ML21126A314
| ML21126A314 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/06/2021 |
| From: | Mark D. Sartain Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 21-043 | |
| Download: ML21126A314 (19) | |
Text
VIRGINIAELECTRIC ANDPOWERCOMPANY RICHMOND,VIRGINIA23261 May6,2021 10CFR50.90 U.S.NuclearRegulatory Commission Serial No.: 21-043 Attention:
Document Control Desk NRA/ENC: RO Washington, DC20555-0001 Docket Nos.:50-338 50-339 License Nos.:NPF-4 NPF-7 VIRGINIA ELECTRIC ANDPOWER COMPANY NORTHANNAPOWERSTATION UNITS 1AND2 E
REVISEPRIMARYGRADEWATERISOLATION TIMEFROM15MINUTES TO1HOURFOLLOWING REACTOR SHUTDOWN t
Pursuant to10CFR50.90, Virginia Electric and Power Company (Dominion Energy Virginia) requests amendments toNorth AnnaPower Station (NAPS)
Units 1and2 Facility Operating License Numbers NPF-4andNPF-7, respectively, intheformofa change totheTechnical Specifications (TS).
Theproposed change revises theTS 3.1.8.A.2 Completion Timetoisolate Primary Grade(PG) water from theReactorCoolant System(RCS) within 15minutes after entering Mode3,4,or5.Specifically, theproposed changewouldadda newrequirement toisolate PGwaterfrom the RCS followinga reactor shutdown fromMode2within 1hourwhile continuing torequire isolation ofPG within 15minutes after aplanned dilution ormakeupactivity while thereactor isinMode 3,4,or5.Additionally, aneditorial change ismadetoTS5.6.5, Core Operating Limits Report (COLR),
toaccurately reflect Amendments 287/270.
A description andassessment oftheproposed changes areprovided inAttachment 1.
Attachment 2provides theexisting TSpagesmarked-up toshowtheproposed changes.
3 Attachment 3 provides revised (clean)
TS'pagesshowing theproposed changes.
Attachment 4 provides existing TS Basespagesmarked-up toshowtheproposed changes.
Attachment 4isprovided forinformation only.
Final TSBaseschanges will be processed inaccordance with theTS5.5.13, "Bases Control Program,"
atthetimethe amendment isissued.
Dominion Energy Virginia hasevaluated theproposed amendment andhasdetermined itdoesnotinvolve asignificant hazards consideration asdefined in10CFR50.92.
The basis forthis determination isincluded inAttachment 1.Dominion Energy Virginia has alsodetermined operation withtheproposed changewill notresult ina significant I
increase intheamountofeffluents thatmaybereleased offsite orasignificant increase inindividual orcumulative occupational radiation exposure.
Therefore, theproposed t
amendment iseligible forcategorical exclusion fromanenvironmental assessment asset forth in10CFR51.22(c)(9).
Pursuant to10CFR51.22(b),
noenvironmental impact i
Serial No.:
21-043 Docket Nos.:
50-338/339 Page2of3 statement orenvironmental assessment isneeded inconnection with theapproval ofthe proposed change.
Theproposed license amendment hasbeenreviewed andapproved bytheNAPSFacility Safety Review Committee.
Dominion EnergyVirginia requests approval oftheproposed change byMay1,2022with a90-day implementation period.
Should youhaveanyquestions orrequireadditional information, please contact Ms.Erica Combsat(804) 273-3386.
Respectfully, MarkD.Sartain VicePresident
- Nuclear Engineering andFleetSupport COMMONWEALTH OFVIRGINIA
))
COUNTYOFHENRICO
)
Theforegoing document wasacknowledged before me,inandfortheCounty andCommonwealth aforesaid, today byMr.MarkD.Sartain, whoisVicePresident
- Nuclear Engineering andFleet
- Support, ofVirginia Electric andPowerCompany.Hehasaffirmed before methat heisdulyauthorized toexecute andfile theforegoing document inbehalf ofthat
- company, andthat thestatementsin the document are true tothebest ofhisknowledge andbelief.
Acknowledged before methisdbdayof
, 2021.
