ML111040421

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Cycle 24 Core Operating Limits Report, Revision 0
ML111040421
Person / Time
Site: Surry Dominion icon.png
Issue date: 04/14/2011
From: Funderburk C
Dominion, Virginia Electric & Power Co (VEPCO), Dominion Resources Services
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
11-196
Download: ML111040421 (10)
v • d • e


Text

Dominion Resources Services, Inc.

Innsbrook Technical Center Dominion 5000 Dominion Boulevard, 25E, Glen Allen, VA 23060 April 14,2011 United States Nuclear Regulatory Commission Serial No.11-196 Attention: Document Control Desk NL&OS/vlh RO Washington, D.C. 20555 Docket No. 50-281 License No. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 2 CYCLE 24 CORE OPERATING LIMITS REPORT, REVISION 0 Pursuant to Surry Technical Specification (TS) 6.2.C, enclosed is a copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 24 Pattern UPG, Revision O.

If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.

Sincerely,

~

C. L. Funderburk, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitment Summary: There are no new commitments as a result of this letter.

Serial No.11-196 Docket No. 50-281 COLR-S2C24 Rev. 0 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. J. S. Wiebe NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.11-196 Docket No. 50-281 CORE OPERATING LIMITS REPORT Surry 2 Cycle 24 Pattern UPG Revision 0 March 2011 Virginia Electric and Power Company Surry Power Station Unit 2

Serial No.11-196 Docket No. 50-281

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 24 has been prepared in accordance with the requirements of Surry Technical Specification 6.2.C.

The Technical Specifications affected by this report are:

TS 2.1 - Safety Limit, Reactor Core TS 2.3.A.2.d - Overtemperature ilT TS 2.3.A.2.e - Overpower ilT TS 3.1.E - Moderator Temperature Coefficient TS 3.12.A.1, TS 3.12.A.2, TS 3.12.A.3 and TS 3.12.C.3.b.1(b) - Control Bank Insertion Limits TS 3.12.A.1.a, TS 3.12.A.2.a, and TS 3.12.G - Shutdown Margin TS 3.12.B.1 and TS 3.12.B.2 - Power Distribution Limits TS 3.12.F - DNB Parameters TS Table 4.1-2A - Minimum Frequency for Equipment Tests: Item 22 - RCS Flow

2.0 REFERENCES

1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003.

Methodology for:

TS 3.1.E - Moderator Temperature Coefficient TS 3.12.A.1, TS 3.12.A.2, TS 3.12.A.3 and TS 3.12.C.3.b.1(b) - Control Bank Insertion Limit TS 3.12.A.1.a, TS 3.12.A.2.a and TS 3.12.G - Shutdown Margin TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor and Nuclear Enthalpy Rise Hot Channel Factor TS 3.12.F - DNB Parameters TS Table 4.1-2A - Minimum Frequency for Equipment Tests: Item 22 - RCS Flow

2. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," (Westinghouse Proprietary), January 2005.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor

3. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," (Westinghouse Proprietary), August 1985.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor COLR-S2C24, Rev. 0 Page 1 of 7

Serial No.11-196 Docket No. 50-281

4. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code,"

(Westinghouse Proprietary), August 1985.

Methodology for:

TS 3.l2.B.1 and TS 3.l2.B.2 - Heat Flux Hot Channel Factor

5. WCAP-1261O-P-A, "VANTAGE+ Fuel Assembly Report," (Westinghouse Proprietary), April 1995.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor

6. WCAP-1261O-P-A and CENPD-404-P-A, Addendum I-A, "Optimized ZIRLO,"

(Westinghouse Proprietary), July 2006.

Methodology for:

TS 3.l2.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor

7. VEP-NE-2-A, Rev. 0, "Statistical DNBR Evaluation Methodology," June 1987.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor

8. VEP-NE-3-A, Rev. 0, "Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code," July 1990.

Methodology for:

TS 3.12.B.1 and TS 3.l2.B.2 - Nuclear Enthalpy Rise Hot Channel Factor

9. DOM-NAF-2-A, Rev. 0.2-P-A, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code," including Appendix B, "Qualification of the Westinghouse WRB-1 CHF Correlation in the Dominion VIPRE-D Computer Code," August 2010.

Methodology for:

TS 3.12.B.1 and TS 3.l2.B.2 - Nuclear Enthalpy Rise Hot Channel Factor

10. WCAP-8745-P-A, "Design Bases for Thermal Overpower Delta-T and Thermal Overtemperature Delta-T Trip Function," September 1986.

Methodology for:

TS 2.3.A.2.d - Overtemperature LlT TS 2.3.A.2.e - Overpower LlT COLR-S2C24, Rev. 0 Page 2 of7

Serial No.11-196 Docket No. 50-281 3.0 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 Technical Specification 6.2.C.

3.1 Safety Limit, Reactor Core (TS 2.1) 3.1.1 The Reactor Core Safety Limits are presented in Figure A-I.

3.2 Overtemperature AT (TS 2.3.A.2.d)

Where:

L1T is measured RCS L1T, of.

