ML14332A790
| ML14332A790 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/11/2014 |
| From: | Geoffrey Miller Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Miller G | |
| References | |
| TAC MF3444, TAC MF3445 | |
| Download: ML14332A790 (15) | |
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 December 11, 2014
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENTS REGARDING TECHNICAL SPECIFICATION 3.4.12; "LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM" (TAC NOS. MF3444 AND MF3445)
Dear Mr. Capps:
By letter dated January 28, 20141, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request to modify Technical Specification 3.4.12, "Low Temperature Overpressure Protection (L TOP) System." Specifically, the change removes a reference to Condition E when entering Condition G.
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 275 to Renewed Facility Operating License NPF-9 and Amendment No. 255 to Renewed Facility Operating Licenses NPF-17 for the McGuire Nuclear $tation, Units 1 and 2, respectively.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML14043A167.
If you have any questions, please call me at 301-415-2481.
Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 275 to NPF-9
- 2. Amendment No. 255 to NPF-17
- 3. Safety Evaluation cc w/encls: Distribution via Listserv Sin3btf~u~
G.
Miller, Project 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. 275 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 28, 2014, 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.
- 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. 275, 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 the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: December 11, 2014
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. 255 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 28, 2014, 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.
- 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. 255, are hereby incorporated into this renewed operating license. The licensee shall operate the facilityin 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 the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: December 11, 2014
ATTACHMENT TO LICENSE AMENDMENT NO. 275 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 255 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Licenses NPF-9, page 3 NPF-17, page 3 TSs 3.4.12-4 Licenses NPF-9, page 3 NPF-17, page 3 TSs 3.4.12-4
(4)
(5)
(6) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as requirecl 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 comporwnts; 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; 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 1 0 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 Soecifications contained in Appendix A, as revised through Amendment Nd 275 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, describec;j 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 1 0 CFR 50.59 and otherwise complies with the requirements in that section.
Renewed License.No. NPF-9 Amendment No: 275
. 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 C.FR 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 con.tain 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 (1 00%).
(2). Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No255are 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 A'nalysis 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."255.
ACTIONS (continued)
CONDITION E.
One PORV inoperable in MODE 5 or 6.
I F.
Required Action and associated Completion Time of Condition E not met.
G.
Two PORVs inoperable.
OR 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, i3, C, D, E, or F.
McGuire Units 1 and 2 REQUIRED ACTION E.1 Suspend all operations which could lead to a water solid pressurizer.
AND E.2 Restore PORV to OPERABLE status.
F.1.
Verify RCS cold leg temperature > 17 4 oF (Unit
- 1) or> 89°F (Unit 2).
AND F.2 Verify RHR suction relief valve is OPERABLE and the suction isolation valves are open.
G. 1 Depressurize RCS and establish RCS vent of
~ 2.75 square inches.
3.4.12-4.
LTOP System 3.4.12 COMPLETION TIME Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1 hour 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 8 hours L
Amendment Nos:*275, 255 I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 275 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 255 TO RENEWED FACILITY OPERATING LICENSE NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
By letter dated January 28, 2014, Duke Energy Carolinas, LLC (Duke Energy), the licensee for McGuire Nuclear Station, Units 1 and 2 (McGuire), requested to revise the McGuire Technical Specification (TS) (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML14043A167). The proposed revision would modify Technical Specification 3.4.12 for Low Temperature Overpressure Protection (L TOP) System to remove the reference to Condition E when entering Condition G.
The L TOP System controls reactor coolant system (RCS) pressure at low temperatures so the integrity of the reactor coolant pressure boundary (RCPB) is not compromised in low-temperature modes of operation. Limiting Condition for Operation (LCO) 3.4.12 provides overpressure protection by specifying a minimum coolant input capability and an adequate pressure relief capability.
The license proposes to revise TS 3.4.12 Condition G as follows, Two PORVs inoperable OR Required Action and associated Completion Time of Condition C, D,-, or F not met OR L TOP System inoperable for any reason other than Condition A, B, C, D, E, or F.
The licensee indicated that the reference to Condition E was inadvertently introduced during the conversion of the McGuire TSs to the Improved Standard Technical Specification format. The NRC staff evaluated the application to determine whether the removal of the reference to Condition E is technically justified.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (1 0 CFR), Part 50, Appendix A, General Design Criterion 14, Reactor Coolant Pressure Boundary states that the reactor coolant pressure boundary shall be designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal le.akage, of rapidly propagating failure, and of gross rupture.,
NUREG'-0800, "Standard Review Plant for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," Section 5.2.2, Overpressure Protection, states that for the application of safety and relief valves (SRVs) and the reactor protection system ensures overpressure protection for the RCPB during operation at power. The application of pressure-reli~ving systems that function during low-temperature operation ensures overpressure protection for the RCPB during low-temperature operation of the plant for startup and shutdown.
The Commission's regulatory requirements related to the content of the TS are contained in 10 CFR 50.36, 'Technical Specifications." Title 10 of the Code of Federal Regulations (1 0 CFR)
Part 50.36(c)(2) states, in part, that when a limiting condition for operation is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs.
The L TOP System controls RCS pressure at low temperatures so the integrity of the RCPB is not compromised by violating the pressure and temperature limits required by 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements."
3.0 TECHNICAL EVALUATION
3.1.
