ML21126A314

Proposed License Amendment Request - Revise Primary Grade Water Isolation Time from 15 Minutes to 1 Hour Following Reactor Shutdown

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 ANDPOWER COMPANY RICHMOND, 23261 VIRGINIA May6,2021 10CFR50.90 U.S.NuclearRegulatory Commission Serial No.: 21-043 l Attention:

Document Washington,DC Control Desk 20555-0001 NRA/ENC: RO Docket Nos.:50-338 l

50-339 License Nos.: NPF-4 NPF-7 VIRGINIA ELECTRIC ANDPOWER COMPANY j NORTH ANNAPOWER STATION UNITS 1AND2 E REVISE PRIMARY GRADE WATERISOLATION TIMEFROM15MINUTES j TO1 HOURFOLLOWING REACTOR SHUTDOWN l t

Pursuantto10CFR50.90, VirginiaElectricand Power Company (Dominion Energy Virginia) requests amendments toNorth AnnaPower Station (NAPS) Units 1 and2 j Facility Operating License Numbers NPF-4andNPF-7, respectively, intheform ofa TS j

changetotheTechnical Specifications (TS). The proposed change revises the 3.1.8.A.2 Completion Time toisolatePrimary Grade (PG) water from the Reactor Coolant System(RCS) within15 minutes afterenteringMode 3, 4,or 5. Specifically, the p roposed changewould reactor adda newrequirement shutdown from Mode2within toisolate 1 hourwhile PGwater continuing from the RCS followinga torequire isolation ofPG j

15minutes within after a planned dilutionormakeup activitywhile thereactor isinMode l 3,4,or5.Additionally, aneditorialchange ismadetoTS5.6.5, Core Operating Limits (COLR),

Report toaccurately reflectAmendments 287/270.

A description andassessment oftheproposed changes areprovided inAttachment 1. provides the TSpages existing marked-up toshowtheproposed changes. 3 provides revised (clean) TS' pages s howing the proposed changes.  ; provides existing TS Basespages marked-up toshowtheproposed  !

Attachment changes. 4 isprovided forinformationonly. Final TSBases changes willbe l processedinaccordance with theTS 5.5.13,"Bases Control Program," atthetime the amendment isissued.

DominionEnergy Virginia hasevaluated theproposed amendment andhasdetermined it doesnotinvolve asignificant hazards considerationasdefined in10CFR50.92. The  ;

basis also forthisdetermination determined operation isincluded with inAttachment theproposed change 1.Dominion will Energy notresult Virginia has ina significant I l

increase inthe amount ofeffluentsthat maybereleased offsite ora significant increase inindividual orcumulative occupational radiation exposure. Therefore, theproposed t amendment iseligibleforcategorical exclusionfrom anenvironmental assessment asset ,

in10CFR51.22(c)(9).

forth Pursuant to10CFR51.22(b), noenvironmental impact l

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Serial No.: 21-043 Docket Nos.: 50-338/339 Page2 of3 statement orenvironmental assessment isneeded inconnection with the approval ofthe proposed change.

Theproposed license amendment has beenreviewed andapproved bytheNAPSFacility Safety Review Committee.

Dominion EnergyVirginia requests approval ofthe proposed change byMay1,2022 with a 90-day implementation period.

Should youhaveanyquestions orrequire additionalinformation, please contact Ms.Erica Combsat(804) 273-3386.

Respectfully, Mark D.Sartain Vice President -

NuclearEngineering andFleet Support COMMONWEALTH OFVIRGINIA )

)

COUNTY OFHENRICO )

Theforegoing document wasacknowledged before me,inandfor theCounty andCommonwealth aforesaid, today byMr.MarkD.Sartain, whoisVicePresident Nuclear Engineering andFleet Support, ofVirginia Electric andPower Company. Hehasaffirmedbeforemethatheisdulyauthorized toexecute andfile theforegoing documentinbehalf ofthat company, andthatthestatements in the document are true tothebest ofhis knowledgeandbelief.

Acknowledged methis before dbdayof , 2021.

MyCommission Expires: .

