ML15174A173

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Issuance of Amendments Regarding Technical Specification Definition of Rated Thermal Power
ML15174A173
Person / Time
Site: McGuire, Mcguire  
Issue date: 08/24/2015
From: Geoffrey Miller
Plant Licensing Branch II
To: Capps S
Duke Energy Carolinas
Miller G
References
TAC MF6071, TAC MF6072
Download: ML15174A173 (14)
v • d • e


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 August 24, 2015

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1AND2 - ISSUANCE OF AMENDMENTS REGARDING TECHNICAL SPECIFICATION DEFINITION OF RATED THERMAL POWER (TAC NOS. MF6071 AND MF6072)

Dear Mr. Capps:

By letter dated March 23, 20151, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request to modify the Technical Specification definition of RATED THERMAL POWER and delete a footnote that allowed staggered implementation of the previously approved Measurement Uncertainty Recapture Power Updated.

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 280 to Renewed Facility Operating License NPF-9 and Amendment No. 260 to Renewed Facility Operating Licenses NPF-17 for the McGuire Nuclear Station, 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. ML 15097 A01 O.

S.Capps If you have any questions, please call me at 301-415-2481.

Docket Nos. 50-369 and 50-370

Enclosures:

1. Amendment No. 280 to NPF-9
2. Amendment No. 260 to NPF-17
3. Safety Evaluation cc w/encls: Distribution via Listserv Sin~e~

. 1/J

(_3r>,J /( '"/(

G. Edward 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. 280 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 March 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 actiyities 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 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-9 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 280, 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: August 24, 2015

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. 260 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 March 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. 260, 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 Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: _:"August 24, 2015

ATTACHMENT TO LICENSE AMENDMENT NO. 280 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 260 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 1.1-5 Licenses NPF-9, page 3 NPF-17, page 3 TSs 1.1-5

.3.

(4). Pursuant to the Act and 10 CFR Parts.30, 40 and 70, to receive, possess

. ana use In am*ounts 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 compor;ients;

  • (5)*

Pursuant to the Act and 10 CFR Parts 30, 40 and 7o, 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)

Purs.uant 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 Technol9gy Center.

C.

Tt:ils renewed operating license shall be deel'"!1ed to contain and is subject to the conditions specllied In !he Commission's regulations set forth in 10 CFR Chapter I and Is s4bject to all applicable provisions of the Act and lb the rules, regulations, and orders*of the Commission now or hereafter in ellect; anq Is subject to the. additional conditions specllied or incorporated below:

(1)

Maximum Power Level

  • The licensee is authorized to operate the facility at a reactor core lull steady state power level of 3469 megawatts the*rmal (100%). *

(2)

Technical Specifications The Technical Snecitications contained in Appendix A, as revised through

~mendmenl No 280are 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 lo 1 O CFR 54.21 (d), as. revised on Decemb.er 16, 2002, describes certain luiure activities to be completed before the period of extended operation.

Duke shall complete t.hese activities no later than June' 12, 2021, and shall notify the NRC In YJrltlng When implementation of these activities is complete and can be verified by NRC inspection.

The t..ij,dated Final Safety Arialysis Aeport"supplement a; revised on December 16, 2002, clescrlb~d above, shall" be included in the next

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. *

  • Renewed License No: NPF-9
  • Amendment No:
  • 280 I *

(4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 7b, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction tO chemical or physical form *. tor sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)

Pursuant to the Act anq 10 C.FR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear tnaierials as may be

. produced by"th~ operation of McGuire Nuclear'Station, Unils 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 ma1erial as may be produced by the Duke Training and Technology Center;

/

C.

This renewed operating license shall be deemed to con.~ain and is subject to Iha conditions specified* In the Commission's regulations set forth ln 10 CFR Chapter I and Is subject to all applicable provisions ol the Act and to the rules, regu!allons, and orders of the Commission now or hereafter in effect; and is subject to th~ additional conditions specified or inc9rporated below:

(1)

Ma>dmum Power Level The licensee Is authorized to operate' the facility at a reactor core full steady state power ievel of 3469*megawatts th.ermal (100%).

(2) : Technical Specilications The Technical Sperificalions con'tainecl in Appendix A, as revised through Amendment No 2503re hereby incorporated Into this renewed operating llcens.e. The licensl:!e shall operate the facility in accordance with the Technical Specifications.

