Required Action G.1 of TS LCO 3.4.12 states, "Depressurize RCS and establish RCS vent of~ 2. 75 square inches," and has a CT of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The prosposed change would extend the CT to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.0 TECHNICAL EVALUATION
3.1 NRC Staff's Technical Evaluation of Licensee's Proposed Changes TSTF-352-A, Revision 1, revised WOG STS 3.4.10, "Pressurizer Safety Valves, STS 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," STS 3.7.4, "Atmospheric Dump Valves (ADVs)," and STS 3.7.6, "Condensate Storage Tank (CST)." The revisions increased the CTs for Required Actions which direct entry into conditions below MODE 4 to allow sufficient time to safely perform the actions and changed the time to go from LTOP conditions to having the RCS vented to allow sufficient time to complete the activity. The NRC published STS NUREG-1431, Revision 2.0, in June 16, 2001. No formal communication was issued to approve this TSTF Traveler in particular, rather, the NRC incorporated TSTF-352-A, Revision 1, along with other approved TSTF Travelers into Revision 2.0 of NUREG-1431.
3.1.1 Extension of CT for TS LCO 3.4.10, Required Action 8.2 The current CT of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for TS LCO 3.4.10, Required Action B.2, is for a normal shutdown from MODE 1 to MODE 4 (average RCS temperature between 350 °F and 200 °F, according to TS 1.1, "Definitions," Table 1.1-1); however, TS LCO 3.4.10, Required Action 8.2, requires that the plant is required to be in MODE 4 at or below RCS cold-leg temperatures of 300 °F.
The 300 °F requirement is 50 °F below the highest average RCS temperature for entry into MODE 4 (average RCS temperature between 350 °F and 200 °F). The additional time is needed to reduce the RCS cold-leg temperature to no more than 300 °F in a safe and controlled manner. The NRC staff finds that it is reasonable to provide the additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow for the fact that the condition to be reached in TS LCO 3.4.10, Required Action 8.2, is a significantly lower RCS temperature (300 °F) than the RCS temperature (350 °F) for entry into MODE 4. Additionally, the proposed change is consistent with NRG-approved TSTF-352-A, Revision 1, and the WOG STS.
3.1.2 Extension of CT for TS LCO 3.7.4, Required Action C.2 Current TS LCO 3.7.4, Required Action C.2, requires the plant to be in MODE 4 without reliance upon steam generator (SG) for heat removal within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The licensee stated that this would require cooling to shutdown cooling entry conditions, which would be below the MODE 4 entry temperature (350 °F). The licensee stated that the additional time is needed for further cooldown and de pressurization of the RCS to shutdown cooling entry conditons. The NRG staff finds that it is reasonable to provide the additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow for a controlled further cooldown and depressurization of the RCS. Additionally, the proposed change is consistent with NRG-approved TSTF-352-A, Revision 1, and the WOG STS.
3.1.3 Extension of CT for TS LCO 3.4.12, Required Action G.1 Current TS LCO 3.4.12, Required Action G.1, requires the plant to depressurize RCS and establish RCS vent of at least 2. 75 inches within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The proposed change to is to extend the CT from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The licensee stated that 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is an insufficient amount of time to plan a Mode change, cool down (following the plan cooldown rate limits), plan and execute the maintenance activity of opening a vent, and cool the RCS sufficiently to safely open a vent. The NRG staff finds that it is reasonable to provide the additional 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to allow for a controlled de pressurization of the RCS and establish an RCS vent of at least 2. 75 inches.
Additionally, the proposed change is consistent with NRG-approved TSTF-352-A, Revision 1, and the WOG STS.
3.2 NRC Staff's Conclusion The NRC staff reviewed the proposed changes and determined that the extended CTs will allow additional time to establish the required plant conditions. The NRC staff determined that the extended CTs are necessary and appropriate to allow for a controlled entry into the required plant conditions as specified by TS LCO 3.4.10, Required Action 8.2, TS LCO 3.7.4, Required Action C.2, and TS LCO 3.4.12, Required Action G.1.
Based on the above, the NRC staff concludes that the proposed TS changes, consistent with TSTF-352-A, Revision 1, and the WOG STS, would continue to meet the requirements of 10 CFR 50.36(c)(2) and are, therefore, acceptable, since the minimum performance level of
equipment needed for safe operation of the facility is contained in the LCO, and the appropriate remedial measures are specified if the LCO is not met.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the NRG staff notified the North Carolina State official of the proposed issuance of the amendments on September 26, 2017. The State official confirmed on September 26, 2017, that the State of North Carolina had no comments.
5.0 PUBLIC COMMENTS On May 23, 2017, the NRG 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 23622). 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.requlations.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 published in the Federal Register on May 23, 2017 (82 FR 23622). 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 Date of issuance: October 31, 2017
S. Capps
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1AND2- ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-352-A, REVISION 1 (CAC NOS. MF9100AND MF9101; EPID L-2017-LLA-0170) DATED OCTOBER 31, 2017 DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsACRS_MailCTR Resource RidsNrrlpl2-1 Resource RidsNrrDssStsb Resource RidsNrrDeEicb Resource RidsNrrPMMcGuire Resource RidsRgn2MailCenter Resource RidsNrrLALKGoldstein Resource MHamm, NRR ADAMS A ccess1on N o. ML17269A198 .b>V memoran dum OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DE/EPNB/BC DSS/STSB/BC (A)'
NAME MMahoney KGoldstein SBailey JWhitman DATE 10/16/17 10/13/17 10/18/17 08/07/17 OGG /NLO subject to OFFICE email comments DORL/LPL2-1/BC DORL/LPL2-1/PM NAME JWachutka MMarkley MMahoney DATE 10/27/17 10/31/17 10/31/17 OFFICIAL RECORD COPY