Nota blic Commitments contained inthis letter:

None CRAIGD SLY Notary Public Commonwealth ofVirginia Attachments: Reg. # 7518653 1, Discussion ofChange MyCommissionExpires December 201.3 31, 2.Marked-up Technical Specifications Pages 3.Proposed Technical Specifications Pages 4.Technical Specifications Bases Mark-up(For InformationOnly)

Serial No.:

21-043 Docket 50-338/339 Nos.:

Page3 of3 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 Anna Station Power U.S.Nuclear Regulatory Commission OneWhite FlintNorth Mail Stop 09E-3 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. Vaughn Thomas NRCProject ManagerSurry-Power Station U.S.Nuclear Regulatory Commission OneWhite FlintNorth Mail Stop 04F-12 11555 Rockville Pike Rockville, Maryland 20852-2738 NRCSenior Resident Inspector North AnnaPower Station Mr.Marcus Harris OldDominion Electric Cooperative Innsbrook Corporate Center, Suite 300 4201Dominion Boulevard Glen Allen, Virginia 23060

Serial No.: 21-043 Docket Nos.:

50-338/339 Attachment 1 i

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i DISCUSSION OFCHANGE l

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I Virginia andPowerCompany Electric (DominionEnergy Virginia)

AnnaPowerStation North Units 1and2

Serial No.: 21-043 Docket Nos.: 50-338/339 Attachment 1 Page1of9 DISCU.SSION OFCHANGE 1.0

SUMMARY

DESCRIPTION

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Pursuant to10 CFR 50.90,Virginia ElectricandPower Company (Dominion Energy Virginia) requests amendments toNorth AnnaPower Station (NAPS) and2 Units 1 Facility Operating License Numbers NPF-4 and NPF-7, respectively, inthe formof a change totheTechnical Specifications (TS). The proposed change revisesthe TS3.1.8.A.2 Completion Time toisolate Primary Grade (PG) water from the Reactor 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 j continuing makeup torequire activitywhile isolation thereactor ofPG within 15minutes isinMode 3,4,or5.

after a planned dilution or l Additionally, aneditorial change ismadetoTS 5.6.5, Core Operating Limits Report (COLR), toaccurately reflect Amendments 287/270.

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Theproposed TS change hasbeen reviewed, andit has beendetermined that no l significant hazards consideration existsasdefined in10 CFR 50.92.Inaddition, it l hasbeendetermined environmental that assessment thechange as setforth qualifies for categorical exclusion in10 CFR 51.22(c)(9). Therefore, no froman l l

environmental impact statement or environmental assessment isneededin l connection with theapproval ofthe proposed TSchange. l I

I 2.0DETAILED DESCRIPTION I I

I 2.1Background l i

I NAPSandSurry Power Station (SPS) are similar vintage 3-loop Westinghouse j Pressurized Water Reactor (PWR) plants. SPS Unit 2 had a boron dilution I event on May28,2011that removed a substantial portion oftherequired j Shutdown Margin (SDM) while inIntermediate Shutdown (NAPS Mode4 l equivalent).

requirements; TheSPS event however, didnotchallenge itrevealed a weakness theTS shutdown inprotection against margin boron l

j dilution events. An extent of condition evaluation revealed NAPS's I susceptibilitytothe sametype ofweakness. Itwasdetermined that theSource j RangeDetector (SRD) channel indication forSurry and North Anna [

inadequately (1/M) approximated performance during the theoretical reactivity subcritical insertion events.

core multiplication factor Thelower-than-expected l l

response tochanges incore reactivity werecreated, inpart, bytheremoval of j Secondary Source Assemblies (SSA). j I

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Serial No.:21-043 Docket Nos.: 50-338/339 Attachment 1 Page2 of9 As a corrective action, NAPShadSSAsre-inserted, beginning fromUnit 1 Cycle 25(spring 2015) and Unit 2 Cycle 24(fall2014). This action to re-insert theSSAs atNAPS improved thecoupling between changes incore reactivity and SRD indication inthecontrol roomandimproved theoperators' abilityto identify, detect, andrespond toreactivity changes that could becaused byan inadvertentdilution event.