MyCommission Expires:
Nota blic Commitments contained inthis letter:
None CRAIGDSLY Notary Public Commonwealth ofVirginia Attachments:
Reg.#7518653 MyCommission Expires December 31,201.3 1, Discussion ofChange 2.Marked-up Technical Specifications Pages 3.Proposed Technical Specifications Pages 4.Technical Specifications BasesMark-up (For Information Only)
Serial No.:
21-043 Docket Nos.:
50-338/339 Page3of3 cc:
U.S.NuclearRegulatory Commission
- Region II Marquis OneTower 245 Peachtree Center
- Avenue, NE,Suite 1200
- Atlanta, Georgia 30303-1257 State Health Commissioner Virginia Department ofHealth JamesMadison Building
- 7th flOOr 109Governor
- Street, Suite 730
- Richmond, Virginia23219 Mr.G.Edward Miller NRCSenior Project Manager North AnnaPowerStation U.S.Nuclear Regulatory Commission OneWhiteFlint North MailStop09E-3 11555Rockville Pike Rockville, Maryland 20852-2738 Mr.VaughnThomas NRCProject Manager
- Surry PowerStation U.S.Nuclear Regulatory Commission OneWhite Flint North MailStop04F-12 11555Rockville Pike Rockville, Maryland 20852-2738 NRCSenior Resident Inspector North AnnaPowerStation Mr.MarcusHarris OldDominion Electric Cooperative Innsbrook Corporate
- Center, Suite 300 4201Dominion Boulevard GlenAllen, Virginia 23060
Serial No.:
21-043 Docket Nos.:
50-338/339 i
DISCUSSION OFCHANGE i
i il II Virginia Electric andPowerCompany (Dominion Energy Virginia)
NorthAnnaPowerStation Units 1and2
Serial No.:
21-043 Docket Nos.:
50-338/339 Attachment 1
Page1of9 DISCU.SSION OFCHANGE 1.0
SUMMARY
DESCRIPTION
=
Pursuant to10 CFR 50.90,Virginia Electric andPowerCompany(Dominion Energy Virginia) requests amendments toNorth AnnaPowerStation (NAPS)
Units 1and2 Facility Operating License Numbers NPF-4andNPF-7,respectively, intheformof achange totheTechnical Specifications (TS).
Theproposed changerevises the TS3.1.8.A.2 Completion Time toisolatePrimary Grade(PG) waterfromtheReactor Coolant System (RCS) within 15minutes after entering Mode3,4,or5.
Specifically, theproposed change would addanewrequirement toisolate PGwater fromtheRCSfollowing a reactor shutdown fromMode2 within 1 hourwhile continuing torequire isolation ofPG within 15minutes after a planned dilution or makeupactivity while thereactor isinMode 3,4,or5.
Additionally, aneditorial change ismadetoTS 5.6.5, CoreOperating Limits Report (COLR),
toaccurately reflect Amendments 287/270.
Theproposed TSchangehasbeenreviewed, andit has beendeterminedthat no significant hazards consideration exists asdefined in10 CFR 50.92.Inaddition, it hasbeendetermined thatthechange qualifies for categorical exclusion froman environmental assessment assetforth in10CFR51.22(c)(9).
Therefore, no environmental impact statement orenvironmental assessment isneededin connection with theapproval oftheproposed TSchange.
I 2.0DETAILEDDESCRIPTION II I
2.1Background
iI NAPSandSurry PowerStation (SPS) aresimilar vintage 3-loop Westinghouse Pressurized WaterReactor (PWR) plants.
SPSUnit2 hada boron dilution I
eventonMay28,2011thatremoved a substantial portion oftherequired Shutdown Margin(SDM) whileinIntermediate Shutdown(NAPS Mode4 equivalent).
TheSPSeventdidnotchallenge theTS shutdown margin requirements;
- however, itrevealed a weakness inprotection against boron j
dilution events.
An extentof condition evaluation revealed NAPS's I
susceptibility tothesametypeofweakness.
Itwasdetermined that theSource RangeDetector (SRD) channel indication forSurryandNorthAnna inadequately approximated thetheoretical subcritical coremultiplication factor (1/M) performance during reactivity insertion events.
Thelower-than-expected response tochanges incorereactivity werecreated,
- inpart, bytheremoval of Secondary Source Assemblies (SSA).
