Text

Core Operating Limits Report, Cycle 29
	ML23116A088
Person / Time
Site:	Millstone
Issue date:	04/26/2023
From:	Armstrong L; Dominion Energy Nuclear Connecticut
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	23-129
	Download: ML23116A088 (1)
	v • d • e

Dom inion En ergy Nu clea r Conn ecti cut, In c.

M ill stone Power Station ~ Dominion 314 Rope Ferry Road, Wa terford, CT 06385 Do minion En ergy.com APR 2 6 2023 :;iiiii" Energy U.S. Nuclear Regulatory Commission Serial No.23-129 Attention: Document Control Desk NSS&L/TFO RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT, CYCLE 29 In accordance with th~ Millstone Power Station Unit 2 (MPS2) Technical Specifications (TSs), Section 6.9.1.Sd , Dominion Energy Nuclear Connecticut, Inc., hereby submits, as an enclosure, the Cycle 29 Core Operating Limits Report (COLR).

The MPS2 COLR has been revised as follows:

Revision of page headers to reflect Cycle 29 The Cycle 29 COLR has been incorporated into the MPS2 Technical Requirements Manual.

If you have any questions or require additional information, please contact Mr. Dean Rowe at (860) 444-5292.

Sincerely,

~ -a ~

L. J. Armstrong Director, Nuclear Station Safety and Licensing - Millstone Endosure: Core Operating Limits Report, Cycle 29 Commitments made in this letter: None

Serial No.23-129 Docket No. 50-336 MPS2 Cycle 29 COLR Page 2 of2 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Rd., Suite 102 King of Prussia, PA 19406-1415 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.23-129 Docket No. 50-336 ENCLOSURE CORE OPERATING LIMITS REPORT, CYCLE 29 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29

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 S~ecification 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 be~ 3.6% LiK/K 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.?x10-4 LiK/K/°F whenever THERMAL POWER is :S:70% of RATED THERMAL POWER,

b. Less positive than 0.4x 10-4 LiK/K/°F whenever THERMAL POWER is > 70%

of RATED THERMAL POWER,

c. Less negative than -3.0x1 o- 4 LiK/K/°F at RATED THERMAL POWER.

MILLSTONE - UNIT 2 TRM 8.1-1 LBDCR 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 2.4 Regulating CEA Insertion Limits (Technical Specification 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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) is ~ 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 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR -- FrT (Technical Specification 3/4.2.3)

The calculated value of FrT at RATED THERMAL POWER shall be:

s 1.690 whenever the reactor coolant flow rate is ~ 360,000 gpm.

s 1.664 whenever the reactor coolant flow rate is < 360,000 gpm and ~ 354,600 gpm.

s 1.639 whenever the reactor coolant flow rate is < 354,600 gpm and ~ 349,200 gpm.

2.6.1 The Power Dependent F/ 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 FrT 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 s 549°F

b. Pressurizer Pressure > 2225 psia*

c. Reactor Coolant Flow Rate ~ 360,000 gpm with Linear Heat Rate and FrT limits as specified in Sections 2.5 and 2.6.

or

~ 354,600 gpm with Linear Heat Rate and F/ limit reductions as specified in Sections 2.5 and 2.6.

or

~ 349,200 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.

d. AXIAL SHAPE INDEX Figure 2.7-1

Limit not applicable during either 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 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29

3. ANALYTICAL METHODS The analytical methods used to determine the core or,erating limits shall be those previously reviewed and approved by the NRC, 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 (MTC)

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 3.2 ANF-84-73 Revision 5 Appendix B(P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: 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 - F\

3.4 XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear 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 Unrodded Integrated Radial Peaking Factor- FTr MILLSTONE - UNIT 2 TRM 8.1-4 LBDCR 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 3.5 EMF-2328(P)(A), Revision O 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 - F\

3.7 XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear 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 Unrodded 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 Unrodded Integrated Radial Peaking Factor - F\

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 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 3.10 ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.

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 - F\

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- FTr 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 (MTC)

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 3.13 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 Unrodded Integrated Radial Peaking Factor - FTr TS 3.2.6 - DNB Margin MILLSTONE - UNIT 2 TRM 8.1-6 LBDCR 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 3.14 EMF-231 0(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 (MTC)

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 3.15 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 3.2.3 - Total Un rodded 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 M5' Properties in Framatome ANP Approved Methods," Framatome ANP, Inc., May 2004.

Methodology for:

TS 3.2.1 - Linear Heat Rate TS 3.2.3 - Total Unrodded Integrated Radial Peaking Factor - F\

3.18 EMF-2103(P)(A), Revision 3, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," AREVA Inc., June 2016.

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 8.1-7 LBDCR 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APP ENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29

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Figure 2.4-1 CEA Insertion Limit vs. THERMAL POWER With Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 TRM 8.1-8 LBDCR 23-MP2-001 March 2, 2023

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PERCENT OF ALLOWABLE POWER LEVEL MILLSTONE - UNIT 2 TRM 8.1-9 LBDCR 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 100 .

