ML12226A169
| ML12226A169 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/01/2012 |
| From: | Jacqueline Thompson Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Thompson J | |
| References | |
| TAC ME7873, TAC ME7874 | |
| Download: ML12226A169 (15) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1,2012 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING CHANGES TO TECHNICAL SPECIFICATION 3.3.1, "REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION,"
(TAC NOS. ME7873 AND ME7874)
Dear Mr. Capps:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating license NPF-9 and Amendment No. 248 to Renewed Facility Operating license NPF-17 for the McGuire Nuclear Station, Units 1 and 2. The amendments consist of changes to the TSs in response to your application dated December 5, 2011. The amendments revise TS 3.3.1, Table 3.3.1-1, "Reactor Trip System Instrumentation,"
Function 16(e) to replace the phrase "Turbine Impulse Pressure" with 'Turbine Inlet Pressure."
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.
Sincerely, Jon Thompson, Project Manager Plant licensing Branch 11-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 268 to NPF-9
- 2. Amendment No. 248 to NPF-17
- 3. Safety Evaluation cc w/encls: Distribution via listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLG DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 268 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 December 5,2011, 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 authoriz.ed 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 tile 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
- 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. 268,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.
FOR THE NUCLEAR REGULATORY COMMISSION
~~
Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-9 and the Technical Specifications Date of Issuance: October 1, 2012
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. 248 Renewed License No. NPF-17
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nucl'3ar Station, Unit 2 (the facility),
Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated December 5,2012, 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 A.ct, 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 oftha Commission's regulations and all applicable requirements have been satisfied.
- 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. 248, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
/2ttP~
Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-17 and the Technical Specifications Date of Issuance: October 1, 2012
ATTACHMENT TO LICENSE AMENDMENT NO. 268 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 248 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 License Pages NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TS Pages TS Pages 3.3.1-17 3.3.1-17
-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70. to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form. for sample analysis or instrument calibration or aSSOCiated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess. but not separate, such byproducts and special nudear 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 materiaf 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 spectfJed In the Commission's regulations set forth in 10 CFR Chapter I and Is subject to all appilcabJe 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 reador core full steady state power 'evel of 3411 megawatts thermal (100%).
(2) Technical Specifications The Technical Specifications contained In Appendix A, as revised through Amendment No. 268 are hereby incorporated into this renewed operating license. The licensee shall operate the facility In accordance with the TechnIcal Specifications.
(3) Updateg Final Safety Ana!y!js 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 supplemant wtthout 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. 268
-3 (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as requIred any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate. such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2; and, (6)
Pursuant to the Act and 10 CFR Part 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 3411 megawatts thermal (100%).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 248 are hereby Incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Anillysil ReQQrt The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d). as revised on December 18.2002, 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 ;s 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 ofthls 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. 248
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)
Reactor Trip System Instrumentation APPLICABLE MOOESOR 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
~ 4E*11 amp""
1E-10 amp***
Range Neutron SR 3.3.1.13
~ 6.6E-6% RTP 1E-5% RTP 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
.5 49% RTP 48% RTP Neutron Flux, SR 3.3.1.13 P-8
- d.
Power Range 1,2 4
S SR 3.3.1.11
~7%,RTPand 10% RTP Neutron Flux.
SR 3.3.1.13
- 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. Reador 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 Mechanisms 3(8), 4(a), 5(a) 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
- The ~ 4E-11 amp Allowable Value and the 1E-10 amp NOMINAL TRIP SETPOINT value apply to the Westinghouse-supplied compensated ion chamber Intermediate Range neutron detectors. The compensated ion chamber neutron detectors are being replaced with Thermo ScientirlC-supplied fission chamber neutron detectors. The ~ 6.6E-6% RTP Allowable Value and the 1E-5% RTP NOMINAL TRIP SETPOINT value apply to the replacement fission chamber Intermediate Range neutron detectors.
(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.