I i
Serial No.:21-043 Docket Nos.:
50-338/339 Attachment 1
Page2of9 As a corrective
- action, NAPShadSSAsre-inserted, beginning fromUnit1 Cycle 25(spring2015) andUnit 2Cycle 24(fall 2014).
Thisaction tore-insert theSSAs atNAPSimproved thecoupling between changes incorereactivity andSRD indication inthecontrol roomandimproved theoperators' ability to identify,detect, andrespond toreactivity changes that could becaused byan inadvertentdilution event.
2.2M Theproposed changerevises theTS3.1.8.A.2 Completion Timetoisolate PG waterfromtheRCSwithin 15minutesafter entering Mode3,4,or5.
Specifically, theproposedchange wouldaddanewrequirement toisolate PG water fromtheRCSfollowing a reactor shutdownfromMode2within 1hour while continuing torequire isolation ofPGwaterwithin 15minutes after a
dilution ormakeupactivity while the reactor isinMode3,4,or5.
Thefollowing changes areproposed tothe NAPS Units 1and2TS.
i Thecurrent version ofTS3.1.8.A reads:
h Condition A.Oneormorevalves notsecured inclosed position.
Required Action A.1 Suspend positive reactivity additions.
Immediately i
AND e
Required Action A.2
- Secure valves inclosed position.
- 15minutes l
AND Required Action A.3
- Perform SR3.1.1.1.
- 4hours,
Thereviseip version ofTS3.1.8.A.
wouldread:
Condition A.Oneormorevalves notsecured inclosed position.
f Required Action A.1 Suspend positive reactivity additions.
Immediately AND '
Required Action A.2
- Secure valves inclosed position.
- 15minutes ORWithin 1hourafter Mode3entry fromMode2.
Serial No.:
21-043 Docket Nos.:
50-338/339 Attachment 1
Page3of9 AND Required ActionA.3
- Perform SR3.1.1.1.
- 4hours Additionally, aneditorial change ismadetoTS5.6.5, CoreOperating Limits Report (COLR),
toaccurately reflect Amendments 287/270.
Thespecific change removes revision barsunrelated toAmendments 287/270.
3.0TECHNICALEVALUAT.ION Theproposed change wouldallow forPGwaterisolation within 1hourafter entry into Mode3following reactor shutdown whenthere isnoplanned dilution ormakeup activity occurring.
Thiswouldbeachange fromthecurrent Completion Timeof15 minutes.
The1-hour Completion Time following reactor shutdown isrequested to continue toensure prompt implementation ofPGwaterisolation without placing an undueburden ontheoperating staff during plant shutdowns.
Additionally, following areactor
- shutdown, operators arehighly focused onplantreactivity conditions and arenowbetter equipped (since the re-insertionof SSAs atNAPSUnits 1and2in response tothelessons learned fromtheSurry Boron Dilution eventinMay2011) tobeable toidentify,
- detect, andrespond toreactivitychanges that could becaused byaninadvertent dilution event.
Asaresult, operators,inthe event ofaninadvertent
- dilution, areexpected tocontinue tobeabletotake action prior toanysignificant reactivity changes.
Additionally, theproposed 1-hour Completion Timerequirementis consistent with theprovisions ofNUREG1431,Volume1,Revision 4,"Standard Technical Specifications, Westinghouse Plants,"
(Reference 1)Section 3.3.9A, "Boron Dilution Protection System(BDPS)
(Without Setpoint Control Program)"
Required Action B.2.2.1 IntheStandard Technical Specifications, theBDPSistheprimarymeans ofprotection against borondilution events inshutdown operating modes.
Inthe Standard Technical Specifications, ifbothtrains ofBDPSareinoperable, onehour isallowed toeither restore atrain ofBDPStoservice or"close unborated water source isolation valves."
Additionally, this proposed 1-hou'r Completion Timeand basis isconsistent withtheCompletion Timeapproved byletter dated May10,2017, "Surry PdwerStation Units 1and2,Issuance ofAmendments, RE:Changes to ExpandPrimary GradeWaterLockout Requirements inTechnical Specification j
3.2.E(CAC Nos.MF7716andMF7717)"
(Accession NumberML17039A513).
j i
1
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Page4of9
4.0REGULATORY EVALUATION
4.1A Section 182a oftheAtomic Energy Actrequires applicants fornuclear power plant operating licensestoinclude TSaspart ofthelicense.
