ML21144A083

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Core Operating Report Surry 2 Cycle 30 Operating Pattern Syk Revision 1
ML21144A083
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/18/2021
From: Standley B
Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
21-181
Download: ML21144A083 (10)
v • d • e


Text

"o"o7"J""2:'9C"'Jr":n aen,vusoso Dominion DominionEnergy.com Energy" l l

May18,2021 United Attention:

States Nuclear Document Regulatory Control Desk Commission Serial No.: 21-181 NRA/GDM: RO

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Washington, D.C.20555 Docket License No.: 50-281 No.:DPR-37 [

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SURRYPOWER STATION UNIT 2 i

COREOPERATING LIMITS REPORT SURRY 2 CYCLE30PATTERN SYK REVISION 1 ,

l Pursuant toSurry PowerStation (Surry) Units 1 and2 Technical (TS)

Specification 6.2.C, attached isa copy oftheCore Operating Limits Report (COLR) S for urry Power [

I Station Unit 2,Cycle 30,Pattern SYK,Revision 1, Therevision changes incorporates associated with therecently approved Surry Units1 and 2 TSAmendments 303/303 that incorporate a newsmall break lossofcoolant accident model into the COLR.

j Ifyou haveany questions Mr.Gary Miller at(804) 273-2771.

or require additional information, pleasecontact !

E Sincerely, j l

[

I B.E.Standley, Director [

Nuclear Dominion Regulatory Energy Affairs Services, Inc. for j

[

Virginia Electric andPower Company g

Attachment:

CoreOperating Limits Report, Surry Unit 2 Cycle 30 PatternSYK,  !

Revision 1 Commitment Summary: There arenonewcommitments contained inthisletter. [

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b b

Serial No.21-181 Docket No.50-281 COLRS2C30 R1 Page2 of2 cc:U.S. Nuclear RegulatoryCommission Region II Marquis One Tower 245 Peachtree Center Avenue,NE I Suite 1200 I Atlanta, Georgia 30303-1257 l I

Mr. Vaughn Thomas  ;

NRCProject Manager Surry

- I U.S. Nuclear Regulatory Commission OneWhite FlintNorth Mail Stop 0 4 F-12 11555 Rockville Pike  ;

Rockville, MD 20852-2738 Mr. G.Edward Miller l

I NRCSenior Project ManagerNorth Anna f U.S. Nuclear Regulatory Commission OneWhite FlintNorth Mail Stop 09E-3 11555 Rockville Pike Rockville, MD 20852-2738 NRCSenior Resident inspector Surry Power Station

Serial No.21-181 Docket No.50-281 Attachment COREOPERATING LIMITS REPORT Surry Unit2 Cycle 30 Pattern SYK Revision 1

Serial No.21-181 Docket No.50-281 COLRS2C30R1 LO L1NTRR.OQDECTLOE This Core Operating Limits Report (COLR) forSurryUnit 2Cycle30has beenprepared inaccordancewith therequirements of Surry Technical Specification 6.2.C.

TheTechnical Specifications affectedbythis are:

report TS2.1SafetyLimit, Reactor Core TS2.3.A.2.d -

Overtemperature AT TS2.3.A.2.e -

Overpower AT TS3.1.E -

Moderator Temperature Coefficient TS3.12.A.1, TS3.12.A.2, TS 3.12.A.3 and TS3.12.C.3.b.1(b) -

Control BankInsertion Limits TS3.12.A.1.a, TS3.12.A.2.a,TS 3.12.A.3.c andTS3.12.G -

Shutdown Margin TS 3.12.B.1 andTS 3.12.B.2Power Distribution Limits (Heat Flux HotChannel and Factor Nuclear Enthalpy RiseHotChannelFactor)

TS3.12.F -

DNBParameters TSTable 4.1-2A -

Minimum Frequency for Equipment Tests: Item 22 RCSFlow 2.0M 1.VEP-FRD-42-A, Revision 2,Minor Revision 2,"Reload Nuclear Design Methodology," October2017.

