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{{#Wiki_filter:I -Sk-" D. CaMpDUKE We= fts&L~IJVice President ENERGY.DueEnmgWMGo1VP 1 12700 Has rAy RoadHw-h~sie, NC 28078o: 980.875.4805 f: 980.875.4809 September 16, 2013 SteLen.-v-Cappu-ercom U.S. Nuclear Regulatory Commission Document Control DeskWashington, D.C. 20555
{{#Wiki_filter:I -Sk-" D. CaMp DUKE We= fts&L~IJVice President ENERGY.DueEnmgW MGo1VP 1 12700 Has rAy Road Hw-h~sie, NC 28078 o: 980.875.4805 f: 980.875.4809 September 16, 2013 SteLen.-v-Cappu-ercom U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555  


==Subject:==
==Subject:==
 
Duke Energy Carolinas, LLC (Duke)McGuire Nuclear Station Docket Number 50-369 Response to Request for Additional Information Regarding the Core Operating Limits Report for Cycle 23 By letter dated April 10, 2013, Duke submitted the McGuire Nuclear Station, Unit 1, Cycle 23, Revision 0, Core Operating Limits Report (COLR), pursuant to the requirements of McGuire Technical Specification 5.6.5.d.By letter dated August 19, 2013, the NRC staff issued a Request for Additional Information (RAI) in order to support completion of their review.Attachments 1 and 2 provide the McGuire response to the RAI.Questions regarding this submittal should be directed to Kay L. Crane at (980) 875-4306.Steven D. Capps www.duke-energy.com U. S. Nuclear Regulatory Commission September 16, 2013 Page 2 xC : V. M. McCree Administrator, Region I1 U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center, Ave., NE Suite 1200 Atlanta, GA 30303-1257 John Zeiler Senior Resident Inspector U.S. Nuclear Regulatory Commission McGuire Nuclear Station Jason Paige (addressee only)NRC Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 GgA Rockville MD 20852-2738 McGuire Response to Request for Additional Information Attachment 1 MNS COLR RAI Question 1 1. The analytical methods used to determine core operating limits for parameters identified in TS come from methodologies approved by the NRC. The approved methodologies used by McGuire are listed in Section 1.1 of the COLR. Please list which of these approved methodologies is used to determine each operating limit in Section 2.0.MNS COLR RAI Question I Response Attachment 2 provides the Duke Energy Carolinas, McGuire Nuclear Station, Unit 1, Cycle 23 Core Operating Limits Report (COLR) Section 1 listing of NRC approved methods in Section 1.1 to analytical methods used to develop and/or determine COLR parameter limits identified in Technical Specifications in Section 2. The listing provided in Attachment 2 will be included in future McGuire Nuclear Station COLRs.
Duke Energy Carolinas, LLC (Duke)McGuire Nuclear StationDocket Number 50-369Response to Request for Additional Information Regarding theCore Operating Limits Report for Cycle 23By letter dated April 10, 2013, Duke submitted the McGuire Nuclear Station, Unit 1,Cycle 23, Revision 0, Core Operating Limits Report (COLR), pursuant to therequirements of McGuire Technical Specification 5.6.5.d.By letter dated August 19, 2013, the NRC staff issued a Request for Additional Information (RAI) in order to support completion of their review.Attachments 1 and 2 provide the McGuire response to the RAI.Questions regarding this submittal should be directed to Kay L. Crane at(980) 875-4306.
Attachment 2 1.0 Core Operating Limits Report -M1C23 COLR Section 1.0 for NRC RAI This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications that reference the COLR are summarized below along with the NRC approved analytical methods used to develop and/or determine COLR parameters identified in Technical Specifications.
Steven D. Cappswww.duke-energy.com U. S. Nuclear Regulatory Commission September 16, 2013Page 2xC :V. M. McCreeAdministrator, Region I1U.S. Nuclear Regulatory Commission Marquis One Tower245 Peachtree Center, Ave., NE Suite 1200Atlanta, GA 30303-1257 John ZeilerSenior Resident Inspector U.S. Nuclear Regulatory Commission McGuire Nuclear StationJason Paige (addressee only)NRC Project ManagerU.S. Nuclear Regulatory Commission 11555 Rockville PikeMail Stop 0-8 GgARockville MD 20852-2738 McGuire Response to Request for Additional Information Attachment 1MNS COLR RAI Question  
NRC Approved TS COLR Methodology (Section 1.1 Number Technical Specifications COLR Parameter Section Number)2.1.1 Reactor Core Safety Limits RCS Temperature and 2.1 6, 7, 8, 9, 10, 12, 15,...............................  
: 11. The analytical methods used to determine core operating limits for parameters identified inTS come from methodologies approved by the NRC. The approved methodologies used byMcGuire are listed in Section 1.1 of the COLR. Please list which of these approvedmethodologies is used to determine each operating limit in Section 2.0.MNS COLR RAI Question I ResponseAttachment 2 provides the Duke Energy Carolinas, McGuire Nuclear Station, Unit 1, Cycle 23Core Operating Limits Report (COLR) Section 1 listing of NRC approved methods in Section 1.1to analytical methods used to develop and/or determine COLR parameter limits identified inTechnical Specifications in Section 2. The listing provided in Attachment 2 will be included infuture McGuire Nuclear Station COLRs.