TheTSensure theoperational capability ofstructures,
- systems, andcomponents that are required toprotect thehealth andsafety ofthepublic.
a 10CFR50.90 requires NRCapproval foranymodification to,addition to,or deletion fromtheplant TS. Therefore, this activity requires NRCapproval prior tomaking theproposed plant-specific changes.
- 10CFR50.36 requires that the TS includeitems inthefollowing specific categories:
(1) safety limits,limiting safetysystems
- settings, andlimiting control settings; (2) limiting conditions for operation (LCOs);
(3) surveillance requirements per10 CFR 50.36(c)(3);
(4)design features; and(5) administrative controls.
This amendment isrelated tothesecondcategory abovesince achangetotheLCO3.1.8is proposed.
4.2Precedents Theproposed 1 hourCompletion TimeforPrimary Grade waterisolation following reactor shutdown wasapproved bytheNRCfor Surry PowerStation f
byletter dated May10,2017,"Surry PowerStation Units1 and 2,issuance of Amendments, RE:ChangestoExpandPrimary Grade Water Lockout Requirements inTechnical Specification 3.2.E(CACNos.MF7716 and i
MF7717),"
(Accession NumberML17039A513).
4.3M i
t Theproposed change revises theTS3.1.8.A.2 Completion Timetoisolate PG waterfromtheRCSwithin 15
- minutes after
' entering Mode3,4,or5.
Specifically, theproposed change wouldaddareq;uirement toisolate PGwater fromtheRCSfollowing a reactor shutdown fromMode2within 1hourwhile continuing torequire isolation ofPGwithin 15minutes after aplanned dilution j
ormakeupactivity while thereactor isinMode3,4,or5.
E Asrequired by10CFR50.91 (a)(1),
Dominion Energy Virginia hasperformed v
anevaluation todetermine whether ornotasignificant hazards consideration isinvolved with theproposed amendment byfocusing onthethree standards setforth in10CFR50.92, "Issuance ofamendment,"
Part50.92(c),
andhas I
Serial No.:
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Page5of9 determined that theproposed change doesnotinvolve asignificant hazards consideration, asdiscussed below:
1.Does theproposed amendment involve a significant increase inthe probability orconsequences ofanaccident previously evaluated?
Response
No Therearenodesign changes associated withtheproposed change.
AII
- design, material, and construction standards that wereapplicable prior to this amendment request will continuetobeapplicable.
Theproposed change will not affect accidentinitiators orprecursors oralter thedesign, conditions, orconfiguration ofthefacility.
Theproposed change doesnotalter thewaythe plant isoperated andmaintained, withrespect to accident initiators orprecursors.
Although theproposed changeisnotdetermined toalter thewaytheplant isoperated withrespect toaccident initiators orprecursors, theproposed change doespotentially alter thewaythe plant is operated asitwouldallow forPGwater isolation within 1hourafter entry into Mode 3following reactor shutdown fromMode2whenthere isnoplanned dilution ormakeupactivity occurring.
This wouldbeanincrease fromthe current Completion Timeof 15minutes.
The1-hour Completion Timefollowing reactor shutdown is requested tocontinue toensureprompt implementation ofPG water isolation without placing anundueburden ontheoperating staff andis consistent withprior NRCapproved Completion Timesfor PG water isolation following reactor shutdown.
Additionally, following areactor
- shutdown, operators arehighly focused on plant reactivity conditions andarenowbetter equipped (since there-insertion ofSSAsatNAPSUnits 1and2inresponse tothelessons learned fromtheSurry BoronDilution eventinMay2011) tobeabletoidentify,
- detect, andrespond toreactivity cha'nges thatcouldbecaused byan inadvertent dilution event.
Asaresult, operators, intheeventofaninadvertent
- dilution, areexpected tocontinue tobeabletotakeaction prior toanysignificant reactivity changes.
I Additionally, aneditorial change ismadetoTS5.6.5, CoreOperating Limits Report (COLR),
toaccurately reflect Arnendments 287/270.
lI t
I s
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50-338/339 Attachment 1
Page6of9 Therefore, itisconcluded that theproposed amendment doesnotinvolve a
significant increase intheprobability orconsequences ofanaccident previously evaluated.