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Figure 2.6-1 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates 2 360,000 gpm MILLSTONE - UNIT 2 TRM 8.1-10 LBDCR 23-MP2-001 March 2, 2023

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I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 10 . .... - . - ;- .... - . .. *:* .... -.... -:* .... . . .. *:* . . .... *:- ........ *:- . . - . . -:- . - . -. *:- . -. - - ! ... -. - -; . . . . . .. ! ....... .... ~ .. - - . .. .. ; . ........ -:* . . . .. .

I I I I I I I I I I I I I I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0

1.664 1.674 1.684 1.694 1.704 1.714 1.724 1.734 1.744 1.754 1.764 1.774 1.784 1.794 1.804 1.814 TOTAL LNRCOCED INTEGRATED RADIAL PEAKING FACTOR- FrT Figure 2.6-2 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates < 360,000 gpm and ~ 354,600 gpm MILLSTONE - UNIT 2 TRM8.1-11 LBDCR 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 100 (1 .639, 100)

(1.654, 00) Ut-,t.,\CCEPTPBLE 00 OPERATION ...*......*......

REGION ' '

00 ***** -~ *** ***:* *** ** ~-- ****

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Ir * * * * * *,*I * * * * * *,*

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- - - - r "U

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0 50 CPERATION REGION c

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if 2CJ - - - - - -r ------: - .. ---, -.... -i - -*. -- r---*--:- --*** ~- ***** ;***** -, _***** r.. -.. -:- .... -~- -.... ;... -.. ;

10 .***.* ,. *..*** :*..*** ~ ****** : ****** ~ ****** :****** ~ ****** : ****** ; ****** ~ ..*...:.**..* ~------~------~

0-+----,---.----,...---,,-.---------,-.---------,-.----------+

1.639 1.649 1.659 1.669 1.679 1.689 1.699 1.700 1.719 1.729 1.739 1.749 1.759 1.769 1.779 1.789

... ---1 TOTAL UNRCX:CED INTEC:RATED RAa.Al PE.AKI I\G FACTffi- 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 23-MP2-001 March 2, 2023

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 29 1.20 - ~- ~ ~~ - ~~-~~~-~~~-~~~-~~-~~~ - ~~ -~

1 1 1 1 1 1 1 1 1 1 1

**----- -----+----- -----~------

1

i----- -----~----- -----+----- -----~----- -----~----- ........ .;. ..... -----~------ -----i----- -----~-----

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----- -----+----- ****-1**---- -----t----- -----}----- -----+----- -----t----- -----t----- -----+----- -----1------ -----!----- -----}-----

1.00 -

UNACCEPTABLE + - - (;0.10, 1.0) ,

O~ElG~~~N 1------ -----(-- ~ -----t----- -----*----- - - f", --t-*--- -----i ~1i16

; ; (0.1~, 1.0) --1 UNACCEPTABLE O 1~N

+--

~ 0.90

~

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0 .80 +---+--+----+- (-0.3, 0.80) : : :

- - -~- - - 1' -----1-----+--+---- -----,-

: (0.30, 0.80) --+---+-~

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~ 0.70 : : : I : : : :

UJ F -----. ----- -----r----- -----r----

i----- ----- ..... -----r---- -----1----- ----- ----- ----- ---------- ------ ----- ----- ----- -----

: : : : : : I

@0 .60 ! ! !

<e ! 1 f ACCEPTABLE ................. ----- ............................. ............................ -----

~ O.50 +---+--+--+---+--+-+---I--+--+---+ OPERATION

~ __________ -----t----- ----+---- ----+---- _____!_____ _ REG ION . _________________________ ,------ ___________________ _

e 0.40

~ 0.30 ..... -----

I : :

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t .

1 l

1 I : I

---t---- ----*t-*--- -----i----- -----! ----- -----t----- -----1------ -----1----- ----- ----- :

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0 .20 ->---+--+--+---+-+---+--+---+---+-+--+--+--+---+---+-- -+--+---+---+-+---+--+--t 0.10 -f---t--+---+--t---1-+---+---+---+-!--t-t---t--+---+--t-----if--+-!- -!f---t--+--+--t---1 0.00 - ~ : - ~ - - ~- ~--+- I ~ - - ~ - ~ - - - + - - - - ~----~ I I- - - ~ - + - ~ - t

-0.6 -0.5 -0.4 -0 .3 -0.2 -0.1 0 0 .1 0 .2 0.3 0.4 0.5 0 .6 AXIAL SHAPE INDEX (ASI)

Figure 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 TRM 8.1-13 LBDCR 23-MP2-001 March 2, 2023

ML23116A088

Text

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