Attachment 21.0 Core Operating Limits Report -M1C23 COLR Section 1.0 for NRC RAIThis Core Operating Limits Report (COLR) has been prepared in accordance with the requirements ofTechnical Specification 5.6.5. The Technical Specifications that reference the COLR are summarized below along with the NRC approved analytical methods used to develop and/or determine COLRparameters identified in Technical Specifications.
NRC ApprovedTS COLR Methodology (Section 1.1Number Technical Specifications COLR Parameter Section Number)2.1.1 Reactor Core Safety Limits RCS Temperature and 2.1 6, 7, 8, 9, 10, 12, 15,...............................  
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311 Sudown Margin Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16.......................  
311 Sudown Margin Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16.......................  
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.... ... ... ... ... .... ... ... ... ... .... ... ... ... ... .... ... ... ... ... .... ... ..... ... ...3.1.5 Shutdown Bank Insertion Limits Shutdown Margin 2.2 _ 6, 7, 8,12, 14, 15, 16 3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion 2.4 2, 4, 6, 7, 8, 9, 10, Limit 12, 14, 15, 16...... .. s....... .6 .. ........ ..... ............  
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....... ... .... ... ...... ...3.1.6 Control Bank Insertion Limits Shutdown Margin 2.2 6,7 8 2-1,1,1 3.1.6 Control Bank Insertion Limits Control Bank Insertion 2.5 2,4, 6, 7, 8,9, 10,___ __ ________Limit 12, 14, 15, 16.i i ................  
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3.1.8 Physics Tests Exceptions Shutdown Margin 2.2 6, 7, 8, 12, 14,15, 163.2.1 Heat Flux Hot Channel Factor Fq, AFD, OTAT and 2.6 2, 4, 6, 7, 8, 9, 10,Penalty Factors 12, 15, 163.2.2 Nuclear Enthalpy Rise Hot Channel FAH, AFD and 2.7 2, 4, 6, 7, 8, 9, 10,.aPs..Factor
3.1.8 Physics Tests Exceptions Shutdown Margin 2.2 6, 7, 8, 12, 14,15, 16 3.2.1 Heat Flux Hot Channel Factor Fq, AFD, OTAT and 2.6 2, 4, 6, 7, 8, 9, 10, Penalty Factors 12, 15, 16 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH, AFD and 2.7 2, 4, 6, 7, 8, 9, 10,.aPs..Factor
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3.2.3 Axial Flux Difference AFD---- 2.8 2,4, 6, 7,8, 15, 16 3.3.1 Reactor Trip System Instrumentation OTAT and OPAT 2.9 6, 7, 8, 9, 10, 12, 15, Setpoints Constants 16 3.4.1 RCS Pressure, Temperature, and Flow RCS Pressure, 2.10 6, 7, 8, 9, 10, 12 DNB3 limits Temperature and Flow.. ......................  
3.2.3 Axial Flux Difference AFD---- 2.8 2,4, 6, 7,8, 15, 163.3.1 Reactor Trip System Instrumentation OTAT and OPAT 2.9 6, 7, 8, 9, 10, 12, 15,Setpoints Constants 163.4.1 RCS Pressure, Temperature, and Flow RCS Pressure, 2.10 6, 7, 8, 9, 10, 12DNB3 limits Temperature and Flow.. ......................  
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.........3.5.1 Accumulators Max and Min Boron 2.11 6, 7, 8, 12, 14, 16 Conc.3.5.4 Refueling Water Storage Tank Max and Min Boron 2.12 -6,,7,8, 12, 14, 16 Conc.3..4 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.13 6, 7, 8, 12, 14, 16........ ... ....... ......7 ..1..4 ...................
3.5.1 Accumulators Max and Min Boron 2.11 6, 7, 8, 12, 14, 16Conc.3.5.4 Refueling Water Storage Tank Max and Min Boron 2.12 -6,,7,8, 12, 14, 16Conc.3..4 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.13 6, 7, 8, 12, 14, 16........  
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3.9.1 Refueling Operations-Boron Min Boron Concentration 2.14 6, 7, 8, 12, 14,16 Concentration 565 CoreOperain Limits Report (COLR) Analytical Methods 1.1 None........ Cor .O.e............  
3.9.1 Refueling Operations-Boron Min Boron Concentration 2.14 6, 7, 8, 12, 14,16Concentration 565 CoreOperain Limits Report (COLR) Analytical Methods 1.1 None........
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._on .... .......The Selected Licensee Commitments that reference this report are listed below:NRC ApprovedSL.C COLR Methodology (Section 1.1Number Selected Licensing Commitment COLR Parameter Section Number)16.9.14 Borated Water Source -Shutdown Borated Water Volume and 2.15 6, 7,88, 12, 14, 16Conc. for BAT/RWST16.9.11 Borated Water Source -Operating Borated Water Volume and 2.16 6, 7, 8, 12, 14, 16Conc. for BAT/RWST16.9.7 Standby Shutdown System Standby Makeup Pump 2.17 6, 7,8, 12, 14, 16Water.Su.ply}}
._on .... .......The Selected Licensee Commitments that reference this report are listed below: NRC Approved SL.C COLR Methodology (Section 1.1 Number Selected Licensing Commitment COLR Parameter Section Number)16.9.14 Borated Water Source -Shutdown Borated Water Volume and 2.15 6, 7,88, 12, 14, 16 Conc. for BAT/RWST 16.9.11 Borated Water Source -Operating Borated Water Volume and 2.16 6, 7, 8, 12, 14, 16 Conc. for BAT/RWST 16.9.7 Standby Shutdown System Standby Makeup Pump 2.17 6, 7,8, 12, 14, 16 Water.Su.ply}}