2.Doesthe proposed amendmentcreate thepossibility ofanewordifferent kind ofaccident fromanyaccident previously evaluated?
Response
No There arenoproposed design changesorchanges inthemethods bywhich anysafety-related plant structures,
- systems, orcomponents perform their specified safety functions.
The proposed change will notaffect thenormal methodsofplant operation orchange anyoperating parameters.
No equipmentperformancerequirements willbe affected.
The proposed change will notalter any assumptions inthesafety analyses.
Theproposed change doesnotinvolve a physical modification ofthe plant.
i Nonewaccident scenarios, transient precursors, failure mechanisms, or limiting single failures willbe introducedbecause ofthis proposed change.
Therewill benoadverse effect orchallenges imposed onany safety-related systembecause ofthis proposed change.
iI Additionally, aneditorial change ismadetoTS5.6.5, CoreOperating Limits Report (COLR),
toaccurately reflect Amendments 287/270.
Therefore, itisconcluded that theproposed amendment does not create thepossibility ofa newordifferent kindofaccident fromanypreviously evaluated.
3.Doestheproposed amendment involve asignificant reduction inamargin ofsafety?
gaI
Response
No
[
I Theproposed change wouldallow forPGwaterisolation within 1hourafter entry into Mode3following reactor shutdown fromMode2whenthere isno planned dilution ormakeupactivity occurring.
Thiswouldbeachange from P
thecurrent Completion Timeof15minutes.
The1-hour Completion Time f
following reactor shutdown wouldensureprompt implementation ofPG waterisolation without placing anundueburden ontheoperating staff and iI I
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Page7of9 isconsistent withprior NRCapproved Completion TimesforPGwater isolation following reactor shutdown There willbenoeffect onplant systems necessary toperform protection functions.
Noinstrument setpoints orsystem response times areaffected andnoneof the acceptance criteria foranyaccident analysis will bechanged.
Consequently, the proposed change will havenoimpact ontheradiological consequences ofadesign basisaccident.
Additionally, aneditorialchange ismadetoTS5.6.5, CoreOperating Limits Report (COLR),
toaccurately reflect Amendments 287/270.
Therefore, itisconcluded that the proposed amendment doesnotinvolve a
significant reduction inamargin ofsafety.
i Therefore, Dominion Energy Virginia concludes thattheproposedamendment doesnotinvolve asignificant hazards consideration underthestandards set forth in10CFR50.92(c),
"Issuance ofAmendment,"
and accordingly, afinding of"no significant hazards consideration" isjustified.
4.4Conclusion iI Insummary, inaccordance with10CFR50.90, Dominion Energy Virginia requests NRCreview andapproval ofthechanges toTechnical Specifications 3.1.8 and5.6.5 forNAPSUnits 1and2.
I i
Basedontheabovediscussions, (1) there isreasonable assurance thatthe health andsafety ofthepublic will notbeendangered byoperation inthe proposed manner,(2) suchactivities will beconducted incompliance with the Commission's regulations, and(3) theissuance oftheamendment will notbe inimical tothecommondefense andsecurity ortothehealth andsafety ofthe public.
It 5.0W x
i Theproposed change wouldallow forPGwaterisolation within 1hourafter entry into Mode3following reactor shutdown whenthere isnoplanned dilution ormakeup t
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Page8of9 activity occurring.
Additionally, anadministrative changeofTS 5.6.5, COLR,is included toremove erroneous revision bars.
A review of the anticipated construction andoperational effects oftherequested amendment has determined therequested amendment meetstheeligibility criteria for categoricalexclusion setforth in10CFR51.22(c)(9),
inthat:
(i) There isnosignificant hazards consideration.
As documented in Section 4.3,No Significant Hazards Consideration Determination, ofthis license amendmentrequest, anevaluation was completed todetermine whether ornotasignificant hazards consideration isinvolved byfocusingon the threestandardssetforth in10CFR50.92, "Issuance of Amendment."
