ML033530078

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Core Operating Limits Report, Cycle 16
ML033530078
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/08/2003
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
B19023
Download: ML033530078 (13)
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Text

Dominion Nuclear Connecticut, Inc. Dominion MGillstone Power Station Rope Ferry Road Waterford, CT 06385 DEC 8 2M Docket No. 50-336 B19023 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Power Station, Unit No. 2 Core Operating Limits Report, Cycle 16 In accordance with the Millstone Unit No. 2 Technical Specifications, Section 6.9.1.8.d, Dominion Nuclear Connecticut, Inc., hereby submits, as Enclosure 1, the Cycle 16 Core Operating Limits Report (COLR).

The Millstone Unit No. 2 COLR has been revised to incorporate changes for Cycle 16 operation. The changes included revisions to Section 3.0, Analytical Methods, and Figure 2.5-1, Axial Shape Index vs. Percent of Allowable Power Level.

The COLR has been incorporated into the Millstone Unit No. 2 Technical Requirements Manual.

There are no regulatory commitments contained within this letter.

Should there be any questions regarding this submittal, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.

Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.

J. P(a]rice Sitvc President - Millstone Enclosure (1) cc: H.J. Miller, Region I Administrator R. M. Pulsifer, NRC Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector

Docket No. 50-336 B1 9023 Enclosure 1 Millstone Power Station, Unit No. 2 Core Operating Limits Report, Cycle 16

TECHNICAL REQUIREMENTS MANUAL I Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 16

  • 1
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 Specification 2.1 3/4.1.1.1 SHUTDOWN MARGIN -Tm > 2000F 2.2 314.1.1.2 SHUTDOWN MARGIN.-Tg < 200°F 2.3 3/4.1.1.4 Moderator Temperature Coefficient 2.4 314.1.3.6 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 Inthe following subsections. These limits have been developed using the NRC-approved methodologies specified In Section 3.

2.1 SHUTDOWN MARGIN - Tg > 200F (Specification 3/4.1.1.1)

The SHUTDOWN MARGIN shall be > 3.6% AK/K 2.2 SHUTDOWN MARGIN - Tavg < 200F (Specification 3/4.1.1.2)

The SHUTDOWN MARGIN shall be > 3.6% AK/K 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1 A)

The moderator temperature coefficient shall be:

Millstone Unit 2 TRM 8.1 -1 LBDCR 03-2-11 November 13,2003

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 16

a. Less'positive than 0.7x104 AK/iKF whenever THERMAL POWER Is 5 70%

of RATED THERMAL POWER,

b. Less positive than 0.4x1 0 AKIKP F whenever THERMAL POWER Is > 70%

of RATED THERMAL POWER,

.c. Less negative than -3.2x10' AK(K/ 0F at RATED THERMAL POWER 2A Regulating CEA Insertion Limits (Specification 314.1.3.6)

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. c 14 Effective Full Power Days per calendar year.

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 Ž 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 2 354,600 gpm.

c) 14.9 kvwIft whenever the reactor coolant flow rate (determined per Specification 3/4.2.6.1) Is < 354,600 gpm and 2 349,200 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 setpolnts shall be adjusted to less than or equal to the limit when the following factors are appropriately Included In the setting of the alarmis:

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 03-2-11 November 13, 2003

TECHNICAL REQUIREMENTS MANUAL ApDendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 16 I

2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR - FrT (Specification 314.2.3)

The calculated value of FrTat RATED THERMAL POWER shall be:

a; 1.690 whenever the reactor coolant flow rate Is > 360,000 gpm.

5 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 FrT limits, whenever the reactor coolant flow rate Is 2 360,000 gpm, are shown In Figure 2.6-1.

2.6.2. The Power Dependent FrT limits, whenever the reactor coolant flow rate is

< 360,00 gpm and 354,600 gpm, are shown InFigure 2.6-2.

2.6.3. The Power Dependent FrT limits, whenever the reactor coolant flow rate Is

< 354,600 gpm and 2 349,200 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 I-Lmits Four Reactor Coolant Pumps Operations

a. Cold Leg Temperature < 5490F
b. Pressurizer Pressure > 2225 psia-
c. Reactor Coolant Flow Rate > 360,000 gpm with Linear Heat Rate and FrT limits as specified InSections 2.5 and 2.6.

or

> 354,600 gpm with Linear Heat Rate and FrT limit reductions as specified InSections 2.5 and 2.6.

or

> 349,200 gpm with Linear Heat Rate and FrT limit reductions as specified InSections 2.5 and 2.6.

d. AXIAL SHAPE INDEX FIGURE 2.7-1
  • Limit not applicable during either the THERMAL POWER ramp Increase Inexcess 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 03-2-11 November 13,2003

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 16

3. ANALYTICAL METHODS The analytical 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 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-92-21 (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 I 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 ANP, 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 I and Supplements 2,4, and 5, Qualification of Exxon Nuclear Fuel for Extended Bumup," Exxon Nuclear Company, October 1986.

3.10 ANF-8-133(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 03-2-11 November 13,2003

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 16 I

3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium Dioxide/Gadolinla irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1988.

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-1 961 (P)(A) Revision 0, "Statistical SetpointlTransient 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 03-2-11 November 13,2003

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 16 I

0.70 0.60 I 050 0.40'

,r 0.30 180 144 108 72 36 0 180 144 14 CEA Poi (e  % mn)

I-r FIGURE 2.4-1 CEA Insertion Limit vs. THERMAL POWER With Four Reactor Coolant Pumps Operating Millstone'. Unit 2 TRM 8.146 LBDCR 03-211 November 13, 2003

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 16 I.

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PERCENT OF ALLOWABLE POWER LEVEL Millstone - Unit 2 TRM 8.1 -7 LBDCR 03-2-11 November 13,2003

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 16 100. (1.690,100°)

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TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 16 10D (I.W4 100)  ;  ;  ;  ;  ; '  ;  ; '  ; '  ;

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TECHNICAL REQUIREMENTS MANUAL Apnendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 16 100- \ 169100)  ;-

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. 1.679. ~~v. 1.689Aloal 169 1.7G9 Rae 1.719 Thermal 1.729 1.739 1.749 1.759.o.er 1.769 1.779 1.789 TOT)AL UJDOB) INTEGRA B) RADIAL PEAK<ING FAC1TOR- FJ FIGURE 2.6-3 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable Rated Thermal Power For Reactor Coolant Flow Rates < 354,600 gpm and 2 349,200 gpm Milstone . Unit 2 TRM 8.1-10 . LBDCR 03-2-11

. ~~~~~~~~~~~November 13, 2003

II TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 16 I 120 1.10

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FIGURE 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating Millstone Unit 2 TRM 8.1-11 LBDCR 03.2.11 November 13, 2003

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