ML17135A289

Millstone, Unit 2, Submittal of Core Operating Limits Report, Cycle 25

ML17135A289
Person / Time
Site:	Millstone
Issue date:	05/05/2017
From:	Stanley B L Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
17-165
Download: ML17135A289 (16)

Text

{{#Wiki_filter:Dominion Nnclear Connecticut, Inc. Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dam.com MAY 0 5 2017 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT, CYCLE 25 Serial No. NSS&L/MLC Docket No. License No. 17-165 RO 50-336 DPR-65 In accordance with the Millstone Power Station Unit 2 (MPS2) Technical Specifications (TSs), Section 6.9.1.8.d, Dominion Nuclear Connecticut, Inc.,* hereby submits, as an enclosure, the Cycle 25 Core Operating Limits Report (COLR). The MPS2 COLR has been revised to include the following:

• Revision of page headers to reflect Cycle 25.
• Revised the least negative temperature coefficient to reflect the revised.* analyses for post-scram main steam line break, pre-scram main steam line break, and single main steam isolation valve closure events.
• Made formatting changes to the Analytical Methods section to add the TS limits associated with each COLR methodology.
• Added BAW-10240(P)(A) and EMF-2103(P)(A) to Analytical Methods section to support use of AREVA Standard CE14 HTP fuel product with M5 cladding in Cycle 25, consistent with the NRG-approved changes to TS 6.9.1.8.b. The Cycle 25 COLR has been incorporated into the MPS2 Technical Requirements Manual. If you have any questions or require additional information, please contact Mr. Jeffry Langan at (860) 444-5544. Sincerely, B. L. Stanley Director, Nuclear Station Safety and Licensing -Millstone

Enclosure:

Core Operating Limits Report, Cycle 25 Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No. 17-165 Docket No. 50-336 MPS2 Cycle 25 COLR Page 2 of 2 ENCLOSURE CORE OPERATING LIMITS REPORT. CYCLE 25 DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 2 Serial No. 17-165 Docket No. 50-336 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 25 1. CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT for Millstone 2 has been prepared in accordance with the requirements of Technical Specification 6.9.1.8 a through 6.9.1.8 d. The Technical Specifications affected by this report are listed below: Section 2.1 3/4.1.1.1 SHUTDOWN MARGIN -(SOM) 2.2 Deleted (Ref. License Amendment 280) 2.3 3/4.1.1.4 Moderator Temperature Coefficient (MTC) 2.4 3/4.1.3.6 Regulating CEA Insertion Limits 2.5 3/4.2.1 Linear Heat Rate 2.6 3/4.2.3 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR --F? 2.7 3/4.2.6 DNB Margin Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications. 2. OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Section 3. 2.1 SHUTDOWN MARGIN'-(SOM) (Specification 3/4.1.1.1) The SHUTDOWN MARGIN shall 3.6% 2.2 Deleted 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4) The moderator temperature coefficient shall be: a. Less positive than 0.7x104 whenever THERMAL POWER is :::;70% of RATED THERMAL POWER, b. Less positive than 0.4x1 o-4 whenever THERMAL POWER is> 70% of RATED THERMAL POWER, c. Less negative than -3.0x1 o-4 at RATED THERMAL POWER. MILLSTONE -UNIT 2 TRM 8.1-1 LBDCR 17-MP2-002 March 16, 2017 I

• TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1
• CORE OPERATING LIMITS REPORT, CYCLE 25 2.4 Regulating CEA Insertion Limits (Technical Specificatio.n 3/4.1.3.6) The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 2.4-1. CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits is restricted to: a. :::;; 4 hours per 24 hour interval, b. :::;; 5 Effective Full Power Days per 30 Effective Full Power Day interval, and c. :::;; 14 Effective Full Power Days per 365 Effective Full Power Day interval. 2.5 Linear Heat Rate (Technical Specification 3/4.2.1) The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed: a. 15.1 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) 360,000 gpm. b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 360,000 gpm and 354,600 gpm.
• c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 354,600 gpm and 349,200 gpm. During operation with the linear heat rate being monitored by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall remain within the limits of Figure 2.5-1. During operation with the linear heat rate being monitored by the lncore Detector Monitor System, the alarm setpoints shall be adjusted to less than or equal to the limit when the following factors are appropriately included in the setting of the alarms: 1. A measurement-calculational uncertainty factor of 1.07, 2. An engineering uncertainty factor of 1.03, and . 3. A THERMAL POWER measurement uncertainty factor of 1.02. MILLSTONE -UNIT 2 TRM 8.1-2 LBDCR 17-MP2-002 March 16, 2017 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 25 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR --F? (Technical Specification 3/4.2.3) The calculated value of F? at RATED THERMAL POWER shall be: ::; 1.690 whenever the-reactor coolant flow rate is ;;:::: 360,000 gpm. ::; 1.664 whenever the reactor coolant flow rate is < 360,000 gpm 2 354,600 gpm. . ::; 1.639 whenever the reactor coolant flow rate is < 354;600 gpm and 2 349,200 gpm. 2.6.1 The Power Dependent FrT limits, whenever the reactor coolant flow rate is;;:::: 360,000 gpm, are shown in Figure 2.6-1. 2.6.2 The Power Dependent FrT limits, whenever the reactor coolant flow rate is < 360,000 gpm and ;;:::: 354,600 gpm, are shown in Figure 2.6-2. ,
• 2.6.3 The Power Dependent F? limits, whenever the reactor coolant flow rate . is < 354,600 gpm and 349,200 gpm, are shown in Figure 2.6-3. ) 2.7 DNB Margin (Technical Specification 3/4.2.6) The DNB margin shall be preserved by maintaining the cold leg temperature, pressurizer pressure," reactor coolant flow rate, and AXIAL SHAPE INDEX within the following limits: Parameter Limits Four Reactor Coolant Pumps Operations a. Cold Leg Temperature ::; 549°F b. Pressurizer Pressure c. Reactor Coolant Flow Rate d. AXIAL SHAPE INDEX > 2225 psia* ;;:::: 360,000 gpm with Linear Heat Rate and F? limits as specified in Sections 2.5 and 2 .. 6. or ;;:::: 354,600 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6. or ;;:::: 349,200 gpm with Linear Heat Rate and F? limit reductions as specified in Sections 2.5 and 2.6. Figure 2.7-1
• Limit not applicable during the THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER MILLSTONE -UNIT 2 TRM 8.1-3 LBDCR 17-MP2-002 March 16, 2017

