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)
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Text

"o"o7"J""2:'9C"'Jr":n aen,vusoso Dominion DominionEnergy.com Energy" May18,2021 United States Nuclear Regulatory Commission Serial No.: 21-181 Attention:

Document Control Desk NRA/GDM: RO Washington, D.C.20555 Docket No.:50-281 License No.:DPR-37 r

SURRYPOWERSTATION UNIT 2 COREOPERATING LIMITS REPORT SURRY2CYCLE30PATTERNSYK REVISION 1

,l Pursuant toSurry PowerStation (Surry) Units 1 and2 Technical Specification (TS) 6.2.C, attached isacopyoftheCore Operating Limits Report (COLR) forSurry Power Station Unit 2,Cycle 30,Pattern SYK,Revision 1, Therevisionincorporates changes I

associated with therecently approved Surry Units1 and 2TSAmendments 303/303 that incorporate anewsmall break loss ofcoolant accidentmodel into theCOLR.

j Ifyou haveany questions or require additional information, please contact Mr.GaryMiller at(804) 273-2771.

E Sincerely, l

I B.E.Standley, Director Nuclear Regulatory Affairs Dominion Energy

Services, Inc.

for Virginia Electric andPowerCompany g

Attachment:

CoreOperating Limits

Report, SurryUnit2 Cycle30 Pattern
SYK, Revision 1

Commitment Summary:

There arenonewcommitments contained inthis letter.

[t sbb

Serial No.21-181 Docket No.50-281 COLRS2C30R1 Page2of2 cc:U.S.

Nuclear RegulatoryCommission Region II Marquis One Tower 245Peachtree Center Avenue, NE Suite 1200

Atlanta, Georgia 30303-1257 Mr.Vaughn Thomas NRCProject Manager Surry U.S.Nuclear Regulatory Commission OneWhite Flint North MailStop04F-12 11555Rockville Pike Rockville, MD20852-2738 Mr.G.Edward Miller NRCSenior Project Manager

- North Anna U.S.Nuclear Regulatory Commission OneWhiteFlint North Mail Stop09E-3 11555Rockville Pike Rockville, MD20852-2738 NRCSenior Resident inspector Surry PowerStation

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 ThisCore Operating LimitsReport (COLR) forSurry Unit2Cycle 30hasbeenprepared inaccordance with the requirements of Surry TechnicalSpecification 6.2.C.

TheTechnical Specifications affectedbythis report are:

TS2.1

- SafetyLimit, 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 andTS3.12.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 TS3.12.B.1 andTS 3.12.B.2 Power Distribution Limits (Heat FluxHotChannel Factor and Nuclear Enthalpy RiseHotChannelFactor)

TS3.12.F

- DNBParameters TSTable 4.1-2A

- Minimum Frequency for Equipment Tests:

Item22

- RCSFlow 2.0M 1.VEP-FRD-42-A, Revision 2,Minor Revision 2,"Reload Nuclear Design Methodology,"

October 2017.

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, TS3.12.A.2.a, TS3.12.A.3.c andTS3.12.G

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

- HeatFluxHotChannel Factor andNuclear Enthalpy Rise Hot Channel Factor TS3.12.F

- DNBParameters TSTable 4.1-2A

- Minimum Frequency forEquipment Tests:

Item22

- RCSFlow 2.WCAP-16009-P-A, "Realistic LargeBreakLOCAEvaluation Methodology UsingtheAutomated Statistical Treatment ofUncertainty Method (ASTRUM),"

(Westinghouse Proprietary),

January 2005.

Methodology for:

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

- HeatFluxHotChannel Factor 3.EMF-2328(P)(A),

"PWRSmall Break LOCAEvaluation

Model, S-RELAP5 Based,"

assupplemented by ANP-3676P, "Surry Fuel-Vendor Independent Small Break LOCAAnalysis,"

asapproved byNRC Safety Evaluation Report dated March19,2021.

Methodology for:

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

- HeatFluxHotChannel Factor l

Page1of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 4.WCAP-12610-P-A, "VANTAGE+ FuelAssembly Report,"

(Westinghouse Proprietary),

April 1995.

Methodology for:

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

- HeatFluxHotChannel Factor 5.WCAP-12610-P-A and CENPD-404-P-A, Addendum1-A,"Optimized zIRLO,"(Westinghouse Proprietary),

July 2006.

Methodology for:

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

- HeatFluxHotChannel Factor 6.VEP-NE-2-A, Rev.0,"Statistical DNBR Evaluation Methodology,"June1987.

Methodology for:

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

- Nuclear Enthalpy RiseHotChannel Factor 7.DOM-NAF-2-P-A, Revision 0,Minor Revision 3, "Reactor CoreThermal-HydraulicsUsingthe VIPRE-DComputer Code,"including Appendix B,

"Qualification oftheWestinghouse WRB-1 CHFCorrelation intheDominion VIPRE-D Computer Code,"

andAppendix D,"Qualification ofthe ABB-NVandWLOPCHFCorrelations intheDominionVIPRE-D ComputerCode,"

September 2014.