(3)

Updated Final Safety Analysis Report

. The Updated !=inal Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on o*ecember 16, 2002, describes certain.

future.activities to be completed belore the period of extended operation.

puke 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 Safely Analysis Report*supplement as. revised on December 16, 2002, described above, shall be include~ In lhe next scheduled update-to the Updated Final Safety A"nalysis Report required by 10 Ci=R 50.71(e)(4),'to11D'Ning issuance of this renewed operating license.

Untll that upc;late 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 ~et forth In 10 CFR 50.59, and otherwise complies with the requirements in that section.

Renewed Llcens~ No. NPF-17 Amendment N~* 260

  • 1.1 Definitions (continued)

QUADRANT POWER TILT RATIO (QPTR)

RATED THERMAL POWER (RTP)

REACTOR TRIP SYSTEM(RTS)RESPONSE TIME SHUTDOWN MARGIN (SOM)

SLAVE RELAY TEST McGuire Units 1 and 2 Definitions 1.1 QPTR shall be the ratio of the maximum upper excore detector calibrated output to. the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3469 MWt.

The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC.

SOM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. However, with all RCCAs verified fully inserted by two independent means, it is not necessary to account for a stuck RCCA in the SOM calculation. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SOM; and
b.

ln MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level.

A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of each slave relay. The SLAVE RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.*

1.1-5 Amendment Nos. 280/260

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 280 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 260 TO RENEWED FACILITY OPERATING LICENSE NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION. UNITS 1AND2

- -- DOCKET NOS. 50-369 AND 50-370

1.0 INTRODUCTION

By letter dated March 23, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15097A010), Duke Energy Carolinas, LLC (Duke, the licensee),

submitted a license amendment request to modify the Technical Specification (TS) definition of

2.0 REGULATORY EVALUATION

1 O CFR 50.36(b) states, in part, that the license authorizing operation of a production or utilization facility will include TSs and they will be derived from the analyses and evaluations included in the safety analysis report (as updated). Although the Code of Federal Regulations does not have an explicit requirement that the TSs include a definition section, they typically include definitions of critical terms used throughout the TSs.

A change to a definition needs to be evaluated for its use throughout all instances within the TSs.

In the case of a material change to a definition, the effect of the change throughout the TSs must be verified to continue to meet the regulations and other applicable requirements. In the case of an administrative change to a definition, the NRC staff needs to verify that the change would not affect how the term is used or understood throughout the TSs.

3.0 TECHNICAL EVALUATION

By letter dated May 16, 2013 (ADAMS Accession No. ML13073A041 ), the NRC issued Amendments 269 and 249 to McGuire Nuclear Station, Units 1 and 2 (McGuire), respectively.

These amendments allowed the implementation of a Measurement Uncertainty Recapture (MUR)

Power Uprate from 3411 Megawatts-thermal (MWt) to 3469 MWt. Typically, full implementation of a Power Uprate requires plant modifications that need to be performed during an outage. For multi-unit sites, this generally requires a staggered implementation of the uprate as each individual unit is only able to perform the required modifications at their respective outage.

McGuire uses a common TS for both units. Thus, to accommodate staggered implementation of the MUR Power Uprate at both units which have different refueling schedules, Duke added a footnote that allowed an increase in power to 3469 MWt following implementation of the MUR on the respective unit. As part of the MUR Power Uprate LAR, Duke also committed to submit a LAR to remove the footnote once it was no longer needed. This LAR fulfills that commitment.

Duke has proposed to delete the footnote and replace the current definition of RTP, 3411 MWt, with 3469 MWt. As of September 24, 2014, both units at McGuire have fully implemented the MUR Power Uprate. As such, the power level of 3411 MWt is no longer applicable to either unit.

Because of the footnote, both units: currently understand RTP to mean 3469 MWt. Therefore, removing the footnote and replacing the definition of RTP with 3469 MWt would not change how the term is used or understood throughout the TSs. Because of this consideration, the NRC staff finds the proposed change to be administrative in nature and, therefore, acceptable.

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 make an editorial and otherwise minor revision to the license. 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 wa!? published in.the Federal Register on June 9, 2015 (80 FR 32627). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10)(v). 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: E. Miller Date: August 24, 2015

ML15174A173

  • Via e-mail OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DSS/STSB/BC OGC /NLO NAME GE Miller SFigueroa RElliott DRoth DATE 06/24/15 06/24/15 06/25/15 07/10/15 OFFICE DORL/LPL2-1 /BC DORL/LPL2-1/PM I

NAME RPascarelli GE Miller DATE 08/24/15 08/24/15

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