2.2M Theproposed change revises the TS3.1.8.A.2 Completion Time toisolate PG water fromtheRCS within 15 minutesafter entering Mode3,4, or5. j Specifically, theproposedchange would adda newrequirement toisolate PG l water from theRCSfollowing a reactor shutdown from Mode2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> j while continuing torequire isolation ofPG water within 15minutes after a l dilution ormakeup activity while the reactor is inMode3,4,or5. ,

Thefollowing changes areproposed tothe NAPS Units 1and2 TS. i j

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Thecurrent version ofTS3.1.8.A reads: l

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h Condition A.Oneormorevalves notsecured in closed position. l Required Action A.1 Suspend positive reactivity additions. -

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Immediately l i

l AND l e

Required Action A.2 Secure valves inclosed position. -

15minutes l l

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Required Action A.3 Perform SR3.1.1.1. -

4hours ,

Thereviseip version ofTS3.1.8.A. would read:

Condition A.Oneormorevalves notsecured inclosed position.

f Required Immediately Action A.1 Suspend positive reactivity additions. -

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' ' l AND l

Required Action A.2 Secure valves inclosed position. -

15minutes l ORWithin 1hour after Mode3 entry from Mode2. l l

Serial No.: 21-043 Docket Nos.: 50-338/339 Attachment 1 Page3 of9 AND Required Action A.3 Perform SR3.1.1.1. -

4hours Additionally, an editorial change ismadetoTS5.6.5, Core Operating Limits Report (COLR), to accurately reflect Amendments 287/270. Thespecific change removes revision bars unrelated toAmendments 287/270.

3.0TECHNICALEVALUAT.ION Theproposed change wouldallow for PGwater isolation within 1hour after entry Mode3following into reactor shutdown whenthere isnoplanned dilution ormakeup activity occurring. This would bea change from thecurrent Completion Timeof15 I minutes. The1-hour Completion Time following reactor shutdown isrequested to continue toensure prompt implementation of PGwater isolation without placing an .

undue burden onthe operating staffduring plant shutdowns. Additionally, following a reactor shutdown, operators arehighly focused onplant reactivity conditions and ,

arenowbetter equipped (since the re-insertion of SSAs at NAPS Units 1 and 2 in 1 response tothelessons learned from theSurry Boron Dilution event inMay2011) tobeable toidentify, detect, andrespond toreactivitychanges that could becaused j byaninadvertent dilution event. Asa result, operators, in the event ofaninadvertent j areexpected dilution, tocontinue tobeable totake action prior toanysignificant l reactivitychanges.  !

s Additionally, theproposed 1-hour Completion Timerequirement is consistent with theprovisions ofNUREG1431, Volume 1,Revision 4,"Standard Technical i Specifications, Westinghouse Plants," (Reference 1) Section 3.3.9A, "Boron Dilution l Protection System (BDPS) (Without Setpoint Control Program)" Required Action B.2.2.1 IntheStandard Technical Specifications, theBDPSistheprimarymeans ofprotection against boron dilution events inshutdown operating modes. Inthe Standard Technical Specifications, ifboth trains ofBDPSareinoperable, onehour j isallowed source toeither isolation restore valves."

a train Additionally, ofBDPStoservice this proposed or"close 1-hou'r unborated Completion water Timeand l

l basis isconsistent "SurryPdwer with Station the Units Completion Timeapproved 1 and2,Issuance byletter ofAmendments, dated May10,2017, RE:Changes to j

j Expand Primary Grade WaterLockout Requirements inTechnical Specification j (CAC 3.2.E Nos. M F7716 a nd MF7717)" (Accession Number ML17039A513). ji 1

Serial No.:21-043 Docket Nos.:

50-338/339 Attachment 1 Page4 of9

4.0 REGULATORY EVALUATION

4.1A

• Section 182a ofthe Atomic Energy Actrequires for applicants nuclearpower plant operating licenses toinclude TSaspart ofthelicense. TheTSensure theoperational capability ofstructures, systems, andcomponents thatare required toprotect the health andsafety ofthepublic.

a 10CFR50.90 requires NRCapproval foranymodification to,additionto,or deletion from theplant TS. Therefore, this requires activity NRCapproval prior tomaking theproposed plant-specific changes.

