ML063260262

Core Operating Limits Reports, Cycle 18, Revised to Incorporate Changes in the Header and a Typographical Correction

ML063260262
Person / Time
Site:	Millstone
Issue date:	11/14/2006
From:	Price J Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-1003
Download: ML063260262 (14)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station 1 D Dominion Rope Ferry Road Waterford, CT 06385 NOV I 4 2 U.S. Nuclear Regulatory Commission Serial No. 06-1003 Attention: Document Control Desk NSS&L/DF RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT, CYCLE 18 In accordance with the Millstone Power Station Unit 2 Technical Specifications, Section 6.9.1.8.d, Dominion Nuclear Connecticut, Inc., hereby submits, as Enclosure 1, the Cycle 18 Core Operating Limits Report (COLR).

The Millstone Power Station Unit 2 COLR has been revised to incorporate changes for Cycle 18 operation. The changes consist of cycle number changes in the headers and a typographical correction to Reference 3.3. Additionally, coordinate "C" on the Axial Shape Index, Figure 2.5-1, was changed from (0.04, 101) to (0.00, 101), and this change was determined to be acceptable with regard to the safety analysis. No change was required to the operating limits in order to produce acceptable safety analysis results.

The COLR has been incorporated into the Millstone Power Station Unit 2 Technical Requirements Manual.

If you have any questions or require additional information, please contact Mr. David W.

Dodson at (860) 447-1791, extension 2346.

Very truly yours, JAn Price ie Vice President - Millstone

-4oo

Serial No. 06-1003 Docket No. 50-336 Core Operating Limits Report, Cycle 18 Page 2 of 2

Enclosures:

(1)

Commitments made in this letter: None.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Serial No. 06-1003 Docket No. 50-336 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 18 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

TECHNICAL REQUIREMENTS- MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 18 I

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. The Technical Specifications affected by this report are listed below:

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

The SHUTDOWN MARGIN shall be >_3.6% AK/K 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4)

The moderator temperature coefficient shall be:

MILLSTONE - UNIT 2 TRM 8.1-1 LBDCR 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL Aooendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 18

a. Less positive than 0.7x10-4 AK/K/°F whenever THERMAL POWER is _*70% of RATED THERMAL POWER,

b. Less positive than 0.4x10-4 AK/K/°F whenever THERMAL POWER is> 70%

of RATED THERMAL POWER,

c. Less negative than -3 .2 x104 AK/K/IF at RATED THERMAL POWER.

2.4 Regulating CEA Insertion Limits (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 hours 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 (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 Specification 3/4.2.6.1) is >_360,000 gpm.

b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Specification 3/4.2.6.1) is < 360,000 gpm and _Ž 354,600 gpm.

c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Specification 3/4.2.6.1) is < 354,600 gpm and Ž 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 Incore 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 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 18 I 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR - FrT (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 Ž_360,000 gpm.

< 1.664 whenever the reactor coolant flow rate is < 360,000 gpm and -e354,600 gpm.

< 1.639 whenever the reactor coolant flow rate is < 354,600 gpm and Ž_349,200 gpm.

2.6.1. The Power Dependent FT limits, whenever the reactor coolant flow rate is Ž_360,000 gpm, are shown in Figure 2.6-1.

2.6.2. The Power Dependent FT limits, whenever the reactor coolant flow rate is < 360,00 gpm and Ž_354,600 gpm, are shown in Figure 2.6-2.

2.6.3. The Power Dependent FT 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 (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 FrT limits as specified in Sections 2.5 and 2.6.

or

Ž354,600 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.

or

Ž349,200 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 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL ApDendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 18

3. ANALYTICAL METHODS The analyical methods used to determine the core operating 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 I and 2, "Reactor Analysis System for PWRs Volume I - 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: Arnalysis 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), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based,"

Framatome AN, March 2001.

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 Nuclear 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 Bumup," 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 Bumups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.

MILLSTONE - UNIT 2 TRM 8.1-4 LBDCR 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL.

Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 18 I 3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1988.

3.12 ANF-89-151 (P)(A), UANF-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-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, Framatome ANP, May 2001.

3.15 EMF-92-153(P)(A), and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, March 1994.

MILLSTONE - UNIT 2 TRM 8.1-5 LBDCR 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 18 I (1.W0, BANK 7 @ 135 Steps) 1.00 0.90 0.80

-00.70 a.

0.60 00.50 OA0 I 1 I I 0

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14 1 I "

I I 180 144 108 72 36 0 180 144 108 72 36 0 CEA Position (steps witbdrawn)

FIGURE 2.4-1 CEA Insertion Limit vs. THERMAL POWER With Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 TRM 8.1-6 LBDCR 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT CYCLE 18 I 120 UNACCEPTABLE OPERATION REGION 110

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FIGURE 2.5-1 AXIAL SHAPE INDEX vs.

PERCENT OF ALLOWABLE POWER LEVEL MILLSTONE - UNIT 2 TRM 8.1-7 LBDCR 06-MP2-035 October 5, 2006

- TECHNICAL REQUIREMENTS MANUAL ADpendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 18

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1.69 1.70 1.71 1.72 1.73 1.74 1.75 1.76 1.77 1.78 1.79 1.80 1.81 1.82 1.83 1.84 TOTAL UNJfDDED NTEGRATED RADIAL PEWC FPCTOR- FT Note: The FrT limit should be reduced for reactor coolant flow rates 349,200 gpm and < 360,000 gpm (see Section 2.6).

FIGURE 2.6-1 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable Rated Thermal Power For Reactor Coolant Flow Rates

• 360,000 gpm MILLSTONE - UNIT 2 TRM 8.1-8 LBDCR 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL ADpendix 8,1 CORE OPERATING LIMITS REPORT, CYCLE 18 I 100. 1.6 S(64 . . .1.0.

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01 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 LMCM HTEGRATED RADLAL PEAANG FACT'R FT 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 TRM 8.1-9 LBDCR 06-MP2-035 October 5, 2006

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 18 100" (1.653R1 1M

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TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 18 12'U *t - - Y - Y - I - - - - V - - V - - - -

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-0.6 -0.5 -OA -0.3 2 -0.1 0 0.1 0.2 0.3 0.4 0.5 0.6 Axial Shape Index FIGURE 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 TRM 8.1-11 LBDCR 06-MP2-035 October 5, 2006