Methodology for:

TS2.1 Safety Limit, Reactor Core TS3.1.E -

Moderator Temperature Coefficient TS3.12.A.1, TS3.12.A.2, TS3.12.A.3 andTS3.12.C.3.b.1(b) -

Control Bank Insertion Limit TS3.12.A.1.a, TS 3.12.A.2.a, TS3.12.A.3.c and TS3.12.G-Shutdown Margin TS3.12.B.1 andTS3.12.B.2 -

Heat FluxHotChannel Factor andNuclear Enthalpy Rise Hot Channel Factor TS3.12.F -

DNBParameters TSTable 4.1-2A -

Minimum Frequency for Equipment Tests: Item 22 RCSFlow

2. WCAP-16009-P-A, "Realistic Large BreakLOCA Evaluation Methodology Using theAutomated StatisticalTreatment ofUncertainty Method (ASTRUM)," (Westinghouse Proprietary), January2005.

Methodology for:

TS3.12.B.1 andTS3.12.B.2 -

Heat FluxHotChannel Factor 3.EMF-2328(P)(A), "PWRSmall Break LOCAEvaluation Model,S-RELAP5 Based," by assupplemented ANP-3676P, "Surry Fuel-Vendor Independent Small Break LOCAAnalysis," asapproved byNRC Safety Evaluation Report datedMarch 19, 2021.

Methodology for:

TS3.12.B.1 andTS3.12.B.2 -

Heat FluxHotChannel Factor l

Page1of7

SerialNo.21-181 Docket No.50-281 COLRS2C30R1 4.WCAP-12610-P-A, "VANTAGE+ Fuel Assembly (Westinghouse Report," Proprietary),April 1995.

Methodology for:

TS3.12.B.1 andTS3.12.B.2 -

Heat Flux HotChannel Factor 5.WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A,"Optimized zIRLO,"(Westinghouse July Proprietary), 2006.

Methodology for:

TS3.12.B.1 andTS3.12.B.2 HeatFlux HotChannel Factor 6.VEP-NE-2-A, Rev. 0,"Statistical DNBR Evaluation Methodology," June 1987.

Methodology for:

TS3.12.B.1 andTS3.12.B.2 -

Nuclear Enthalpy Rise HotChannel Factor

7. DOM-NAF-2-P-A, Revision 0,Minor Revision 3, "Reactor CoreThermal-HydraulicsUsing the VIPRE-DComputer including Code," Appendix B, "Qualification ofthe Westinghouse WRB-1 CHFCorrelation inthe Dominion VIPRE-D Computer Code," and Appendix D,"Qualification ofthe ABB-NVandWLOP CHF Correlations in the D ominionVIPRE-D Computer Code," September 2014.

Methodology for:

TS3.12.B.1 andTS3.12.B.2 -

Nuclear Enthalpy RiseHotChannel Factor 8.WCAP-8745-P-A, "DesignBases for Thermal Overpower Delta-T and Thermal Overtemperature Delta-T Function,"

Trip September 1986.

Methodology for:

TS2.3.A.2.d -

Overtemperature AT TS2.3.A.2.e -

Overpower AT Page2 of7

Serial No.21-181 DocketNo.50-281 COLRS2C30R1 3.0m Thecycle-specific parameter limits forthespecifications listed inSection inthe 1.0arepresented following subsections. Theselimits havebeendeveloped using theNRC-approved methodologies specified inTechnical Specification 6.2.C andrepeated inSection 2.0.

3.1m(TS 2.1)

TheReactor Core SafetyLimits are presented in Figure A1.

3.2M(TS 2.3.A.2.d)

+h" AT<;ATo [K1K21+e2s (T -T') +K3(P -

P')f(zil))

Where:

ATismeasured RCSAT,OF.

AToisthe indicated ATatRATEDPOWER,OF.

sisthe Laplace transform operator, sect T isthe measured RCSaverage temperature(Tavg),OF.

T'isthe nominal Tavg atRATEDPOWER,5 573.00F.

P isthe measured pressurizer psig.

pressure, P'isthe nominal RCSoperating 2 2235 pressure psig.

K15 1.1425 K22 0.01059 /0F K32 0.000765

/psig t12 29.7 seconds t25 4.4 seconds f(AI) 2 0.0268 (-24 -

(qtqb)),

when(qtqb)

< 24.0% RATEDPOWER 0, when24.0% RATEDPOWER 5 (qtqb) 5 +8.0%RATEDPOWER 0.0188 ((qtq3)8.0),

when(qtqb)

> +8.0% RATEDPOWER Where qtand qbare percent RATEDPOWER intheupper andlowerhalves ofthecore, respectively, andqt+ qbisthe THERMALPOWER total inpercentRATEDPOWER.