.--... ___ __) TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 25 3. ANALYTICAL METHODS . . *The analytical methods used to determine the core or.erating limits shall be those -preyious*ly reviewed and approved by the NRG, specifically those described in the following documents: . . 3.1 EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 -Methodology Description, Volume 2 -Benchmarking Results," Siemens Power Corporation, January 1997.

• Methodology for: TS 3.1.1.1 -Shutdown Margin -(SOM) TS 3.1.1.4 -Moderator Temperature Coefficient (MTG) TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate . TS 3_.2.3 -Total Un rodded Integrated Radial Peaking Factor-FTr 3.2 ANF-84-73 Revision 5 Appendix B(P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Analysis of Chapter 15 Events," Advanced Nuclear Fuels, July 1990. }
• Methodology for: TS 3.1.1.1 -Shutdown Margin -(SOM) TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Peaking Factor-FTr 3.3 XN-NF-82-21 (P)(A) Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983. Methodology for: TS 3.2.1 -Linear Heat Rate TS 3.2.3-Total Unrodded Integrated Radial Peaking Factor-FTr 3.4 XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Bowing," Exxon Nuclea'. Company, October 1983. Methodology for: TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Un rodded Integrated Radial Peaking Factor -FTr MILLSTONE -UNIT 2 TRM 8.1-4 LBDCR 17-MP2-002 March 16, 2017 TECHNICAL REQUIREMENTS MANUAL I APPENDIX 8.1 ********--" CORE OPERATING LIMITS REPORT, CYCLE 25 3.5 Revision 0 and Supplement 1 (P)(A), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based," Framatome ANP, September 2015. Methodology for: TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Peaking Factor-.FTr 3.6 EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for .PWR LBLOCA Applications," Siemens Power Corporation, June 1999. Methodology for: TS 3.1.3 .. 6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Peaking Factor-FTr 3.7 XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," E:Xxon Nuclear Company, October 1983. ) Methodology for: i ___ ,. TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Un rodded Integrated Radial Peaking Factor -F\ 3.8 XN-NF-621 (P)(A) Revision 1, "Exxon Nuclear DNB *Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983. Methodology for: TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Integrated Radial Peaking Factor-FTr 3.9 XN-NF-82-06(P)(A) Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear* Company, October 1986. Methodology for: TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3-Total Unrodded Integrated Radial Peaking Factor-FTr MILLSTONE -UNIT 2 TRM 8.1-5 LBDCR 17-MPZ-002 March 16, 2017
• TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 25 3.1 O ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced NucleC\r Fuels PWR Design Methodology for Rod Burn ups of 62 GWd/MTU, Advanced Nuclear* Fuels Corporation, December 1991. Metho!=f ology for: TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Peaking Factor-FTr 3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986. Methodology for: TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Peaking Factor-3.12 ANF-89-151 (P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992. Methodology for: TS 3.1.1.4 -Moderator Temperature Coefficient (MTG) TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Un rodded Integrated Radial Peaking Factor-F Tr 3.13 EMF-1961 (P)(A) Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000. Methodology for: TS 3.1.3.6 -Regulating CEA Insertion Limits* . TS.3.2.1 -Linear Heat Rate
• TS 3.2.3 -*Total Un rodded Integrated Radial Peaking Factor -F Tr TS 3.2.6 -DNB Margin MILLSTONE -UNIT 2 TRM 8.1-6 LBDCR 17-MP2-0d2 March 16, 2017

... _} ... ./ TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 25 3'.14 EMF-231 O(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP, May 2004-. Methodology for:

