ML21140A392
| ML21140A392 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/18/2021 |
| From: | Standley B Dominion Energy Services, Dominion Energy Virginia, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 21-182 | |
| Download: ML21140A392 (10) | |
Text
Dominion Energy
- Services, Inc.
g 5000 Dominion Boulevard, GlenAllen, VA23060 DominionEnerg ycom b Q@
I May18,2021 United States Nuclear Regulatory Commission Serial No.: 21-182 I
Attention:
Document Control Desk NRA/GDM: RO Washington, D.C.20555 Docket No.:50-280 License No.:DPR-32 t
SURRYPOWERSTATION UNIT 1 COREOPERATING LIMITS REPORT f
SURRY1CYCLE31PATTERN RNA REVISION 0
,I Pursuant toSurry Technical Specification (TS) 6.2.C,attached isacopyoftheCore Operating Limits Report (COLR) forSurry Power Station Unit 1,Cycle 31,Pattern
- RNA, Revision 0.
lfyou haveanyquestions or require additional information, pleasecontact Mr.GaryMiller at(804) 273-2771.
j f
Sincerely, B.E.Standley, Director j
Nuclear Regulatory Affairs I
Dominion Energy
- Services, inc.
for Virginia Electric andPowerCompany gaI I
Attachment:
i CoreOperating Limits
- Report, Surry Unit1Cycle 31,Pattern RNA,Revision 0
jI Commitment Summary:
There arenonewcommitments contained inthis letter.
Iii I
Is I
Serial No.21-182 Docket No.50-280 COLRS1C31 cc:
U.S. Nuclear Regulatory Commission Region II Marquis OneTower 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, Maryland 20852-2738 Mr.G.EdwardMiller NRCSenior Project Manager
- North Anna U.S.Nuclear Regulatory Commission OneWhite Flint North MailStop09E-3 11555Rockville Pike Rockville, Maryland 20852-2738 NRCSenior Resident Inspector Surry PowerStation I
II II i
Serial No.21-182 Docket No.50-280 Attachment COREOPERATING LIMITS REPORT Surry Unit1Cycle31 Pattern RNA Revision 0
Virginia Electric andPowerCompany (Dominion Energy Virginia)
Serial No.21-182 Docket No.50-280 COLRS1C31 LO IlyTTAQD[LCTLQM This Core Operating Limits Report (COLR) forSurryUnit!1l Cycle j31j hasbeenprepared inaccordance with the requirements ofSurry Technical Specification6.2.C.
TheTechnical Specifications affected bythis report are:
- Safety
- Overpower AT TS3.1.E
- Moderator Temperature Coefficient TS3.12.A.1, TS3.12.A.2, TS3.12.A.3 andTS3.12.C.3.b1(b)
- Control BankInsertion Limits TS3.12A.1.a, TS3.12.A.2.a, TS3.12.A.3.c andTS3.12G
- Shutdown Margin TS3.12.B.1 andTS3.12.B.2
- Power Distribution Limits (Heat FluxHotChannel Factor and Nuclear Enthalpy Rise HotChannel Factor)
- DNBParameters TSTable 4.1-2A
- Minimum Frequency for Equipment Tests:Item22
- RCSFlow 2.0RE.FEEENCEJ 1.VEP-FRD-42, Rev.2.2-A, "Reload Nuclear Design Methodology,"
October 2017.
Methodology for:
- 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.A1.a, TS3.12.A.2.a, TS3.12.A.3.c andTS3.12.G
- Shutdown Margin TS3.12.B.1 andTS3.12.B.2
- HeatFlux HotChannel Factor andNuclear Enthalpy Rise Hot Channel Factor TS3.12.F
- DNBParameters i
TSTable 4.1-2A
- Minimum Frequency forEquipment Tests:
Item22
- RCSFlow 2.WCAP-16009-P-A, "Realistic Large BreakLOCAEvaluation Methodology Using theAutomated 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 byANP-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 Page1of7
Serial No.21-182 Docket No.50-280 COLRS1C31 4.WCAP-12610-P-A, "VANTAGE+ FuelAssembly Report,"
(Westinghouse Proprietary),
April 1995.
Methodology for:
- HeatFluxHotChannel Factor 5.WCAP-12610-P-Aand 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, Rev.0.3,"Reactor CoreThermal-Hydraulics UsingtheVIPRE-DComputer Code,"
including Appendix B,"Qualification ofthe Westinghouse WRB-1CHFCorrelation inthe Dominion VIPRE-DComputer Code,"
andAppendixD, "Qualification oftheABB-NVandWLOP CHFCorrelations intheDominion VIPRE-D Computer Code,"
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-TTrip Function,"
September 1986.