L1To is the indicated L1T at RATED POWER, of.

s is the Laplace transform operator, sec':

T is the measured RCS average temperature (Tavg) , of.

T' is the nominal T avg at RATED POWER,:S 573.0°F.

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure > 2235 psig.

K 1 :s 1.1425 K2 :::: 0.01059/oF K3 2: 0.000765 /psig ti > 29.7 seconds t2:S 4.4 seconds f(t.I) 2: 0.0268 { (qt- qb)}, when (qt- qb) < -24.0% RATED POWER 0, when -24.0% RATED POWER:S (qt - qb):S 8.0% RATED POWER 0.0188 {(qt - qb) - 8.0}, when (qt - qb) > +8.0% RATED POWER Where qt and qb are percent RATED POWER in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RATED POWER.

COLR-S2C24, Rev. 0 Page 3 of7

Serial No.11-196 Docket No. 50-281 3.3 Overpower AT (TS 2.3.A.2.e)

Where:

~T is measuredRCS ~T, OF.

~To is the indicated ~T at RATED POWER, oF.

s is the Laplace transform operator, sec":

T is the measuredRCS average temperature (Tavg) , OF.

T' is the nominal T avg at RATED POWER,::; 573.0°F.

~:S 1.0965 x, ~ 0.0198 fOP for increasing T avg  !< T'

~ 0 lOP for decreasing T avg ~ 0 forT :ST' t3 ~ 9.0 seconds f(M) =as defined above for OTLlT 3.4 Moderator Temperature Coefficient (TS 3.1.E) 3.4.1 The Moderator Temperature Coefficient (MTC) limits are:

+6.0 pcm/°P at less than 50 percent of RATED POWER, and

+6.0 pcm/°P at 50 percent of RATED POWER and linearly decreasing to 0 pcm/°P at RATED POWER 3.5 Control Bank Insertion Limits (TS 3.12.A.1, TS 3.12.A.2 and TS 3.12.C.3.b.1(b>>

3.5.1 The control rod banks shall be limited in physical insertion as shown in Figure A-2.

3.5.2 The rod insertion limit for the A and B control banks is the fully withdrawn position as shown on Figure A-2.

3.5.3 The rod insertion limit for the A and B shutdown banks is the fully withdrawn position as shown on Figure A-2.

3.6 Shutdown Margin (TS 3.12.A.1.a, TS 3.12.A.2.a and TS 3.12.G) 3.6.1 Whenever the reactor is subcritical the shutdown margin (SDM) shall be ~ 1.77 %Llk/k.

COLR-S2C24, Rev. 0 Page 4 of7

Serial No.11-196 Docket No. 50-281 3.7 Power Distribution Limits (TS 3.12.B.1 and TS 3.12.B.2) 3.7.1 Heat Flux Hot Channel Factor - FQ(z)

CFQ FQ(z) ~ pK(z) for P > 0.5 CFQ FQ(z) ~ o:sK(z) for P s 0.5 THERMAL POWER where: P = RATED POWER 3.7.1.1 CFQ=2.5 3.7.1.2 K(z) = 1.0 for all core heights, z 3.7.2 Nuclear Enthalpy Rise Hot Channel Factor - F~H(N)

F~H(N) ~ CFDH * (l + PFDH(l- P)}

THERMAL POWER where: P = RATED POWER 3.7.2.1 CFDH= 1.56 3.7.2.2 PFDH=0.3 3.8 DNE Parameters (TS 3.12.F and TS Table 4.1-2A) 3.8.1 Departure from Nucleate Boiling (DNB) Parameters shall be maintained within their limits during POWER OPERATION:

  • Pressurizer Pressure 2: 2205 psig

COLR-S2C24, Rev. 0 Page 5 of7

Serial No.11-196 Docket No. 50-281 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660 650

,I I 238 Ll.

i___........ n~i___

.. r----

VI 3l 640 22::\

1 I I

110 I

~ 630 """"--

.. r--- """"'--

<IJ I~ 198, psig """"'~I' 10.. 620

J i, i -r--.....

<IJ E610

<IJ

~

III 600 I

i I

I II r---- _i;~

- r---- ------ - "'-",,,

- ----1,""'- ----" '-

~ 590

<t Cii

~ 580 ~~.

<IJ <,

570 560 r

550 o 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power COLR-S2C24, Rev. 0 Page 6 of7

Serial No.11-196 Docket No. 50-281 Figure A*2 Surry 2 Cycle 24 ROD GROUP INSERTION LIMITS Fully wid position = 225 steps 230 (0.4625, 225) 220 210 200 190 180

-V-BANK I (1.0, 183) 170 160 150 lZ

¥ (0, 151)

"C I l'

VI 140 c..

....OJ 130 VI r::.' 120 I 0 I

~

"Vi 0 110 I

I / I Q.

e,

J 100 4 V

0 D-BANK C)

"C 0

90 l'

/'

c:::

80 70 I

60 50 40 30 20

~23)

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10 .

0 o 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Fraction of Rated Power COLR-S2C24, Rev. 0 Page 7 of7

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