Methodology for:

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

- Nuclear Enthalpy RiseHotChannel Factor 8.WCAP-8745-P-A, "Design Bases forThermal Overpower Delta-T and Thermal Overtemperature Delta-T Trip Function,"

September 1986.

Methodology for:

TS2.3.A.2.d

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

- Overpower AT Page2of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 3.0m Thecycle-specific parameter limits forthespecifications listed inSection 1.0arepresented inthe following subsections.

Theselimits havebeendeveloped usingtheNRC-approved methodologies specified inTechnical Specification 6.2.C andrepeated inSection 2.0.

3.1m(TS 2.1)

TheReactor CoreSafety Limits are presented inFigure A1.

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

AT<;ATo[K1

- K2 +h" (T -T')

+K3(P

- P')

- f(zil))

1+e2s Where:

ATismeasured RCSAT,OF.

AToistheindicated ATatRATEDPOWER,OF.

sistheLaplace transform

operator, sect Tisthemeasured RCSaverage temperature (Tavg),

OF.

T'isthenominal Tavg atRATEDPOWER,5573.00F.

Pisthemeasured pressurizer

pressure, psig.

P'isthenominal RCSoperating pressure 22235psig.

K151.1425 K220.01059

/0F K320.000765

/psig t1229.7seconds t254.4seconds f(AI) 2 0.0268

(-24

- (qt

- qb)),

when(qt

- qb)< 24.0%RATEDPOWER 0, when24.0%RATEDPOWER5(qt

- qb)5+8.0%RATEDPOWER 0.0188

((qt

- q3)

- 8.0),when(qt

- qb)>+8.0%

RATEDPOWER Whereqtandqbarepercent RATEDPOWERintheupper andlower halves ofthecore, respectively, andqt+qbisthetotal THERMALPOWERinpercent RATEDPOWER.

Page3of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 3.3Qy.eej;gpwweerAT.(TS 2.3.A.2.e) h' AT<;ATo[K4

- Ks T

- Ke(T

-T')

- f(AI))

1+c3 S

Where:

ATismeasured RCS AT,OF.

AToisthe indicated ATatRATEDPOWER,OF.

sistheLaplace transform operator, sec4 Tisthemeasured RCS average temperature (Tavg),

OF.

T'isthenominal Tavg atRATED

POWER, 5573.00F.

K451.0965 K520.0198

/oFfor increasing Tavg Ka20.001074

/oFforT>T' 20/0Ffor decreasing Tavg 20forT5T' t329.0seconds f(AI)

= asdefined above forOTAT 3.4M (TS3.1.E)

TheModerator Temperature Coefficient (MTC) limits are:

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

+6.0pcm/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 asshowninFigure A2.

3.5.2Therodinsertion limit fortheA andB control banks isthefully withdrawn position asshown on Figure A2.

3.5.3Therodinsertion limit fortheA andB shutdown banksisthefully withdrawn position asshownon Figure A2.

3.6h (TS 3.12.A.1.a, TS3.12.A.2.a, TS3.12.A.3.c andTS3.12.G)

Shutdown margin (SDM) shall be21.77

%Ak/k.

Page4of7

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 K(z)for P>0.5 P

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

P =

RATEDPOWER CFQ

= 2.5 K(z)

= 1.0forall core

heights, z

3.7.2Nuclear 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 3.8h(TS 3.12.F andTSTable 4.1-2A) r Departure fromNucleate Boiling (DNB)

Parameters shall bemaintained within their limits during POWER OPERATION:

  • Pressurizer Pressure 22205psig

= Reactor Coolant System Total FlowRate2 273,000 gpm(Tech SpecLimit) and2 274,000 gpm(COLR Limit)

Page5of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 Figure A-1 REACTORCORESAFETY LIMITS THREE LOOPOPERATION

, 100%FLOW o

650

^

-~~~-

~~~~

-"""~~~

~

^--

---~---

640

---""~

^~^-

'-""~~~~~

"--~~^^'i^""

' -"^~~~

-~~~~~-

j

~ ~^~~"----~~^"-

---~~~""-

630

~~-"'

~~--~~~~~~~~""~^

~~~"-

~-~~~~~~~~"-

B 198[>psig 16

---L-----

186Jsig 600

"--"-~^

"~~~~~~T--

"--^-

~~~^

F I

I 590

"--~"-"~+--"--"~~~-

j

'"T-j

-~~~^

'~~~--~^-'-"~~~

~

^

5 0

l

^

l l

I 560

'~-")------

~~~--"

~--^""

l 550 4-""---

---~~~~

0 10 20 30 40 50 60 70 80 90 100 110 120 Percent ofRated Power Page6of7

Serial No.21-181 Docket No.50-281 COLRS2C30R1 Figure A-2 Surry 2Cycle 30 RodGroupInsertion Limits Maxw/dposition

= 227steps 230[

y---

220l----

-=----

0.475, 227 210 '---'~~

-~---

200 ;---

~---

190 180 t--

170[-----

--L---

160 150 L-----

1 2 120 i-------

110 DBank 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 Page7of7

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