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| number = ML13252A243
| number = ML13252A243
| issue date = 08/28/2013
| issue date = 08/28/2013
| title = H. B. Robinson, Unit 2, First Six-month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for beyond-Design-Basis External Events (Order Number EA-12-049)
| title = First Six-month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for beyond-Design-Basis External Events (Order Number EA-12-049)
| author name = Gideon W G
| author name = Gideon W
| author affiliation = Duke Energy Carolinas, LLC, Duke Energy Corp
| author affiliation = Duke Energy Carolinas, LLC, Duke Energy Corp
| addressee name =  
| addressee name =  
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:A AWbmm Soon%796 R4 10 CFR 50.4 Serial: RNP-RN13-0]87 AUG 2 8 2013 ATTN: Document C;ontrol Desk Un~ed State Nuclear Reguao Commission Washington, DC 20555-00 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23  
{{#Wiki_filter:A R4AWbmmSoon
                                                                                  %796 10 CFR     50.4 Serial: RNP-RN13-0]87 AUG 2 8 2013 ATTN: Document C;ontrol Desk Un~ed State Nuclear Reguao Commission Washington, DC 20555-00 H. B.ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23


==References:==
==References:==
: 1. NRC Order Number EA-12-049, Order Modgf*g for umptatwn Strategs for Beyond4)ealgnbowI Externa ErWnt, dated March 12,2012, (ADAMS Accession No. ML12056A045)
: 1. NRC Order Number EA-12-049, Order Modgf*g Lkws*WOh Reg"rd*--oR for umptatwn Strategs for Beyond4)ealgnbowI Externa ErWnt, dated March 12,2012, (ADAMS Accession No. ML12056A045)
: 2. NRC Interi Staff Guidance JD-ISG-2012-01, CW ance ,* Order E-12049, Order AtWhýfjtg WW"ee with Regar to Requ W)Wiremnt
: 2. NRC Interi Staff Guidance JD-ISG-2012-01, CW ance ,* OrderE-12049, Order AtWhýfjtg WW"ee with Regar to Requ W)Wiremnt for UpMitgto S"Wtgle for fetynd-Oein-faele Extnerl ueiv"t, Revision 0, dated August 29, 2012, (ADA" Accessio No. ML12229A174)
: 3. NEI 12.06, Oivee and Fbext COP* SbraMW (FLEX)                  WInpwnttn auide, Revision 0, dad August 2012, (ADAMS Accession No. ML12242A378)
: 4. Duke Energy Letter, CaoW Power n LtCoNpany and Forkd PbWW Copoator Iniba Stafts RWW in Rsepm to MAftm 12, 2012, C&onsuon Order MfocSij? License with Re~gar t0 PRequ wiiremets for Aitgakwo Stratgie for Be~ayd-DeFoau* ExtWen Event (Order hnterEA-12-.W), dated Oeter 29, 2012, (ADAMS Accession No. ML12307A021)
: 5. Duke Energy Letter, Overall Inegrated Plan In Reow to Mach 12,2012, Commission Order M~ocifyin Liensee ith Regard to Requireent

Latest revision as of 01:52, 6 February 2020

First Six-month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for beyond-Design-Basis External Events (Order Number EA-12-049)
ML13252A243
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 08/28/2013
From: William Gideon
Duke Energy Carolinas, Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
EA-12-049, RNP-RN13-0]87
Download: ML13252A243 (20)


Text

A R4AWbmmSoon

%796 10 CFR 50.4 Serial: RNP-RN13-0]87 AUG 2 8 2013 ATTN: Document C;ontrol Desk Un~ed State Nuclear Reguao Commission Washington, DC 20555-00 H. B.ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23

References:

