ML103190515

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Cycle 24 Core Operating Limits Report, Revision 0
ML103190515
Person / Time
Site: Surry Dominion icon.png
Issue date: 11/12/2010
From: Funderburk C
Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
10-659
Download: ML103190515 (10)
v • d • e


Text

Dominion Resources Services, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard. 2S£ . Glen Allen. VA 23060 November 12, 2010 United States Nuclear Regulatory Commission Serial No.10-659 Attention: Document Control Desk NL&OS/GDM: RO Washington, D.C. 20555 Docket No. 50-280 License No. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 1 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 1 Cycle 24 Pattern OWL ,

Revision O. This revision to the COLR incorporates updates to TS references , reactor core safety limits, OT~T and OP~T setpoints, power distribution limits, and DNB parameters consistent with implementation of recently approved TS amendments 269 and 270.

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.10-659 Docket No. 50-280 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower, NE 245 Peachtree Center Avenue Suite 1200 Atlanta, Georgia 30303-1257 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.10-659 Docket No. 50-280 Enclosure COLR-SIC24, Revision 0 CORE OPERATING LIMITS REPORT Surry 1 Cycle 24 Pattern OWL COLR-SIC24, Rev. 0 Page 1 of8

Serial No.10-659 Docket No. 50-280 Enclosure

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 1 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 - ISafety Limit, Reactor Core TS 2.3 .A!.2.d - Overtemperature ~ T TS 2.3.A.2 .e - Overpower ~ T TS 3.1.E - Moderator Temperature Coefficient TS 3.12.A.l , TS 3.12 .A.2 , TS 3.12.A.3 and TS 3.12.C.3 .b.l(b) - Control Bank Insertion Limits TS 3.12.A.l.a, TS 3.12.A.2.a, and TS 3.12.G - Shutdown Margin TS 3.12.B.l 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.l , 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.l.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.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor

3. WCAP-I0054-P-A, " Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," (Westinghouse Proprietary), August 1985 Methodology for:

TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor COLR-SIC24, Rev. 0 Page 2 of8

Serial No.1 0-659 Docket No. 50-280 Enclosure

4. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," (Westinghouse Proprietary), August 1985 Methodology for:

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

5. WCAP-1261O-P-A, "VANTAGE+ Fuel Assembly Report," (Westinghouse Proprietary), June 1990 Methodology for:

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

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

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

7. VEP-NE'-3-A, Rev. 0, "Qualification of the WRB-l CHF Correlation in the Virginia Power COBRA 1Code," July 1990 Methodology for:

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

8. 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 liT TS 2.3.A.2.e - Overpower liT I

I COLR-S1C24, Rev. 0 Page 3 of8

Serial No.10-659 Docket No. 50-280 Enclosure 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)

!:J.T :s:; !:J.To [ K1 - Kz ( 1 + t 1 S),

(T - T ) + K3 (P - P,) - [(M) ]

1 + tzs Where:

!:J.T is measured RCS !:J.T, of.

!:J. To is the indicated !:J.T at RATED POWER, of.

s is the Laplace transform operator, sec":

T is the measured RCS average temperature (T avg) , OF.

T' is the nominal Tavg at RATED POWER, ~ 573.0°F.

P is the measured pressurizer pressure, psig.

p' is the nominal RCS operating pressure 2: 2235 psig.

Kl < 1.1425 K 2 2: 0.01059 / oP K3 2: 0.000765 /psig t[ 2: 29.7 seconds t2 ::; 4.4 seconds f(~I) 2: 0.0268 { (qt - qb)}, when (qt - qb) < -24.0% RATED POWER 0, when -24.0% RATED POWER::; (qt - qb) ::; 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-S1C24, Rev . 0 Page 4 of8

Serial No.10-659 Docket No. 50-280 Enclosure 3.3 Overpower AT (TS 2.3.A2.e)

!1T s !1To [K4 - Ks (1 ~:3J T - K6(T - T') - f(!1I)]

Where: ~T is measured RCS ~T, OF.

~To is the indicated ~T 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.

~ :s 1.0965 x, 2: 0.0198 /oP for increasing Tavg K6 2: 0.001074 /oP for T > T' 2: 0 /oP for decreasing T avg 2: 0 for T :s T' t3 2: 9.0 seconds f(.-11) = as defined above for OT.-1T 3.4 Moderator Temperature Coefficient (TS 3.1.E) 3.4.1 The Moderator Temperature Coefficient (MTC) limits are:

+6.0 pcmfP 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/°F at RATED POWER 3.5 Control Bank Insertion Limits (TS 3.12.A l, TS 3.12.A2 and TS 3.12 .C.3.b.l (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.A1.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 2: 1.77 %.-1k/k.

COLR-SIC24, Rev. 0 Page 5 of8

Serial No.10-659 Docket No. 50-280 Enclosure 3.7 Power Distribution Limits (TS 3.12.B.l and TS 3.12.8.2) 3.7.1 Heat Flux Hot Channel Factor - FQ(z)

CFQ FQ(z) :s; pK(z) for P > 0.5 CFQ FQ(z) :s; 05 K(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 - FilH(N)

Fb.H(N) s CFDH * {I + 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 DNB 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

Serial No.10-659 Docket No. 50-280 Enclos ure Figure A-1 REACTOR CORE THERMALAND HYDRAULIC SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660

- - -j ...._.._ - _....-

f 630 +----+--=-~=--j----r__----!--:-::::::-r_:__- -t-----'=-_.;.o;;;;;:::::___+_-"""""

Q QJ

~ 620 sQJ E 610 +---+---+---j---f--~-_=-+---+--.=::::t!-_d----+-~-P"""---I

~

QJ

~ 600 QJ

~

m 590 +----+ - - -+-- - -j-----if---------+-- - + ----+----+-- -+-- -l---,,-P....----i QJ I I I 570 - - - - _ + _ -----l------L-_~__

550 'r- f--------***-**--f-*** ** * * * * * --+ ---....-_..- -.. . - ... -~---- . .---J.._...- -L.- ---,-..---- J-..-_*+..*. *. -_... .-. *1-- *..- --

o 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power COLR-S 1C24, Rev. 0 Page 7 of8

Seria l No.10-659 Docket No . 50-280 Enclosure Figure A-2 SURRY UNIT 1 CYCLE 24 ROD GROUP INSERTION LIMITS Fully wid position =230 steps 230

~I I (0.4938, 230) 220

./

V 210 200 /'

190 /

180 ./

V C-BANK (1.0,1 83)

./

170 , /' v:

/'

160 / /

150 V V

'0

~

en 140 (0, 151)

,/

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c.

....en 0) 130 /

~

,£ 120 /'

0

'iii 110 0

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e, C. ./ /O-BANK

3 100 e

0 l-

'0 90 V"

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0 0::: 80 /

70 V 60 V

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50 /

40 /'

30 /

20 V(0, 23) f-10 o

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power COLR-SIC24, Rev. 0 Page 8 of 8

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