Revision as of 22:53, 13 July 2018

McGuire Nuclear Station, Response to Request for Additional Information Regarding the Core Operating Limits Report for Cycle 23
ML13270A087
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 09/16/2013
From: Capps S D
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13270A087 (4)
v • d • e


Text

I -Sk-" D. CaMp DUKE We= fts&L~IJVice President ENERGY.DueEnmgW MGo1VP 1 12700 Has rAy Road Hw-h~sie, NC 28078 o: 980.875.4805 f: 980.875.4809 September 16, 2013 SteLen.-v-Cappu-ercom U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC (Duke)McGuire Nuclear Station Docket Number 50-369 Response to Request for Additional Information Regarding the Core Operating Limits Report for Cycle 23 By letter dated April 10, 2013, Duke submitted the McGuire Nuclear Station, Unit 1, Cycle 23, Revision 0, Core Operating Limits Report (COLR), pursuant to the requirements of McGuire Technical Specification 5.6.5.d.By letter dated August 19, 2013, the NRC staff issued a Request for Additional Information (RAI) in order to support completion of their review.Attachments 1 and 2 provide the McGuire response to the RAI.Questions regarding this submittal should be directed to Kay L. Crane at (980) 875-4306.Steven D. Capps www.duke-energy.com U. S. Nuclear Regulatory Commission September 16, 2013 Page 2 xC : V. M. McCree Administrator, Region I1 U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center, Ave., NE Suite 1200 Atlanta, GA 30303-1257 John Zeiler Senior Resident Inspector U.S. Nuclear Regulatory Commission McGuire Nuclear Station Jason Paige (addressee only)NRC Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 GgA Rockville MD 20852-2738 McGuire Response to Request for Additional Information Attachment 1 MNS COLR RAI Question 1 1. The analytical methods used to determine core operating limits for parameters identified in TS come from methodologies approved by the NRC. The approved methodologies used by McGuire are listed in Section 1.1 of the COLR. Please list which of these approved methodologies is used to determine each operating limit in Section 2.0.MNS COLR RAI Question I Response Attachment 2 provides the Duke Energy Carolinas, McGuire Nuclear Station, Unit 1, Cycle 23 Core Operating Limits Report (COLR) Section 1 listing of NRC approved methods in Section 1.1 to analytical methods used to develop and/or determine COLR parameter limits identified in Technical Specifications in Section 2. The listing provided in Attachment 2 will be included in future McGuire Nuclear Station COLRs.