The Significant HazardsConsideration determined that(1) the proposed amendment doesnotinvolve asignificant increase intheprobability orconsequences ofanaccident previously evaluated; (2) theproposed amendment doesnotcreate thepossibility ofa newordifferent kindofaccident from any accident previously evaluated; and(3) theproposed amendment doesnot involve asignificantreduction in amargin ofsafety.
Therefore, itis concluded that theproposedamendment doesnotinvolve a significant hazards consideration underthestandards setforth in10CFR50.92(c),
andaccordingly,a finding of"no significant hazards consideration" isjustified.
i (ii)Thereisnosignificant changeinthetypes orsignificant increase inthe amounts ofanyeffluents that maybereleased offsite.
Theproposed change isunrelated toanyaspects ofplant construction or operation that wouldintroduce anychanges toeffluent types (e.g.,effluents containing chemicals orbiocides, sanitary systemeffluents, andother effluents) oraffect anyplant radiological ornon-radiological effluent release quantities.
Theproposed change doesnotadversely impact anyfunctions associated withcontaining, controlling, channeling, monitoring, or processing radioactive ornon-radioactive materials, nordotheydiminish thefunctionality ofanyldesign oroperational features that arecredited with controlling therelease ofeffluents during plant operation.
Thetypes and quantities ofexpected plant effluents arenotchanged.
Noeffluent release pathisassociated withthisamendment.
Neither radioactive nornon-radioactive material effluents areaffected bythis activity.
Furthermore, the proposed change doesnotdiminish thefunctionality ofanydesign or operational features that arecredited with controlling therelease ofeffluents during plant operation.
Therefore, itisconcluded thattheproposed amendment doesnotinvolve a significant changeinthetypesora I
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Page9of9 significant increase intheamounts ofanyeffluents thatmaybereleased offsite.
(iii)There isnosignificantincrease inindividual orcumulative occupational radiation exposure.
Theproposed change doesnotaffect plant radiation zonesdescribed in UFSARSection 11andcontrols under10CFR Part20 preclude a
significantincrease in occupational radiation exposure.
The proposed change does notadverselyimpactradiologically controlled zones.Plant radiation
- zones, radiation controls established tosatisfy 10 CFRPart20requirements andexpected amounts andtypes ofradioactive materials arenotaffected bytheproposed amendment.
Therefore, individual andcumulative radiation exposures arenotsignificantly affected bythis change.
Therefore, the proposed amendmentdoesnotinvolve a
significant increase inindividual or cumulative occupational radiation exposure.
Basedontheabovereview oftheproposed amendment, ithasbeendetermined that anticipated construction andoperational effects of the proposed amendment do notinvolve (i) a significant hazards consideration, (ii) a significant changeinthe typesorsignificant increase intheamounts ofanyeffluents thatmaybereleased
- offsite, or(iii) a significant increase intheindividual orcumulative occupational i
radiation exposure.
Accordingly, theproposed amendment meets theeligibility criteria forcategorical exclusion setforth in10CFR51.22(c)(9).Therefore, pursuant to 10 CFR 51.22(b),
an environmental impact statement or environmental assessment oftheproposed amendment isnotrequired.
,i 6.0References 1.NUREG1431,Volume1,Revision 4,"Standard Technical Specifications, Westinghouse Plants,"
April 2012.
2.Letter fromNRCtoMr.Daniel G.Stoddard, "Surry PowerStation Units
- 1and2, issuance ofAmendments, RE:Changes toExpand Primary GradeWaterLockout Requirements inTechnical Specification 3.2.E(CAC Nos.MF7716andMF7717),"
dated May10,2017(Accession NumberML17039A513).
j I
Serial No.:21-043 Docket Nos.:
50-338/339 MARKED-UP TECHNICAL SPECIFICATIONS PAGES iIi I
I Virginia Electric andPowerCompany (Dominion EnergyVirginia)
NorthAnnaPowerStation Units1and2 Ii
Primary GradeWaterFlowPathIsolation Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Primary Grade WaterFlowPathIsolation V~alves
~
LCO3.1.8 Eachvalve usedtoisolate primary gradewaterflowpaths shallbesecured intheclosed position.
NOTE--
Primary gradewaterflowpathisolation valves maybeopened under administrative control forplanned borondilution or
~
makeup activities.
