ML021000340

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Core Operating Limits Report, Cycle 15 for Millstone Nuclear Power Station, Unit 2
ML021000340
Person / Time
Site: Millstone Dominion icon.png
Issue date: 03/25/2002
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
B18619
Download: ML021000340 (11)
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Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station SDominion Rope Ferry Road Waterford, CT 06385

'!Al 2 5 2002 Docket No. 50-336 B18619 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Core Operating Limits Report, Cycle 15 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 15 Core Operating Limits Report (COLR).

The Millstone Unit No. 2 COLR has been revised to incorporate changes for Cycle 15 operation. The changes included the most negative moderator temperature coefficient permitted and linear heat rate limit.

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.

Si President - Millstone Enclosure (1) cc: H. J. Miller, Region I Administrator R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector, Millstone Unit No. 2 CiA

Docket No. 50-336 B18619 Enclosure 1 Millstone Nuclear Power Station, Unit No. 2 Core Oreratina Limits ReDort. Cycle 15

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 15

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-- Tavg > 200°F 2.2 3/4.1.1.2 SHUTDOWN MARGIN - Tavg < 2000F 2.3 3/4.1.1.4 Moderator Temperature Coefficient 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 -- FT 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 -- Tavg > 200°F (Specification 3/4.1.1.1)

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

The SHUTDOWN MARGIN shall be > 3.6% AK/K 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4)

The moderator temperature coefficient shall be:

Millstone - Unit 2 TRM 8.1-1 TRMCR 01-2-2 March 8, 2002

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT. CYCLE 15

a. Less positive than 0.7x10

.. AK/K/ 0 F whenever THERMAL POWER is < 70% of RATED THERMAL POWER,

b. Less positive than 0.4xi0 AK/K/°F whenever THERMAL POWER is> 70% of RATED THERMAL POWER,
c. Less negative than -3.2x104 AK/K/OF 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 andto 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 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 15.1 kw/ft.

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.

2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR -- FrT (Specification 3/4.2.3)

The calculated value of FrT shall be < 1.69.

2.6.1. The Power Dependent FrT limits are shown in Figure 2.6-1.

Millstone - Unit 2 TRM 8.1-2 TRMCR 01-2-3 March 8, 2002

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 15 I 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 < 5490 F
b. Pressurizer Pressure > 2225 psia*
c. Reactor Coolant Flow Rate > 360,000 gpm
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 TRMCR 01-2-2 March 8, 2002

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 15

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 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-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 EMF-84-093(P)(A) Revision 1, "Steamline Break Methodology for PWRs," Siemens Power Corporation, February 1999.

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

3.6 EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based,"

Framatome ANP, March 2001.

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

3.8 XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983.

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

3.10 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.

3.11 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.

Millstone - Unit 2 TRM 8.1-4 TRMCR 01-2-2 March 8, 2002

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 15 I 3.12 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1988.

3,13 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.

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

3.15 EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," FramatomeANP, May 11, 2001.

Millstone - Unit 2 TRM 8.1-5 TRMCR 01-2-2 March 8,2002

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 15 I (1.00, BANK 7 @ 135 Steps) 1.00 0.90 0.80 S0.70 0

(.

S0.60 0.50:

"o0.40 0

L~ 0.30 I 1, 51 I I 144 108 72 36 0 J 1 1W 36 0 180 144 108 CEA Position (steps withdrawn)

FIGURE 2.4-1 CEA Insertion Limit vs. THERMAL POWER With Four Reactor Coolant Pumps Operating Millstone - Unit 2 TRM 8.1-6 TRMCR 01-2-2 March 8, 2002

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 15 I 120

.UNACCEPTABLE OPERATION.

110 .. .. 0-----. _ -. 0.0.. .. -------------- - - - -_

- - - - -AC A-LE -----

100 Lu 90

(-.3 65 ra Pont (0"3. 65 0

80

-J C.(00,101)

(L 70 I

I-0 60 ILl I.- ------ . B. (0.00-.1-0) .;---- -- . ----------

a:

50

. ..... ----.- - -....... : ~~~D.

E. (+0.30. 65)

(40.08,.100) .. ...

I-l "40 30 Note: Point "C is provided for selting plant instrumentation only.

20 S..........

. ......... Operation is not allowed abrove 100%/ of rated power. . . . . . . . . . . .

10 -------- -- - ---.--------

0

-00.4 -0.3 -0.2 -0.1 0 0.1 0.2 0.3 0.4 AXIAL SHAPE INDEX (ASI)

FIGURE 2.5-1 AXIAL SHAPE INDEX vs.

PERCENT OF ALLOWABLE POWER LEVEL Millstone - Unit 2 TRM 8.1-7 TRMCR 01-2-2 March 8, 2002

  • 0 , ii i* i i
  • , N C4

"

  • I ' '  :

--eI .. . . . . .. . ., . . . . .. *.. . ............... .... ,...... co z'oi*l c

, ,* , I , " ,I,*

  • I I ,I I 0.-0 hzlO. *:*,"

.. ............ ow M.L<  :................. 1.1 LLJ 0

. .6 .. . .. . . . . . . . : . . . . . . . . . . .. . . . . . . . .. .

  • Z C

.. ' 0 z CYC 0~L 00 0~~ ~ ( ~ N ~0~ LU <~I)

....... ........ ... d ew.. ~.. ....... ....... ......

JgI O II~q p*8 I. ~elq, I.e~ l

TECHNICAL REQUIREMENTS MANUAL Appendix 8.1 CORE OPERATING LIMITS REPORT, CYCLE 15 I 1.20 1.10 1.00 UNACCEPTABLE  : . UNACCEPTABLE:

OPERATION "  : 0 10) ( 1.0) OERATION w REGION:  :  :  : N

EGO 0

-j o<a 0.90 LU ...-- ------- ---------------- --------- --

I 0.80 (-0.30. 0.80) ,  ;- i " "- (0.30, 0.8O)

U'

- .  :  : ACCEPTABLE bL OPERATION 0 ______ _____ - REGION z 0.70 0

U- 0.60

!  :".... ...... . i.... " "' ....  ;

0.50 0.40

-0.4 -0.3 -0.2 -0.1 0 0.1 0.2 0.3 0.4 0.5 0.6

-0 .6 -0.5 Axial Shape Index FIGURE 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating Millstone - Unit 2 TRM 8.1-9 TRMCR 01-2-2 March 8, 2002

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