ML16067A229
| ML16067A229 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 04/08/2016 |
| From: | Geoffrey Miller Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Miller G, NRR/DORL/LPL2-1, 415-2481 | |
| References | |
| CAC MF6391, CAC MF6392, CAC MF6393, CAC MF6394 | |
| Download: ML16067A229 (27) | |
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 April 8, 2016
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 AND CATAWBA NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING REMOVAL OF OBSOLETE TECHNICAL SPECIFICATION REQUIREMENTS (CAC NOS. MF6391, MF6392, MF6393 AND MF6394)
Dear Mr. Capps:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 283 to Renewed Facility Operating License NPF-9 and Amendment No. 262 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station (MNS), Units 1 and 2 and Amendment No. 278 to Renewed Facility Operating License NPF-35 and Amendment No. 274 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station (CNS), Units 1 and 2, respectively.
The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 23, 2015.
The amendments remove superseded TS requirements. By letter dated July 1, 2009, as supplemented by letter dated May 20, 2010, Duke Energy submitted a license amendment request (LAR) to change TSs 3.3.1 in support of plant modifications planned for MNS and CNS.
The amendment allowed the licensee to install new instrumentation that utilized fission chamber detectors that perform both the Source Range and the Intermediate Range monitoring functions.
The modifications installed new nuclear instrumentation systems on a staggered basis, thus the TSs were written to allow a phased installation. The licensee, as part of these amendments, made a commitment to submit a follow-up administrative LAR to delete the now obsolete portion of TSs that allowed use of the old style instrumentation until the new style was installed.
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.
If you have any questions, please call me at 301-415-1119.
Sincer7 j
6b'),j J1,,~
G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370, 50-413 and 50-414
Enclosures:
- 1. Amendment No. 283 to NPF-9
- 2. Amendment No. 262 to NPF-17
- 3. Amendment No. 278 to NPF-35
- 4. Amendment No. 274 to NPF-52
- 5. Safety Evaluation cc w/encls: 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. 283 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 the Duke Energy Carolinas, LLC (licensee), dated June 23, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 1 O CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 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. 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 30 days of issuance.
Attachment:
Changes to License No. NPF-9 and the 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: April 8, 2o1 6
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. 262 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 June 23, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 1 O CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 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 1 O 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. 262, 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 the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION
~~4 Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: Apr i 1 a, 2o1 6
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 278 Renewed License No. NPF-35
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. NPF-35 filed by the Duke Energy Carolinas, LLC, acting for itself, and North Carolina Electric Membership Corporation (licensees), June 23, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 1 O CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 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 1 O 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-35 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 278, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC, 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-35 and the 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: April 8, 2o1 6
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 27 4 Renewed License No. NPF-52
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Carolinas, LLC, acting for itself, North Carolina Municipal Power Agency No. 1 and Piedmont Municipal Power Agency (licensees), dated June 23, 2015, 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.
- 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-52 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 274, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC, 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-52 and the Technical Specifications Date of Issuance: April a, 2o1 6 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 TO LICENSE AMENDMENT NO. 283 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 262 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 License Pages NPF-9, page 3 NPF-17, page 3 TS Pages 3.3.1-12 3.3.1-14 3.3.1-15 3.3.1-17 License Pages NPF-9, page 3 NPF-17, page 3 TS Pages 3.3.1-12 3.3.1-14 3.3.1-15 3.3.1-17
- 4)
Pursuant to the Act and 1 O CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6)
Pursuant to the Act and 1 O CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth iri 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. 283, 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. 283 (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 1 O 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 1 O CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or 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. 262 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. 262
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3. 3. 1. 9
N 0 TES----------------------------------
Ve rifi cation of setpoint is not required.
Perform TADOT.
SR 3.3.1.10 ------------------------------NOTES----------------------------------
This Surveillance shall include verification that the time constants are adjusted to the prescribed values.
Perform CHANNEL CALIBRATION.
SR 3.3.1.11
NOTES----------------------------------
- 1.
Neutron detectors are excluded from CHANNEL CALIBRATION.
- 2.
Power Range Neutron Flux high voltage detector saturation curve verification is not required to be performed prior to entry into MODE 1 or 2.
Perform CHANNEL CALIBRATION.
SR 3.3.1.12 Perform CHANNEL CALIBRATION.
McGuire Units 1 and 2 3.3.1-12 RTS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Proqram In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Proqram (continued)
Amendment Nos. 283/262
SURVEILLANCE REQUIREMENTS (continued)
Table 3.3.1-1(page1 of?)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS
- 1.
Manual Reactor Trip 1,2 2
B SR 3.3.1.14 3(a), 4(a), 5(a) 2 c
SR3.3.1.14
- 2.