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• 10CFR50.36 requires that the TS include items inthefollowing specific l categories: (1) safety limits, limiting safety systems settings,and limiting 1 control settings; (2) limiting conditions foroperation (LCOs); surveillance (3) requirements per10 CFR 50.36(c)(3); (4) design features; and (5) administrative controls. This amendment isrelated tothesecond category j above since a change totheLCO3.1.8is proposed. l I

4.2Precedents Theproposed 1 hourCompletion TimeforPrimary Grade water isolation l following reactor shutdown wasapproved bytheNRCfor Surry PowerStation f byletter dated May10,2017, "Surry Power Station 1 and 2,issuance of Units Amendments, Requirements RE: Changes inTechnical to ExpandPrimary Specification 3.2.E Grade Water Lockout (CACNos.MF7716 and j

i MF7717)," Number (AccessionML17039A513). l 4.3M I

i t Theproposed change revises the TS 3.1.8.A.2 Completion Timetoisolate PG water fromtheRCS within 15 minutes after enteringMode 3, 4, or PGwater

5. l Specifically, from the theRCSfollowing proposed change a reactor would adda req;uirement shutdown from toisolate Mode2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> while l

l continuing torequire isolation ofPGwithin 15minutes aftera planned dilution j ormakeup activity while thereactor isinMode3,4,or5. E Asrequired by10CFR50.91 (a)(1), Dominion Energy Virginiahasperformed v anevaluation todetermine whether ornota significant hazards consideration isinvolved with theproposed amendment byfocusing onthe threestandards j setforth in10CFR 50.92, "Issuance ofamendment," Part50.92(c), andhas l I

SerialNo.: 21-043 Docket Nos.:50-338/339 Attachment 1 Page5 of9 determined that theproposed change doesnotinvolve a significant hazards consideration, asdiscussed below:

1.Does theproposed amendment involve a significant increase inthe probability orconsequences ofanaccident previously evaluated?

Response: No There arenodesign changes associated with theproposed change. AII i design, material, and construction standards that wereapplicable priorto l this amendment request willcontinuetobeapplicable.

I Theproposed change will not affect accident initiators orprecursors oralter j the design, conditions, orconfiguration ofthefacility. Theproposed change l doesnot thewaythe alter plant isoperated andmaintained, withrespect to  !

accident initiators orprecursors.

Although theproposed change isnot determined toalter thewaytheplant is operated change does with respect potentially toaccident alter the initiators or precursors, waytheplant isoperated asit theproposed would allow l

for PGwater isolation within 1hour after entry into Mode 3 following reactor  ;

shutdown from Mode2whenthere isnoplanned dilution ormakeup activity j occurring. This would beanincrease from thecurrent Completion Timeof j 15minutes. The1-hour Completion Timefollowing reactor shutdown is j requested tocontinue toensure prompt implementation ofPG water j isolation without placing anundue burden on theoperating staff andis j consistent isolation with following prior NRCapproved reactor shutdown.

Completion Timesfor PG water l

l Additionally, following a reactor shutdown, operators arehighly focused on l plant reactivity insertion conditions ofSSAsatNAPSUnits andarenow better 1and2 inresponse equipped tothe (since lessons the re-learned l

l from theSurry Boron Dilution event inMay2011) tobeable toidentify, l detect, andrespond toreactivity cha'nges that could be caused byan l inadvertent dilution event. l Asa result, operators, intheevent ofaninadvertent dilution, areexpected tocontinue tobe able totake action prior toanysignificant reactivity l changes. l I

Additionally, aneditorial change ismadetoTS5.6.5, Core Operating Limits l Report (COLR), toaccurately reflectArnendments 287/270. l l

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Serial No.: 21-043 Docket Nos.:50-338/339 Attachment 1 Page6 of9 Therefore, itisconcluded that the proposed amendment does notinvolve a l significant previously increase evaluated.

intheprobability orconsequences ofan accident  !

1 2.Doesthe proposed amendmentcreate the possibility ofa newordifferent kind ofaccident from anyaccident previously evaluated?