Methodology for:
TS2.3.A.2.d
- Overtemperature AT TS2.3.A.2.e
- Ove1power AT Page2of7
Serial No.21-182 Docket No.50-280 COLRS1C31 3.0m Thecycle-specific parameter limits forthespecifications listed inSection 1.0arepresented inthe following subsections.
These limits havebeendeveloped using theNRC-approved methodologies specified inTechnicalSpecification 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)
AT5;ATo[K1
- K2 (T -T') +K3(P
- P')
- f(AI))
Where:
ATismeasured RCSAT,0F.
AToistheindicated ATatRATEDPOWER,OF.
sistheLaplace transform
- operator, sect T isthemeasured RCSaverage temperature (Tavg),
OF.
T'isthenominal Tavg atRATEDPOWER,5573.00F.
Pisthemeasured pressurizer
- pressure, psig.
P'isthenominal RCSoperating pressure 22235psig.
K151.1425 K220.01059
/oF 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
- qb)
- 8.0),when(qt
- qb)>+8.0%
RATEDPOWER Where qtandqbarepercent RATEDPOWERintheupper andlower halves ofthecore, respectively, andqt+qbisthetotal THERMALPOWERinpercent RATEDPOWER.
Page3of7
Serial No.21-182 Docket No.50-280 COLRS1C31 3.3M(TS 2.3.A.2.e)
AT<;ATo[K4
- Ks T
- Ke(T
- T')
- f(AI))
Where:
ATismeasured RCSAT,OF AToisthe indicated ATatRATEDPOWER,OF.
sisthe Laplacetransform operator, sect Tisthemeasured RCS average temperature (Tayg),
0F.
T'isthenominal Tavg atRATED POWER, 5573.00F.
K451.0965 K520.0198
/oF for increasing Tavg K620.001074
/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 3.5M(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 andBshutdown banks isthefully withdrawn position asshown on Figure A2.
3.6SjmtdpqanMaggin (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.21-182 Docket No.50-280 COLRS1C31 3.7'PowerDistribution Limits (TS 3.12.B.1 andTS3.12.B.2) 3.7.1HeatFlux 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 THERMAL POWER where:
P =
RATEDPOWER CFQ
= 2.5 K(2)
= 1.0forall coreheights, z
3.7.2Nuclear Enthalpy Rise HotChannel Factor
- FAH(N)
FAH(N) 5 CFDH*(1+PFDH(1
- P))
THERMALPOWER where:
P RATEDPOWER CFDH=1.635 PFDH=0.3 3.8h(TS 3.12.F andTSTable 4.1-2A)
Departure fromNucleate Boiling (DNB)
Parameters shall bemaintained within their limits duringPOWER OPERATION:
a Reactor Coolant System Tayg 5577.0 OF
- Pressurizer Pressure 22205psig
- Reactor Coolant System Total FlowRate2 273,000 gpm(Tech SpecLimit) and2 $74,000lgpm (COLR Limit)
Page5of7
Serial No.21-182 Docket No.50-280 COLRS1C31 Figure A1 REACTOR CORESAFETY LIMITS THREE LOOPOPERATION, 100%FLOW 670
~~~~--
l 660 j-~^
~----~
--~~~~"^
l 650
~~^
-~~~~^'
-~~~~i-640
--)'~~~~~~~~~-
-~~~~~~~
--^-~^
4-~--
630~~~~~~^l~~"-
~~^"-^""-
~~~~~~~~~~^""'
E 620 1 -"--^~~~-'[--
-~~-~~~--~~
~^-"' j 610
! ^'
~~~~~"-~~^
"-1
--i u
I I
I
--,-i 600
~~~~~~~b
"-~~~~^--
--~~--
--~~
~~~~^"
1 590 j
I
^
580 '-b"
=
I I
~~~~~~~""
j
~
570
"----'-~-
~---
--~~~~
~~~~~--
-~~
560'~~"
550 0
10 20 30 40 50 60 70 80 90 100 110 120 PercentofRatedPower Page6of7
Do e COLRS1C31 Figure A-2 Surry11)
Cyclej31j RodGroupinsertion Limits Maxw/dposition
=$29) steps 0.4875, 229 220 i
--j---
)
210 l
C-B nk l
1.0,183
/
180
--j---
j---
~
170 L
160 30 o,151 140 130 f
120
'=--
j 110
~--
-- -'-j"---
90 80 m---i----
70 50
.......~....--
40 gy I
Page7of7