Attachment 2 1.0 Core Operating Limits Report -M1C23 COLR Section 1.0 for NRC RAI This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications that reference the COLR are summarized below along with the NRC approved analytical methods used to develop and/or determine COLR parameters identified in Technical Specifications.

NRC Approved TS COLR Methodology (Section 1.1 Number Technical Specifications COLR Parameter Section Number)2.1.1 Reactor Core Safety Limits RCS Temperature and 2.1 6, 7, 8, 9, 10, 12, 15,...............................

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.... ... ... ... ... .... ... ... ... ... .... ... ... ... ... .... ... ... ... ... .... ... ..... ... ...3.1.5 Shutdown Bank Insertion Limits Shutdown Margin 2.2 _ 6, 7, 8,12, 14, 15, 16 3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion 2.4 2, 4, 6, 7, 8, 9, 10, Limit 12, 14, 15, 16...... .. s....... .6 .. ........ ..... ............

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....... ... .... ... ...... ...3.1.6 Control Bank Insertion Limits Shutdown Margin 2.2 6,7 8 2-1,1,1 3.1.6 Control Bank Insertion Limits Control Bank Insertion 2.5 2,4, 6, 7, 8,9, 10,___ __ ________Limit 12, 14, 15, 16.i i ................

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3.1.8 Physics Tests Exceptions Shutdown Margin 2.2 6, 7, 8, 12, 14,15, 16 3.2.1 Heat Flux Hot Channel Factor Fq, AFD, OTAT and 2.6 2, 4, 6, 7, 8, 9, 10, Penalty Factors 12, 15, 16 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH, AFD and 2.7 2, 4, 6, 7, 8, 9, 10,.aPs..Factor

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3.2.3 Axial Flux Difference AFD---- 2.8 2,4, 6, 7,8, 15, 16 3.3.1 Reactor Trip System Instrumentation OTAT and OPAT 2.9 6, 7, 8, 9, 10, 12, 15, Setpoints Constants 16 3.4.1 RCS Pressure, Temperature, and Flow RCS Pressure, 2.10 6, 7, 8, 9, 10, 12 DNB3 limits Temperature and Flow.. ......................

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.........3.5.1 Accumulators Max and Min Boron 2.11 6, 7, 8, 12, 14, 16 Conc.3.5.4 Refueling Water Storage Tank Max and Min Boron 2.12 -6,,7,8, 12, 14, 16 Conc.3..4 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.13 6, 7, 8, 12, 14, 16........ ... ....... ......7 ..1..4 ...................

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3.9.1 Refueling Operations-Boron Min Boron Concentration 2.14 6, 7, 8, 12, 14,16 Concentration 565 CoreOperain Limits Report (COLR) Analytical Methods 1.1 None........ Cor .O.e............

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._on .... .......The Selected Licensee Commitments that reference this report are listed below: NRC Approved SL.C COLR Methodology (Section 1.1 Number Selected Licensing Commitment COLR Parameter Section Number)16.9.14 Borated Water Source -Shutdown Borated Water Volume and 2.15 6, 7,88, 12, 14, 16 Conc. for BAT/RWST 16.9.11 Borated Water Source -Operating Borated Water Volume and 2.16 6, 7, 8, 12, 14, 16 Conc. for BAT/RWST 16.9.7 Standby Shutdown System Standby Makeup Pump 2.17 6, 7,8, 12, 14, 16 Water.Su.ply

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