Response: No j There arenoproposed design changes orchanges inthe methods bywhich anysafety-related plant structures, systems, orcomponents perform their specified safetyfunctions. The proposed change will notaffect thenormal j methods ofplant operation orchange anyoperating parameters. No l equipment proposed performance requirements change will notalter any assumptions willbe affected.

inthe safetyanalyses.

The l l

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change doesnotinvolve a physical modification ofthe l l

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No newaccident limiting single scenarios, failures will transient precursors, failure mechanisms, or be introducedbecause of this proposed j

l change. There w illbe no adverse effectchallenges or imposed on any l safety-related system because ofthis proposed change. l i

I Additionally, aneditorial change ismadetoTS5.6.5, CoreOperating Limits l Report (COLR), toaccurately reflect Amendments 287/270. l I

Therefore, thepossibility itisconcluded that ofa newordifferent theproposed kind amendment ofaccident from doesnot create anypreviously l

j evaluated. l I

3.Doesthe proposed amendment involve a significant reduction ina margin ofsafety? g a

Response: No I

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I Theproposed change would allow forPGwater isolation within1hour after l entry planned into Mode3following dilution ormakeup reactor activity shutdown occurring.

from This Mode2whenthere would bea change isno from l P

thecurrent Completion Timeof15minutes. The1-hour Completion Time f following reactor shutdown would ensure prompt implementation ofPG water isolation without placing anundue burden ontheoperating staffand l l

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Serial No.: 21-043 DocketNos.: 50-338/339 Attachment 1 Page7 of9 isconsistent with prior NRCapproved Completion Times forPGwater isolation following reactor shutdown There benoeffect will onplant systems necessary toperform protection functions.

Noinstrument setpoints orsystem response timesareaffected andnone of 1 theacceptance criteria for anyaccident analysis bechanged.

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Consequently, the proposed change will have noimpact ontheradiological consequences ofa design basis accident.

Additionally, aneditorialchange ismadetoTS5.6.5, CoreOperating Limits Report (COLR),toaccurately reflect Amendments 287/270.

Therefore, isconcluded it that the proposed amendment doesnotinvolve a i

j significant reduction ina margin ofsafety. I i

i Therefore, Dominion Energy a significant Virginia concludes thatthe proposed amendment l doesnotinvolve hazards consideration underthestandards set l forthin10CFR50.92(c), "Issuance ofAmendment," and accordingly, afinding  !

of"no significanthazards consideration" is justified. l I

I 4.4Conclusion j i

I Insummary, inaccordance with 10CFR50.90, Dominion Energy Virginia l requests NRCreview andapproval ofthe changes toTechnical Specifications l 3.1.8 and5.6.5 forNAPSUnits 1and2. l I

Based health ontheabove andsafety discussions, ofthepublic (1) will there isreasonable notbeendangered assurance byoperation thatthe inthe j

i proposed Commission's manner,(2) such regulations, activities and(3) will beconducted theissuance incompliance oftheamendment will with notbe the j j

j inimical tothe commondefense andsecurity ortothe healthandsafety ofthe public.

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i Theproposed changewould allow for PGwater isolation within1 hour after entry j Mode3following into reactor shutdown whenthere isnoplanned dilutionormakeup j t

Serial No.: 21-043 Docket Nos.: 50-338/339 Attachment 1 Page8 of9 activity occurring. Additionally, an administrative change ofTS 5.6.5, COLR,is included toremove erroneous revision bars.

A review of the anticipated construction andoperational effectsoftherequested amendment has determined therequested amendment meets theeligibility criteria for categoricalexclusion set forth in10 CFR 51.22(c)(9), inthat:

(i) There isnosignificant hazards consideration.

As documented in Section 4.3,No Significant Hazards Consideration i Determination, completed ofthis license amendment request, todetermine whether ornota significant an evaluation hazards consideration was l

I isinvolved byfocusingon the threestandards setforth in10CFR50.92, "Issuance of Amendment." The Significant Hazards Consideration j determined that (1) theproposed amendment doesnotinvolve a significant i increase intheprobability orconsequences ofan accident previously l evaluated; (2) the proposed amendment does not createthe possibility ofa newordifferent kind ofaccident from any accident previously evaluated; ,

and(3) a margin the proposed ofsafety.

amendment Therefore, it doesnot involve a significant isconcluded that the reduction proposedamendment in l doesnotinvolve setforth a significant in10CFR50.92(c),

hazards consideration under andaccordingly,a finding of"no thestandards significant l

hazards consideration" is justified.