McGuire Units 1 and 2 3.3.1-17 Amendment Nos. 268 and 248
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 248 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 application dated December 5, 2012 (Agencywide Documents Access and Management System Accession No. ML11341A110), Duke Energy Carolinas, LLC (Duke, the licensee),
requested changes to the Technical Specifications (TSs) for the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2). The proposed changes would revise TS 3.3.1, "Reactor Trip System (RTS) Instrumentation," Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 16(e) to rep/ace the phrase "Turbine Impulse Pressure" with "Turbine Inlet Pressure." The physical changes to McGuire 1 and 2 turbines and the associated relocation of the pressure taps are not within the scope of the proposed changes and will be performed under the licensee's engineering change process, following approval of this License Amendment Request (LAR).
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission (NRC or the Commission) staff reviews proposed changes to TSs for compliance with Title 10 of the Code ofFederal Regulations (10 CFR), Part 50, Section 50.36, "Technical specifications," and other regulatory requirements, including conformance with the general design criteria (GDG) found in 10 CFR 50, Part A, "General Design Criteria for Nuclear Power Plants," to determine whether or not the proposed changes maintain adequate safety. Licensees may revise their TSs provided that a plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (I.e., no requirements are materially altered); (2) the change is more restrictive than the licensee's current requirement; or (3) the change is less restrictive than the licensee's current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards.
- 2 Of the criteria found in 10 CFR 50, Appendix A. "General Design Criteria for Nuclear Power Plants," Criterion 13, "Instrumentation and control," (GDC 13) and Criterion 20, "Protection system functions," (GDC 20) are applicable to the review of this LAR. GDC 13 states that "Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges. GDC 20 states that The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.
3.0 TECHNICAL EVALUATION
The licensee in the LAR dated December 5, 2011, proposed the revision of TS 3.3.1, Table 3.3.1-1, Function 16(e), for permissive interlock P-13. The phrase Turbine Impulse Pressure" will be replaced with "Turbine Inlet Pressure." The phrase "turbine impulse pressure" applies when using a particular type of turbine blade design, whereas the phrase "turbine inlet pressure" is not linked to a particular turbine blade design. Approval of the LAR would, therefore, provide greater flexibility for the licensee to make turbine design changes without necessarily making changes to the TSs.
As the licensee plans to replace the existing high-pressure (HP) turbine nozzle-controlled, partial arc design with a new, throttle-controlled, full arc design after the approval of this LAR, the proposed changes to TS 3.3.1 will allow flexibility for implementing these planned turbine blade deSign changes, which eliminate the nozzle block and impulse stage. The actual physical changes to the McGuire 1 and 2 turbines and the associated relocation of the pressure taps described in this LAR are not within the scope of the changes proposed. These changes will be performed under the licensee's engineering change process.
The LAR proposes no physical or design change to Function 16.e, the P-13 function, and will have no effect on the operation of the RTS. Currently, when one of two turbine impulse pressure channels detect that the steam pressure is greater than approximately 10% of the rated full power pressure (permissive P-13), (or when two of four Power Range Neutron Flux channels detect that power is greater than 10% rated thermal power (permissive P-10>>, the P-7 RTS interlock actuates to remove the low power block (to enable reactor trips). The requirement for turbine pressure input to the P-13 RTS interlock is that the P-13 signal be representative of the rated thermal power. After approval of the LAR, the P-13 RTS interlock and signal would operate in the same manner.
The LAR proposes no changes to the other parts of Table 3.3.1-1 associated with the P-13 function, (i.e. the applicable modes or other specified conditions, required channels, conditions, surveillances requirements, allowable value, or nominal trip setpoint).
The NRC staff has reviewed the LAR. No physical or design changes to the P-13 function are proposed in this LAR and no changes are proposed to the other parts of Table 3.3.1-1 associated
- 3 with the P-13 function. The LAR would provide greater flexibility with respect to the turbine blade design used at McGuire 1 and 2, but no changes are proposed to how the P-13 RTS interlock and signal would operate. The NRC staff, therefore, finds these changes acceptable.
4.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
DETERMINATION The Commission may issue the license amendments before the expiration of the 60-day period provided that its final determination is that the amendments involve no significant hazards consideration. These amendments are being issued prior to the expiration of the 60-day period.
Therefore, a final finding of no significant hazards consideration follows.
The Commission has made a final determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendments does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91 (a), the licensee has provided its analysis of the issue of no significant hazards consideration which is presented below.