Summary of Technical Information Provided by Licensee To justify the removal of the reference to Condition E, the licensee's LAR states:
To establish the required redundancy in relief capacity, Required Action F.2 currently requires verifying that the residual heat removal (RHR) suction relief valve is operable and the suction isolation valves are open within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and Required Action G.1 currently requires depressurizing the RCS and establishing a RCS vent of ~ 2. 75 square inches within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Required Actions F.2 and G.1 are overly restrictive since either action is sufficient to compensate for the loss of one power-operated relief valve (PORV). As such, Condition G is being corrected to eliminate the reference to Condition. E so that alignment of an operable RHR suction relief valve is sufficient to compensate for the loss of one PORV. L TOP calculations support the use of the RHR suction relief valve as an alternative to one PORV.
3.2 Summary of NRC Staff Review The licensee's proposed change removes Condition E from Condition G for Required Action and associated Completion Time of Condition C, D, E, or F not being met forTS 3.4.12. The licensee states that Condition G is being corrected to eliminate the reference to Condition E because the alignment of an operable RHR relief valve is sufficient to compensate for the loss of one PORV.
The objective of this review is to determine if the removal of Condition E from Condition G is conservative and has no effects on safety.
The NRC staff reviewed the technical analysis provided in the letter dated January 28, 2014. The conditions to be analyzed under TS 3.4.12, L TOP System, are Conditions E, F, and G. A description of each condition from the Technical Specifications is provided as follows.
Condition E states that if one PORV is inoperable in MODE 5 or 6 the Required Actions are, E.1 Suspend all operations which could lead to a water solid pressurizer with an immediate completion time AND E.2 Restore PORV to OPERABLE status with a completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Condition F states that if the Required Action and associated Completion Time of Condition E. are not met, F.1 Verify RCS cold leg temperature are greater than the required temperature for Unit 1 or Unit 2 with a completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND F.2 Verify RHR suction relief valve is OPERABLE and the suction isolation valves are open with a completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Condition G states that if two PORVs are inoperable OR Required Action and associated Completion Time of Condition C, D, E, or F are not met OR L TOP System is inoperable for any reason other than Condition A, B, C, D, E, or F, G.1 Depressurize RCS and establish RCS vent of~ 2.75 square inches with a completion time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The NRC staff reviewed the conditions, required actions, and completion times associated with LCO 3.4.12. A failure to meet ConditionE is an inappropriate entry condition for Condition G, because Condition F should be entered first. With Condition E not met under the current TS, the Required Actions to be performed become F.1, F.2, and G.1. Requiring both actions F.2 and G.1 is overly restrictive in that F.2 restores redundancy with one PORV and one RHR suction relief valve, and further action by Required Action G.1 is not necessary. Even with the elimination of the reference to ConditionE in Condition G, the TSs will continue to maintain adequate protection of the RCS pressure boundary. Therefore, the NRC staff concludes it acceptable to remove the reference to Condition E.
Additionally, the NRC staff identified other differences in McGuire TS 3.4.12 compared to NUREG-1431, Revision 1, "Standard Technical Specifications-Westinghouse Plants," (ADAMS Accession No. ML13196A405). The differences identified by the NRC staff were: (1) McGuire TS 3.4.12 Condition G not containing Condition A for its required actions and associated completion time, (2) McGuire TS 3.4.12 having an additional condition in Condition F as compared to the Westinghouse STS, (3) why the RHR valve was not credited or listed under LCO 3.4.12, and (4) the RHR suction relief.valve capability and vent size forTS 3.4.12 Condition F not stated. The NRC staff issued a draft request for additional information (ADAMS Accession No. ML14329A317) to Duke regarding these differences and their applicability to the removal of the reference to Condition E. In subsequent discussions, the licensee identified existing, docketed references, to the NRC staff to address these issues. These references include the following: McGuire Nuclear Station, Unit 1 and 2 Technical Specification 3.4.9.3 License Amendment Request, "Unit 1 and 2 Heat Up and Cool Down Curves Low Temperature Overpressure Protection (L TOP)," dated March 29, 1995 (ADAMS Legacy Library Accession No. 9504050135), McGuire Nuclear Station, "Unit 1 and 2 Revised Record pages for Low Temperature Overpressure Protection (L TOP)
Technical Specification Amendment," dated September 18, 1995 (ADAMS Legacy Library Accession No. 9509260018), and McGuire Nuclear Station, "Unit 1 and 2 Response to Request for Additional Information," dated November 16, 1995 (ADArv1S Legacy Library Accession No. 9511270306). The NRC staff reviewed these precedential amendments and confirmed that the deviations from NUREG-1431, Revision 1 were previously reviewed and addressed. Further, the information confirmed that removal of Condition E was appropriate. Therefore, the NRC staff determined that no additional information was needed with respect to the subject LAR.
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. 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 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 such finding, which was published in the Federal Register on April 1, 2014 (79 FR 18330). 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 Contributors: M. Hardgrove K. Wood Date: December 11, 2014
ML14332A790 OFFICE LPL2-1/PM NAME GEMiller DATE 12/05/14 OFFICE Dl RS/ITSB/BC NAME REIIiott DATE 12/05/14 Sincerely,
/RAJ G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsNrrPMMcGuire Resource RidsNrrLASFigueroa Resource RidsRgn2MaiiCenter Resource
- By memo dated November 20, 2014 LPL2-1/LA DSS/SRXB/BC*
SFigueroa CJackson 12/02/14 11/20/14 OGCJNLO wlcomments LPL2-1/BC BHarris RPascarelli 12/08/14 12/11/14,