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(ii)There isnosignificant change inthetypes orsignificant increase inthe l amounts ofanyeffluents that maybereleased offsite. l l

Theproposed change isunrelated toanyaspects ofplant construction or l operation that would introduce anychanges toeffluent types (e.g.,effluents l containing chemicals orbiocides, sanitary system effluents, and other j effluents) or affect any plant radiological or non-radiological effluent release quantities. Theproposed change does notadversely impact anyfunctions l associated withcontaining, controlling, channeling, monitoring, or l processing radioactive materials, ornon-radioactive nordothey diminish j thefunctionality ofanyldesign oroperational features thatarecredited with j controlling therelease ofeffluents during plant The operation.types and l quantities path ofexpected isassociated plant with effluents this arenotchanged.

amendment. Neither Noeffluent radioactive release nornon-l l

radioactive material effluentsareaffected bythis activity.Furthermore, the ,

proposed change doesnotdiminish thefunctionality ofanydesign or  !

operational during features plant that operation.

arecredited Therefore, with controlling itisconcluded the release that ofeffluents theproposed l

I amendment doesnotinvolve a significant change inthetypes ora l I

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SerialNo.: 21-043 Docket Nos.: 50-338/339 Attachment 1 Page9 of9 significant increase intheamounts ofanyeffluents that maybereleased offsite.

(iii)There isno significantincrease inindividual orcumulative occupational radiation exposure.

Theproposed change doesnotaffect plant radiation zones described in ,

UFSARSection 11andcontrols under 10 CFR Part 20 preclude a  !

significantincrease in occupational radiation exposure. The proposed change does not adverselyimpact radiologically controlled zones. Plant radiation zones, radiation controls established tosatisfy 10 CFRPart 20requirements andexpected amounts andtypes ofradioactive materials arenotaffected by theproposed amendment. Therefore, ,

individual andcumulativeradiation exposures arenotsignificantly affected  !

bythis significant change. Therefore, increase the proposed amendmentdoesnotinvolve inindividual or cumulative occupational a

radiation j

exposure. ,

I Basedontheabove review oftheproposed amendment, it hasbeendetermined that anticipated construction andoperational effects of the proposed amendment do i notinvolve (i) a significant hazards consideration, (ii) a significant change inthe l orsignificant types increase intheamounts ofanyeffluents thatmaybereleased i or(iii) offsite, a significant increase intheindividual orcumulative occupational i radiation exposure. Accordingly, theproposed amendment meets theeligibility criteria for categorical exclusion setforth in10CFR51.22(c)(9).Therefore, pursuant  !

to 10 CFR 51.22(b), an environmental impact statement or environmental assessment ofthe proposed amendment isnot required. ,

i 6.0References ,

1 1.NUREG1431,Volume1, Revision 4, "Standard Technical Specifications, Westinghouse Plants," April 2012.

from 2.Letter NRCtoMr. Daniel G.Stoddard, "Surry Power Station Units 1and2, issuance ofAmendments, RE:Changes Specification toExpand Primary Grade Water Lockout andMF7717),"

j Requirements inTechnical 3.2.E (CAC Nos. MF7716 l datedMay10, 2017(Accession Number ML17039A513). j l

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Serial No.:

21-043 DocketNos.:

50-338/339 Attachment2 i

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MARKED-UP TECHNICAL SPECIFICATIONS PAGES l

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Virginia ElectricandPowerCompany (Dominion Virginia)

Energy NorthAnna PowerStation Units 1 and2 I

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Primary Grade Water FlowPathIsolation Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS V~alves

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3.1.8 Primary Grade Water Flow PathIsolation LCO3.1.8 Each valve used to isolate primary grade water flowpaths .

shall besecured intheclosed -

position.