Criterion 1:
Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change to replace the phrase "Turbine Impulse Pressure, P-13" with "Turbine Inlet Pressure, P-13" in the descriptive text associated with Technical Specification 3.3.1, Reactor Trip System Instrumentation, Table 3.3.1-1, Function 16, Reactor Trip System Interlocks, item (e), does not involve any physical or design change to the P-13 function. The proposed change renames the turbine inlet pressure to reflect a change in turbine design and the new location where the pressure is sensed. The change is intended to eliminate any potential confusion regarding turbine type or the sensing location.
The proposed clarification of the P-1 3 function does not introduce an initiator or any design basis accident or event. The proposed change is consistent with the safety analysis assumptions and resultant consequences. In that the P-13 function is not affected, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Criterion 2:
Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
- 4 The relationship between turbine inlet pressure and the Rated Thermal Power (RTP) at the new location will be verified during testing. Although the pressure sensed at the new location is higher than the pressure sensed at the current location, the end use devices (i.e., various indication, recording, monitoring, control, and protection functions) of the RTS and associated functions will be recalibrated/re-scaled as necessary to maintain their basic functions. The response of the P-13 logic is unaffected, and the design function of the instrument loops has not changed.
Because the proposed change to replace the phrase "Turbine Impulse Pressure, P-13" with "Turbine Inlet Pressure, P-13" in Table 3.3.1-1, Function 16(e), does not involve a physical or design change to the P-13 function, no new accident causal mechanisms are created as a result of the requested changes which would result in the possibility of a new or different kind of accident from any accident previously evaluated.
Criterion 3:
Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
Implementation of this amendment will not result in a significant reduction in the margin of safety. Margin of safety is related to the confidence in the ability of the fission product barriers to perform their design functions during and following an accident situation.
These barriers include the fuel cladding, the reactor coolant system, and the containment system. The performance of these barriers will not be impacted by the proposed change.
The requirement for turbine pressure input in the P-13 RTS interlock is that the P-13 signal be representative of the RTP. This is accomplished by measuring the pressure at the HP turbine inlet because this pressure exhibits a consistent and accurate relationship with RTP.
The end use/device of the RTS and associated functions will be recalibrated/re-scaled as necessary to maintain their basic functions. The response of the P-1 3 logic is unaffected by this modification. The design function of the instrument loops has not changed.
Therefore, the proposed change does not involve a significant reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and based on this review, determined that the three standards of 10 CFR 50.92 are satisfied. Therefore, the NRC staff has determined that the amendments involve no significant hazards consideration.
5.0 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
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 such finding (77 FR 47677).
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 NRC staff 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:
J. Thompson, NRR Date: October 1, 2012
October 1, 2012 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING CHANGES TO TECHNICAL SPECIFICATION 3.3.1, "REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION,"
(TAC NOS. ME7873 AND ME7874)
Dear Mr. Capps:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating License NPF-9 and Amendment No. 248 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2. The amendments consist of changes to the TSs in response to your application dated December 5, 2011. The amendments revise TS 3.3.1, Table 3.3.1-1, "Reactor Trip System Instrumentation,"
Function 16(e) to replace the phrase "Turbine Impulse Pressure" with 'Turbine Inlet Pressure."
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.
Sincerely, IRA!
Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 268 to NPF-9
- 2. Amendment No. 248 to NPF-17
- 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
Public LPL2*1 RlF RidsAcrsAcnw MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDssSbpb Resource RidsNrrDraAhph Resource RidsNrrDeEicb Resource RidsNrrDirsloeb Resource RidsNrrDorlDpr Resource RidsNrrOor1LpI2-1 Resource RidsNrrPMMcGuire Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsRgn2MailCenter Resource ADAMS Accession No ML12226A169 IOFFICE NAME NRRlLPL2-1IPM JThompson NRRlLPL2-1/LA SFigueroa DSS/SBPB/BC GCasto DRAlAHPB/BC UShoop DE/EICB/BC JThorp II I
DATE 08/13/12 08/13/12 08/16/12 08/20/12 09/05/12 I
iOFFICE DlRS/ITSB/BC OGC NLO NRRlLPL2-1/BC NRRlLPL2-1/PM I
INAME RElliott wI comment BMizuno wI comment RPascarelli JThompson iDATE 09/7/12 09/12/12 10/1112 10/1/12 II OFFICIAL RECORD COpy