Power Range Neutron Flux
- a.
High 1,2 4
D SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16
- b.
Low 1 (b),2 4
E SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16
- 3.
Power Range Neutron Flux Rate High Positive Rate 1,2 4
D SR 3.3.1.7 SR 3.3.1.11
- 4.
Intermediate Range 1(b), 2(c) 2 F,G SR 3.3.1.1 Neutron Flux SR 3.3.1.8U)(k)
SR 3.3.1.11 U)(k) 2(d) 2 H
SR 3.3.1.1 SR 3.3.1.8U)(k)
SR 3.3.1.11 U)(k)
(a)
With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.
(b)
Below the P-10 (Power Range Neutron Flux) interlocks.
(c)
Above the P-6 (Intermediate Range Neutron Flux) interlocks.
(d)
Below the P-6 (Intermediate Range Neutron Flux) interlocks.
RTS Instrumentation 3.3.1 NOMINAL ALLOWABLE TRIP VALUE SETPOINT NA NA NA NA
~ 2 sec
~ 2 sec
U)
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.
(k)
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.
McGuire Units 1 and 2 3.3.1-14 Amendment Nos. 283/262
- 5.
- 6.
- 7.
- 8.
(a)
(d)
(e)
(f)
U)
(k)
APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS Source Range 2(d)
Neutron Flux 3(a), 4(a), 5(a) 3(e), 4(e), 5(e)
Overtemperature L\\.T 1,2 Overpower L\\. T 1,2 Pressurizer Pressure
- a.
Low 1 (f)
- b.
High 1,2 Table 3.3.1-1 (page 2 of 7)
Reactor Trip System Instrumentation REQUIRED SURVEILLANCE CHANNELS CONDITIONS REQUIREMENTS 2
l,J SR 3.3.1.1 SR 3.3.1.8U)(k)
SR 3.3.1.11 G){k) 2 J,K SR 3.3.1.1 SR 3.3.1. 7U)(k)
SR 3.3.1.11 Q)(k)
L SR 3.3.1.1 SR3.3.1.11 4
E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12 SR3.3.1.16 SR 3.3.1.17 4
E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12 SR3.3.1.16 SR 3.3.1.17 4
M SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR3.3.1.16 4
E SR3.3.1.1 SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.
Below the P-6 (Intermediate Range Neutron Flux) interlocks.
RTS Instrumentation 3.3.1 NOMINAL ALLOWABLE TRIP VALUE SETPOINT
~ 1.44 E5 cps 1.0 E5 cps
~ 1.44 E5 cps 1.0 E5 cps N/A N/A Refer to Note 1 Refer to (Page Note 1 (Page 3.3.1-18) 3.3.1-18)
Refer to Note 2 Refer to (Page Note 2 (Page 3.3.1-19) 3.3.1-19)
- _ 1935 psig 1945 psig
~ 2395 psig 2385 psig (continued)
With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.
Above the P-7 (Low Power Reactor Trips Block) interlock.
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.
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.
McGuire Units 1 and 2 3.3.1-15 Amendment Nos. 283/262
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 16. Reactor Trip System Interlocks
- a.
Intermediate 2(d) 2 s
SR 3.3.1.11
.'.'., 6.6E-6% RTP 1E-5% RTP I Range Neutron SR 3.3.1.13 Flux, P-6
- b.
Low Power 1 per train T
SR 3.3.1.5 NA NA Reactor Trips Block, P-7 C.
Power Range 4
T SR 3.3.1.11
- d.
Power Range 1,2 4
s SR 3.3.1.11
.'.'., 7% RTP and 10% RTP Neutron Flux, SR3.3.1.13
- 5. 11% RTP P-10
- e.
Turbine Inlet 2
T SR 3.3.1.12
- 5. 11 % turbine 10% turbine Pressure, P-13 SR 3.3.1.13 inlet pressure inlet pressure equivalent equivalent
- 17. Reactor Trip 1,2 2 trains R,V SR 3.3.1.4 NA NA Breakers(i) 3(a), 4(a), 5(a) 2 trains c
SR 3.3.1.4 NA NA
- 18. Reactor Trip Breaker 1,2 1 each per u
SR 3.3.1.4 NA NA Undervoltage and RTB Shunt Trip 3(a), 4(a), 5(a)
Mechanisms 1 each per c
SR 3.3.1.4 NA NA RTB
- 19. Automatic Trip Logic 1,2 2 trains Q,V SR 3.3.1.5 NA NA 3(a), 4(a), 5(a) 2 trains c
SR 3.3.1.5 NA NA (a)
With RTBs closed and Rod Control System capable of rod withdrawal.