NOTE-- - -------

Primary grade water flowpathisolation valves maybeopened under administrative control forplanned boron ~

dilution or '

makeup activities. ~

APPLICABILITY: MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME  !

c A. ---------NOTE------- A.1 Suspend positive Immediately j Required mustbecompleted Action A.3 reactivity additions, j

whenever Condition A AND isentered. -

L A.2 Secure valves in 15minutes j closed position. ^

OR l Oneormorevalves not ,e ,

1hour aher I I

secured inclosed AND N VVithin

. position. -

A.3 Perform SR3.1,1.1 4 hourMode Mode 3entryfrom 2

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SURVEILLANCE REQUIREMENTS SURVEILLANCE -

, FREQUENCY 1 SR 3.1.8.1Verify each valve intheaffected flow path Within 1 ,

that isolates primary grade waterflow 15mi'nutes A1 l paths secured islocked, intheclosed sealed, or otherwise position.

following boron a

dilution s A(

j ormakeup -

A L2 I activity s .

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North AnnaUnits 1 and2 3.1,8-1 Amendments 231/212 n. j I

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No.:

Serial 21-043 Docket Nos.:

50-338/339 Attachment 3 I

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PROPOSEDTECHNICAL SPECIFICATIONS PAGES  !

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j Electric Virginia andPowerCompany j (Dominion Energy Virginia)

AnnaPowerStation North Units 1and2

Primary'Grade Water FlowPathIsolation Valves 3.1.8

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3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Primary Grade WaterFlowPathIsolation Valves LCO3.1.8 Each valveusedto isolate primary gradewater flowpaths shall besecured intheclosed position.

NOTE Primary water grade. flow path isolation valves maybeopened under administrative control forplanned boron dilution or makeup activities.

APPLICABILITY: MODES 3,4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETIONTIME A. ---------NOTE--------- A.1 Suspend positive Immediately Required Action A.3 reactivity additions.

mustbecompleted whenever Condition A AND isentered.

A.2 Secure valves in 15minutes  !

closedposition l Oneormore valves not OR l secured inclosed

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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 /> j

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Serial No.:

21-043 Docket Nos.:

50-338/339 Attachment4 l

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(Dominion EnergyVirginia)

NorthAnna PowerStation Units1 and2

Primary Grade Water FlowPathIsolation Valves 8 3.1.8 BASES LCO flowpaths maybeisolated from the,RCS byclosing valve (continued) 2-CH-140. Alternatively, 2-CH160, 2-CH156,2-CH-FCV-21148, and2-CH-FCV-2113B maybeused in lieu of2-CH-140.

TheLCO ismodified bya Note which allows theprimary grade water flowpath isolation valves tobeopened under administrative control forplanned boron dilution ormakeup activities.

APPLICABILITY ThisLCOis applicable inMODES 3',4, and5 to prevent an inadvertentboron dilution.event byensuring closure ofall primary grade water flow pathisolation valves.

InMODE Isolation 6, LCO3.9.2, "Primary Valves-MODE 6," requires Grade Water allprimary Flow Path grade water

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I isolation valves to be closed toprevent aninadvertent l boron dilution.  !

i InMODES andwasfound 1 and2, theborondilution tobecapable of being accident wasanalyzed mitigated.

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ACTIONS AM I

Preventing inadvertent dilution ofthereactor coolant boron I concentration water flow isdependent pathisolation onmaintainingthe primary grade valves locked, sealed, or l

j otherwise secured closed, except asallowed under j administrative control bytheLCONote. Becauseof the j

p.ossibility ofaninadvertent boron dilution, Required l Action A.1prohibits other positive reactivity additions j while securing.the isolation valves on theprimary grade j water system. TheCompletion Time of "Immediately" for suspending positive reactivity additions refleorwithin 1hour  !

importance sothat ofpreventing anyboron .dilution known positive event reacti canbe'readil afterMode3entry i l

andterminated from Mode2 j I

TheRequired securing Action theisolation A.2Completion valves Timeof15minutes provides sufficient timeto or j j

close andsecure theisolation valves ontheprimary grade j waterflow paths while minimizing theprobability ofan .

E unintentional dilution.during theCompletion Time. Secur1ng .

i thevalves intheclosed position ensures that thevalves '

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cannot beinadvertently opened.

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I North 1and2 AnnaUnits B 3.1.8-2 Revision 8 i

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