Page3 of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 3.3Qy.eej;gpwweerAT.(TS 2.3.A.2.e) h' T AT <;ATo [K4Ks1+c3 S

Ke(T -T')f(AI))

Where:

ATismeasured RCS AT,OF.

AToisthe indicated AT atRATEDPOWER, OF.

sisthe Laplace transform operator, sec4 T isthe measured RCS average temperature (Tavg), OF.

T'isthe nominal Tavg atRATED POWER, 5 573.00F.

K45 1.0965 K52 0.0198 /oFfor increasing Tavg Ka2 0.001074 /oFfor T >T' 2 0/0F fordecreasing Tavg 2 0for T 5 T' t32 9.0 seconds f(AI)= asdefined above for OTAT 3.4M (TS 3.1.E)

TheModerator Temperature Coefficient (MTC) limitsare:

+6.0 pcm/0F atless than 50percent ofRATEDPOWER,and

+6.0 pcm/0F at50percent ofRATEDPOWERandlinearly decreasing to0pcm/0F at RATED POWER 3.5Control BankInsertion Limits (TS 3.12.A.1, TS3.12.A.2, TS3.12.A.3,andTS3.12.C.3.b.1(b))

3.5.1Thecontrol rodbanks shall belimited inphysical insertion asshown A2.

inFigure 3.5.2Therodinsertion limit for the A andB control banks isthefullywithdrawnposition asshown on Figure A2.

3.5.3Therodinsertion limit for the A andB shutdown isthe banks fullywithdrawnposition asshown on Figure A2.

3.6h (TS 3.12.A.1.a, TS3.12.A.2.a, TS3.12.A.3.c TS3.12.G) and Shutdown margin (SDM) shall be2 1.77 %Ak/k.

Page4 of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 3.7M(TS 3.12.B.1 andTS3.12.B.2) 3.7.1 Heat Flux HotChannelFactor FQ(z)

CFQ FQ(z) 5 P K(z)for P > 0.5 CFQ FQ(z) 5 0.5K(z)for P 5 0.5 THERMALPOWER where: P=

RATEDPOWER CFQ = 2.5

= 1.0 K(z) for all coreheights,z 3.7.2 Nuclear Enthalpy Rise HotChannel Factor -

FAH(N)  !

FAH(N) 5 CFDH* (1 +PFDH(1 P))

THERMAL POWER where: P -

RATEDPOWER CFDH=1.635  !

PFDH=0.3 l l

3.8h(TS andTSTable 3.12.F 4.1-2A) j r

from NucleateBoiling shallbemaintained their within l Departure (DNB) Parameters limits during POWER OPERATION: j

  • Pressurizer 2 2205 Pressure psig

= Reactor CoolantSystemTotal Flow Rate 2 273,000gpm(Tech Spec Limit) and2 274,000 gpm(COLR Limit)

Page5 of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION , 100% FLOW o

$ 650

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630 B 198[>psig 16 - ------ -- ---L----- --- ---

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0 10 20 30 40 50 60 70 80 90 100 110 120 Percent ofRated Power Page6 of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 Figure A-2 Surry 2 Cycle 30 RodGroup Insertion Limits Maxw/dposition = 227steps 230

[

y--- - -- -

220 l---- ----- ---- -=----

0.475, 227 . , .

210 '---'~~ - -~--- --- -- --- ----'--' - --- --

200 ;--- ---- -- ~--- --- --- --- -- ---- ---

190 --- ----- - -- ---- - ---- ...--- ---

180 -- - ----- t-- -

--L---

170

[----- -- ' - ---- ---- -' -

160 - - -- -

150 - ----- ---,- ----- L-----

1 - ' - -

2 120 i-------

110 ---- --- ---- ----

D Bank .

j 100 - --- -

90 ----

80 -- ---- ---- -- ---- --

70 -- '---'=-- --^^-- "- -- -'-=--- ----=-'-' ----

60 --- --- - ------ ---- - ----- --- -

50 j----- -- ---- --- --- ------- ----

j 10 - -

0 - --- ---- --

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Fraction ofRated Thermal Power Page 7 of7

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