(d)
Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(i)
Including any reactor trip bypass breakers that are racked in and closed for bypassing on RTP.
Table 3.3.1-1 (page 5 of 7)
McGuire Units 1 and 2 3.3.1-17 Amendment Nos. 283/262
ATTACHMENT TO LICENSE AMENDMENT NO. 278 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AND DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 274 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 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 License Pages NPF-35, page 4 NPF-52, page 4 TS Pages 3.3.1-12 3.3.1-16 3.3.1-19 License Pages NPF-35, page 4 NPF-52, page 4 TS Pages 3.3.1-12 3.3.1-16 3.3.1-19 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 278, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC 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 December 6, 2024, 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.
(4)
Antitrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Program (Section 9.5.1, SER, SSER #2, SSER #3, SSER #4, SSER #5)*
Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, as amended, for the facility and as approved in the SER through Supplement 5, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or its supplement wherein this renewed license condition is discussed.
Renewed License No. NPF-35 Amendment No. 278 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 27 4, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC 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 February 24, 2026, 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 1 O CFR 50.59 and otherwise complies with the requirements in that section.
(4)
Antitrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Program (Section 9.5.1, SER, SSER #2, SSER #3, SSER #4, SSER #5)*
Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, as amended, for the facility and as approved in the SER through Supplement 5, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or its supplements wherein this renewed license condition is discussed.
Renewed License No. NPF-52 Amendment No. 27 4
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3. 3. 1. 9
N 0 TE--------------------------------
Ve rifi cation of setpoint is not required.
Perform T ADOT.
SR 3. 3. 1. 1 0 ----------------------------------N 0 TE--------------------------------
Th is Surveillance shall include verification that the time constants are adjusted to the prescribed values.
Perform CHANNEL CALIBRATION.
SR 3.3.1.11
NOTE--------------------------------
- 1.
Neutron detectors are excluded from CHANNEL CALIBRATION.
- 2.
Power Range Neutron Flux high voltage detector saturation curve verification is not required to be performed prior to entry into MODE 1 or 2.
Perform CHANNEL CALIBRATION.
RTS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Catawba Units 1 and 2 3.3.1-12 Amendment Nos. 278/27 4
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 8)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 4.
Intermediate Range 1 (b), 2(C) 2 F,G SR 3.3.1.1
.S. 38% RTP 25% RTP Neutron Flux SR 3.3.1.8(l)(m)
SR 3.3.1.11 (l)(m) 2(d) 2 H
.S. 38% RTP 25% RTP SR 3.3.1.8i1Hml SR 3.3.1.11 (l)(ml
- 5.
Source Range 2(d) 2 l,J SR 3.3.1.1
.s. 1.44 E5 cps 1.0 E5 cps Neutron Flux SR 3.3.1.8(1l(ml SR 3.3.1.11 (IJ(ml 3(a), 4(a), 5(a) 2 J,K SR 3.3.1.1
.s. 1.44 E5 cps 1.0E5cps SR 3.3.1.7(1Hml SR 3.3.1.11 (lllml
- 6.
Overtemperature /I. T 1,2 4
E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 1 (Page Note 1 SR 3.3.1.6 3.3.1-19)
(Page SR 3.3.1.7 3.3.1-19)
SR 3.3.1.10 SR 3.3.1.16 SR 3.3.1.17 (continued)
(a)
With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.
(b)
Below the P-1 O (Power Range Neutron Flux) interlocks.
(c)
Above the P-6 (Intermediate Range Neutron Flux) interlocks.
(d)
Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(I)
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.
(m) 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.
Catawba Units 1 and 2 3.3.1-16 Amendment Nos. 278/27 4
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 8)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 16. Reactor Trip System Interlocks
- a.
Intermediate 2(d) 2 R
SR 3.3.1.11
~ 6.6E-6%
1E-5% RTP Range Neutron SR 3.3.1.13 RTP Flux, P-6
- b.
Low Power 1 per train s
SR 3.3.1.5 NA NA Reactor Trips Block, P-7 C.
Power Range 4
s SR 3.3.1.11 s 50.2% RTP 48% RTP Neutron Flux, SR 3.3.1.13 P-8
- d.
Power Range 4
s SR3.3.1.11 s 70% RTP 69% RTP Neutron Flux, SR3.3.1.13 P-9
- e.
Power Range 1,2 4
R SR3.3.1.11
P-10 RTP
- f.