• TS 3.1.1 .4 -Moderator Temperature Coefficient (MTG) TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Factor-FTr 3.15 EMF-92-153(P)(A), Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005. *Methodology for: TS 3.2.1 -Linear Heat Rate TS -Total Unrodded Integrated Radial Peaking Factor-FTr 3.16 EMF.,92-116(P)(A) Revision 0 and Supplement 1 (P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 2015. Methodology for: TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Peaking Factor-FTr 3.17 BAW-10240(P)(A), Revision 0, "Incorporation of M5Ž Properties in Framatome . ANP Approved Methods," Framatorrie ANP, Inc., May 2004. Methodology for: TS 3.2.1 -Linear Heat Rate TS 3.2.3 -Total Unrodded Integrated Radial Peaking Factor..:. FTr 3.18 EMF-2103(P)(A), Revision 3, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," AREVA Inc., June 201-6. Methodology for: TS 3.1.3.6 -Regulating CEA Insertion Limits TS 3.2.1 ,.... Linear Heat Rate TS 3.2.3 -Total Unrodoed Integrated Radial Peaking Factor-FTr ( MILLSTONE -UNIT 2 TRM 8.1-7 LBDCR 17-MP2-002 March 16, 2017

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) -.../ ffi 100 00 00 a. 70 'iii E ID F= oo "i 1i1 t1: 50 0 1: ID 0 ffi 40 a. (I) :0 !11 30 20 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 25 (1.639, 100) I, (1.654, 00) UJ\l4a:EPJ"ABLE OPERATION REGION ***A************* I I ' ' I 1, I I I I I I J I I I I I I I * * * * * *,* ** * * **** ** * ** "i. * * * * *1 * * ** * *r * * * ** *.** * ** * ** * * ** *** *

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• r '* I *, 10 ***** ***** *1* ...... ., ........ : ....... ....... : ............... 'I* ***** : ...... ............... ...... ......... . . ....... ....... 1.639 1.&ID 1.659 1.669 1.679 1.689 1.699 1.709 1.719 1.729 1.739 1.749 1.759 1.769 1.779 1.789 TOTAL UNRCX'.CED INTEGRATED RADAL PE/IK!t\k3FACfffi-F/ Figure 2.6-3 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates < 354,600 gpm and ;:::: 349,200 gpm MILLSTONE -UNIT 2 TRM 8.1-12 LBDCR 17-MP2-002 March 16, 2017

'l* 120 1.10 1.00 n: 0-90 UJ 0 O.BO n.. ....I <( 2 0.70 "" '1.1 ?= n 0:50 I:! <<!; .!>:: 050 0 z TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 25 I I I l J I l I --+-----l,*--r--+---+---il-----4-----1----t---+-J I I I I I I : l I : : : l l i I j1 l I ! ! I 1 I I --t,-------+----1---t----r----1-----'-1 -------:---------+---1---1--------t-------r----* I *

• I I I I UNACCEPTABLE f---{-0.10, 1.fi) : : {0.15, 1.0)---] UNAC-CEf>TA.BLE {---OPERATION ---+----r----l OPERATION -1------ll REGlOf'>J I I l./1 i I ! '\.. l 1 REGION ! I I l l I l I . t-' ' f I I I J I I I I I I -*-T-----+-*** ---i-------* ----1--------+-------+--*-1----r-------**------i----r**--+-------!---' ! ! I I I ! l I .1. . I I I I {-0.3, 0.00) ! , I I : : {0.30, 0.00} I ---t------t--------+-------1--r-----t----i---f-----1 I I I I I I I I I I I I I I I ' I I I I I I I -!..-----i-r---i----f------f---f i I I I I I I I I I I I I I ---+----____ J_ _____ _.: ____ _ I I i I I --t----I I ! -I I I I ____ ! ___ ----!----ACCEPTABLE OPERATION REGION *. ! I I I ! ---r--------+-------i------+---.... --1-----1 I I I I
• I I I I I I I I -----.+-----------1-------+-----I I I I ! 1 ; I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I I I I I I --r----1--r--<<!; n: u.. 0.30 0.20 0.10 !
• I I I I I I I I I I : ' ' !--t----..----' ' ' ' ' ' I I r I I I I l : l -I-----+--+--+-------+----1-------t-----r---1 t J I I l I l I ' ' ' -----!-----+---! ' ' . ' ' ' I i I I :---t--------r-------t------t-----' ' --+---------+---------t----! l I I ! J I I I I I I I I I f I I f I [ I I ---1---1--r----r----,-------i--1-----r-------1--------T----:---' ' ' ' ' . ' 0.00 -OJi , ! I J j j ! l I -0.5 -0.4 -0.3 -0..2 -0.1 0 0..1 0.2 -,----0.3 0.4 05 0..5 AXIALSHAPE INDEX !AS!) Figure 2. 7-1 AXIAL' SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE -UNIT 2 TRM 8.1-13 LBDCR 17-MP2-002 March 16, 2017

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