ML17017A205

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Update to the Core Operating Limits Report, Cycle 24 Core Operating Limits Report in Support of License Amendment 329 - Small Break Loss of Coolant Accident Reanalysis
ML17017A205
Person / Time
Site: Millstone Dominion icon.png
Issue date: 01/09/2017
From: Stanley B
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17017A205 (15)
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Text

Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385

<lorn.com JAN *o 9 2017 U.S. Nuclear Regulatory Commission Serial No.16-459 Attention: Document Control Desk NSS&L/WEB RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 UPDATE TO THE CYCLE 24 CORE OPERATING LIMITS REPORT IN SUPPORT OF LICENSE AMENDMENT 329 - SMALL BREAK LOSS OF COOLANT ACCIDENT REANALYSIS 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, an update to the Cycle 24 Core Operating Limits Report (COLR).

The MPS2 COLR, which is contained in Appendix 8.1 of the MPS2 Technical Requirements Manual (TRM), was updated to be consistent with changes to the MPS2 TSs that were recently approved by the NRC under License Amendment 329 (ADAMS Accession No. ML16249A001 ). License Amendment 329 revised the MPS2 Technical specifications to add the evaluation model EMF-2328(P)(A), Supplement 1, "PWR (pressurized water reactor) Small Break, LOCA (loss of coolant accident) Evaluation Model, S-RELAP5 Based," and EMF-92-116(P)(A), Supplement 1, "Generic Mechanical Design .Criteria for PWR Fuel Designs," to the TS Section 6.9.1.8.b list of analytical methods used to determine core operating limits as a result of reanalyzing the small break LOCA analysis. MPS2 TRM was updated as follows:

  • Reference 3.5 - Added 'Revision 0 and Supplement 1(P)(A)' to EMF-2328(P)(A) consistent with the NRG-approved changes to TS 6.9.1.8.b.
  • Reference 3.16 - Added 'and Supplement 1(P)(A)' to EMF-92-116(P)(A) consistent with the NRG-approved changes to TS 6.9.1.8.b.
  • The dates listed for References 3.5 and References 3.16 were updated to September 2015 and February 2015 respectively, consistent with the issuance date of Supplement 1(P)(A) for each reference.

The Cycle 24 *cOLR updates have been incorporated into the MPS2 Technical Requirements Manual.

-~-----

Serial No.16-459 Docket No. 50-336 Update to MPS2 Cycle 24 COLR Page 2 of 3 If you have any questions or require additional information, please contact Mr. Jeffry A.

Langan at (860) 444-5544.

Sincerely, JlJ:5-5 B. L. Stanley Director, Nuclear Station Safety and Licensing - Millstone

Enclosure:

Update to the Cycle 24 Core Operating Limits Report Commitments made in this letter: None

Serial No.16-459 Docket No. 50-336 Update to MPS2 Cycle 24 COLR Page 3 of 3 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.16-459 Docket No. 50-336 ENCLOSURE UPDATE TO THE CORE OPERATING LIMITS REPORT, CYCLE 24 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

TECHNICAL REQUIREMENTS MANUAL APPENDIX 1 s:

CORE OPERATING LIMITS REPORT, CYCLE 24

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 MARG!N-(SDM) 2.2 Deleted (Ref. License Amendment 280) 2.3 3/4.1.1.4 Moderator Temperature Coefficient (MTG) 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 specifie<;I in Section 3.

2.1 SHUTDOWN MARGIN- (SDM).(Specification 3/4.1.1.1)

The SHUTDOWN MARGIN shall be~ 3.6% ~K/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 0.7x1 o-4 ~K/K/°F whenever THERMAL POWER is ::;70% of RATED THERMAL POWER,
b. Less positive than 0.4x1 o- 4 ~K/K/°F whenever THERMAL POWER is> 70%

of RATED THERMAL POWER,

c. Less negative than -3.2x10-4 .i1K/K/°F at RATED THERMAL POWER.

MILLSTONE - UNIT 2 TRM 8.1-1 LBDCR 15-MP2-010 October 6 2015

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 2.4 Regulating CEA Insertion Limits (Technical Specificati6n 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 k~/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 S.HAPE 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 TRMS.1-2 LB OCR 15-MP2-010 October 6, 2015

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR-- F/ (Technical Specification 3/4.2.3)

The calculated value of FrT 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 and ~ 354,600 gpm.
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 F/ 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 > 2225 psia*
c. Reactor Coolant Flow Rate ;;:: 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 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 15-MP2-010 October 6, 2015

TECHNICAL REQUIREMENTS MANUAL

( APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24

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.

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.

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.

3.4 XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.

3.5 EMF-2328(P)(A) Revision 0 and Supplement 1(P)(A), "PWR Small Break LOCA

( Evaluation Model S-RELAP5 Based," Framatome ANP, September 2015.

3.6 EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999.

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.

3.8 XN-NF-621 (P)(A) Revision 1, "Exxon Nucle*ar DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983.

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.

3.10 ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burn ups of 62 GWd/MTU," Advanced Nuclear_

Fuels Corporation, December 1991.

MILLSTONE - UNIT 2 TRM 8.1-4 LBDCR 16-MP2-013 November 8, 2016

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.

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.

3.13 EMF-1961 (P)(A) Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000.

3.14 EMF-231 O(P)(A), Revision 1, "SRP Chapter 15 Non-LO CA Methodology for Pressurized Water Reactors," Framatome ANP, May 2004.

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.

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.

MILLSTONE - UNIT 2 TRM 8.1-5 LBDCR 16-MP2-013 November 8, 2016

TECHNICAL REQUIREMENTS MANUAL

.. APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 (1.01), B#IK 7 @US Steps)

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Note: Regulating CEAs that are~ 176 steps withdrawn arE? conside.red fully withdrawn and are acceptable per this figure.

  • Figure 2.4-1 CEA Insertion Limit vs. THERMAL POWER With Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 TRM 8.1-6 LBDCR 15-MP2-010 October 6, 2015

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PERCENT OF ALLOWABLE POWER LEVEL MILLSTONE - UNIT 2 TRM 8.1-7 LBDC R 15-M P2-010 October 6, 2015

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1

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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 8.1-8 LBDCR 15-MP2-010 October 6, 2015

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1

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TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 UW\CCEPf,ill3lE 00 '* * * * *

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TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates < 354,600 gprn and ;:::: 349,200 gprn MILLSTONE- UNIT 2 TRM 8.1-10 LBDCR 15-MP2-010 October 6, 2015

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1

( CORE OPERATING LIMITS REPORT, CYCLE 24 1.20 -~~~~~~-~---~~~~~-----~~~~~

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-0.6 -0.5 -0.4 -o.s -0.2 -0.1 0 0.1 0.2 0.3 0-4 0.5 0.6 AXJALSHAPE INDEX (ASI)

Figure 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 TRM 8.1-11 LBDCR 15-MP2-010 October 6, 2015

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