Turbine 2
s SR 3.3.1.12 s 12.2% RTP 10% RTP Impulse SR 3.3.1.13 turbine turbine Pressure, P-13 impulse impulse pressure pressure equivalent equivalent
- 17. Reactor Trip 1,2 2 trains Q,U SR 3.3.1.4 NA NA Breakers(k) 3(a), 4(a), 5(a) 2 trains c
SR 3.3.1.4 NA NA
- 18. Reactor Trip Breaker 1,2 1 each per T
SR 3.3.1.4 NA NA Undervoltage and RTB Shunt Trip 3(a), 4(a), 5(a)
Mechanisms 1 each per c
SR 3.3.1.4 NA NA RTB
- 19. Automatic Trip Logic 1,2 2 trains P,U SR 3.3.1.5 NA NA 3(a), 4(a), 5(a) 2 trains c
SR 3.3.1.5 NA NA (continued)
(a)
With RTBs closed and Rod Control System capable of rod withdrawal.
(d)
Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(k)
Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.
Catawba Units 1 and 2 3.3.1-19 Amendment Nos. 278/27 4
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 283 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AMENDMENT NO. 262 TO RENEWED FACILITY OPERATING LICENSE NPF-17 AMENDMENT NO. 278 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AMENDMENT NO. 274 TO RENEWED FACILITY OPERATING LICENSE NPF-52 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By application dated June 23, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15190A381 ), Duke Energy Carolinas, LLC (Duke, the licensee),
requested changes to the Technical Specifications (TSs) for the McGuire Nuclear Station, Units 1 and 2 (MNS) and Catawba Nuclear Station (CNS), Units 1 and 2. The proposed no significant hazards consideration determination was published in the Federal Register on August 4, 2015, 80 FR 46347.
The proposed changes would remove obsolete TS requirements. By letter dated July 1, 2009, (ADAMS Accession No. ML091950355), as supplemented by letter dated May 20, 2010, (ADAMS Accession No. ML101530462), Duke Energy submitted a license amendment request (LAR) to change TSs 3.3.1 in support of plant modifications planned for MNS and CNS. The amendment allowed the licensee to install new instrumentation that utilized fission chamber detectors that performs both the Source Range and the Intermediate Range monitoring functions. The modifications installed new nuclear instrumentation systems on a staggered basis, thus the TSs were written to allow a phased installation. The licensee, as part of these amendments, made a commitment to submit a follow-up administrative LAR to delete the now obsolete portion of TSs that allowed use of the old style instrumentation until the new style was installed.
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission's (NRC's or the Commission's) regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical Specifications." This regulation requires that the TSs include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings: (2) limiting conditions for operation; (3) surveillance requirements: (4) design features; and (5) administrative controls. It also requires that each TS limiting condition for operation (LCO) specify, at a minimum, the lowest functional capability or performance level of equipment required for the safe operation of the facility.
10 CFR 50.36(c)(1 )(ii)(A) states that "[w]here a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded."
Additionally, 10 CFR 50.36(c)(3), states, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."
3.0 TECHNICAL EVALUATION
The proposed changes are consistent with the commitment in Duke Energy's July 1, 2009, LAR, as supplemented by a letter dated May 20, 2010. That LAR was approved by the NRC in their SER dated August 2, 2010. The proposed changes fulfill the commitment to the NRC to delete the superseded temporary TSs.
The licensee has proposed to delete selected Source (SR) and Intermediate Range (IR)
Neutron Flux allowable values, setpoints, and associated footnotes. The values and footnotes proposed for deletion were only applicable to the Westinghouse supplied compensated ion chamber neutron detectors (Intermediate range) and the boron trifloride detectors (Source Range). Additionally, the licensee has proposed to delete SR 3.3.1.11.3 and its associated footnote, which is also only applicable to the Westinghouse supplied detectors.
As indicated in the licensee's submittal, these alternate values and surveillances were included in the TSs to facilitate a phased migration to Thermo Scientific supplied fission chamber neutron detectors. As indicated in their submittal, the licensee has completed the associated plant modifications at both MNS and CNS. As such, there are no longer any of the Westinghouse supplied instruments in use. Therefore, there is no need for the TSs to maintain the associated AVs, setpoints, footnotes, or SRs. As such, the NRC staff concludes that the deletion is appropriate and acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the North Carolina and South Carolina State officials were notified of the proposed issuance of the amendments. The State officials 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 and changes surveillance requirements. 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 80 FR 46347. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 1 O CFR 51.22(c)(9). Pursuant to 1 O 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: K. Cotton Gross D~e:April 8, 2016
ML16067A229 OFFICE N RR/DORL/LPL2-1 /PM NAME EMiller DATE 03/24/16 OFFICE DSS/SRXB/BC NAME RElliott (SAnderson for)
DATE 03/29/16 NRR/DORL/LPL2-1 /LA SFigueroa 03/09/16 OGC INLO wledits BMizuno 03/24/16