~
APPLICABILITY:
MODES 3,4,and 5.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE-------
A.1 Suspend positive Immediately Required Action A.3 reactivity additions, mustbecompleted whenever Condition A
AND isentered.
L A.2 Securevalves in 15minutes closed position.
^
OR l
secured inclosed AND N
Oneormorevalves not
,e VVithin 1houraher I position.
Mode 3entryfrom A.3 Perform SR3.1,1.1 4 hourMode 2 I
~
. j n
n SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1
SR 3.1.8.1Verify eachvalve intheaffected flowpath Within 1
thatisolates primary gradewaterflow 15mi'nutes A 1 pathsislocked,
- sealed, orotherwise following a
j secured intheclosed position.
borondilution s
A ormakeup
. AL2 I activity s
jII North AnnaUnits1and2 3.1,8-1 Amendments 231/212
- n. jI n I
. j tf!
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i i
i I
1 j
Virginia Electric andPowerCompany (Dominion EnergyVirginia)
NorthAnnaPowerStation Units 1and2
Primary' GradeWaterFlowPathIsolation Valves 3.1.8
=
3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Primary Grade WaterFlowPathIsolation Valves LCO3.1.8 Eachvalve usedtoisolate primary gradewaterflowpaths shallbesecured intheclosed position.
NOTE Primary grade.
waterflowpathisolation valves maybeopened under administrative control forplanned borondilution or makeup activities.
APPLICABILITY:
MODES 3,4,and 5.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------
A.1 Suspend positive Immediately Required Action A.3 reactivity additions.
mustbecompleted whenever Condition A
AND isentered.
A.2 Securevalves in 15minutes closed position Oneormorevalves not
~~OR secured inclosed position.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after Mode 3 entryfrom Mode 2
MD A.3 Perform SR3.1.1.1. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Il I
I Ill North AnnaUnits1and2 3.1.8-1 Amendments j
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MARKED-UP TECHNICAL SPECIFICATIONS BASES PAGE fi i
E i
i Virginia Electric andPowerCompany (Dominion EnergyVirginia)
NorthAnnaPowerStation Units1and2
Primary GradeWaterFlowPathIsolation Valves 8 3.1.8 BASES LCO flowpaths maybeisolated fromthe,RCS byclosingvalve (continued) 2-CH-140.
Alternatively, 2-CH160, 2-CH156,2-CH-FCV-21148, and2-CH-FCV-2113B maybeusedinlieuof2-CH-140.
TheLCO ismodified bya Notewhichallows theprimary grade water flowpathisolation valves tobeopenedunder administrative control forplanned borondilution ormakeup activities.
APPLICABILITY ThisLCOis applicable inMODES 3',4,and5 toprevent an inadvertentboron dilution.event byensuring closure ofall primary gradewater flowpathisolation valves.
InMODE 6,LCO 3.9.2, "Primary GradeWaterFlowPath
~
Isolation Valves-MODE 6,"
requires allprimary gradewater isolation valves tobe closed toprevent aninadvertent borondilution.
i InMODES 1and2,theborondilution accidentwasanalyzed andwasfoundtobecapable of being mitigated.
I ACTIONS AM I
Preventing inadvertent dilution ofthereactor coolant boron I
concentration isdependent onmaintainingthe primary grade waterflowpathisolation valves
- locked, sealed, or otherwise secured
- closed, exceptasallowed under administrative control bytheLCONote.Becauseof the
' j p.ossibility ofaninadvertent boron
- dilution, Required Action A.1prohibits other positive reactivity additions whilesecuring.the isolation valves ontheprimary grade watersystem.TheCompletion Timeof"Immediately" for suspending positive reactivity additions refleorwithin 1hour importance ofpreventing known positive reacti afterMode3entry i
sothatanyboron.dilution eventcanbe'readil fromMode2 andterminated I
TheRequired Action A.2Completion Timeof15minutesor securing theisolation valves provides sufficient timeto j
closeandsecure theisolation valves ontheprimary grade j
waterflowpathswhile minimizing theprobability ofan E
unintentional dilution.during theCompletion Time.Secur1ng i
thevalves intheclosed position ensures thatthevalves
' i cannotbeinadvertently opened.
I
. (continued)
I I
North AnnaUnits 1and2 B 3.1.8-2 Revision 8
I i
I I