1. NRC Order Number EA-12-049, Order Modgf*g Lkws*WOh Reg"rd*--oR for umptatwn Strategs for Beyond4)ealgnbowI Externa ErWnt, dated March 12,2012, (ADAMS Accession No. ML12056A045)
2. NRC Interi Staff Guidance JD-ISG-2012-01, CW ance ,* OrderE-12049, Order AtWhýfjtg WW"ee with Regar to Requ W)Wiremnt for UpMitgto S"Wtgle for fetynd-Oein-faele Extnerl ueiv"t, Revision 0, dated August 29, 2012, (ADA" Accessio No. ML12229A174)
3. NEI 12.06, Oivee and Fbext COP* SbraMW (FLEX) WInpwnttn auide, Revision 0, dad August 2012, (ADAMS Accession No. ML12242A378)
4. Duke Energy Letter, CaoW Power n LtCoNpany and Forkd PbWW Copoator Iniba Stafts RWW in Rsepm to MAftm 12, 2012, C&onsuon Order MfocSij? License with Re~gar t0 PRequ wiiremets for Aitgakwo Stratgie for Be~ayd-DeFoau* ExtWen Event (Order hnterEA-12-.W), dated Oeter 29, 2012, (ADAMS Accession No. ML12307A021)
5. Duke Energy Letter, Overall Inegrated Plan In Reow to Mach 12,2012, Commission Order M~ocifyin Liensee ith Regard to Requireent for Mitgaton Stratgie for &*yond-OesIFI-8as&External Event (Oerder Nmber E4-12-049), dated February 26, 2013.

Ladies and Gentlemen:

On March 12,2012, the Nuclear Regulatory Commission (NRC) issued Order EA-12-049 (Reference 1) to Duke Enrgy Progress, Inc., fomely known as Carolina Power & Ligh.

A(5(

United States Nuclear Regulatory Commission Serial: RNP-RA/13-0X07 Page 2 of 2 Referec I was irmedately effective and directs Duke Energy to develop, i.plement, and malntan gdance and strategies to maintain or restore core cooli, oontairment, and spent fuel pool coong capaWbiles inthe event of a beyond-dsign-basis exernal event. Specific Iements are ou in Atachmet 2 of Reference 1.

Referenc I required sWubm of an nitil status report 80 days followin Issuance of the final Interim staff guidance (Reference 2) and an overall Integrated pln puruant to Section IV, Condition C. Referern 2 edorses indusr guidance document NEI 12-08, Reision 0 (Reference 3) with cafcatons and excepbons intMfd in ferenc 2. Reference 4 provided the Duke Energy Initial status repout mgd mitigation strategies. Refrene 5 pwoved the Duke Energy ovea Integrated plan for K.B. Roio Sem Electric Palt (I.BRSEP).

il iýA- 8, (+J it "Si 4 Reference I requrs s son of a stau report at sx-month intervals fowing subittl of the ovwell Integrated Plan. ROeence 3 prvkdw direction nrgdigthe content of the status reports. The purpose of this aer is to provide the fi six-month status report pursuant to Sectio IV,Condtion C.2, of Reference 1, that felineae progress made I inplementing the requ of Refn 1. The attched repot rovides an update of milstone hffwft since the lat status report, ind any changes to the compance me ,

schedule, or need for relMeM and the bais, if any.

There are no regulatory commitmenwt made inthis submittal. Ifyou have any questions regar*ing this submt, please contact Mr. R. Hightowe at (843) 857-1329.

I declare under penalty of perjury that the foregoing is true and correct.

ExecutedOn: Tusr" ?o,0

Sinceely, Site Vice President WRG/am Enclosure
1. First Six Month Status Report (Order EA-12-049) H.B. Robinson Steam Electric Plant (HSRSEP), Unit 2, Docket No. W0-261, Renewed Lcense Number DPR-23 cc: Mr. V. KL MoCree, NRC, Region II Mr. S. P. Lingam, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP, Unit No. 2 Ms. J. A. Kralchrnan, NRR/JLD/PMB, NRC

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/I 3-0087 18 Pages (including cover sheet)

SERIAL RNP/RA.43aUI ENCLOSURE FMSTISIX MONTh STATUS REVM (ORDE* A1.2449) 3*.

U WISMOf M ELCS AN? (O It l2 DOC1KET O9S" WELCENSE NO.1O23 E1-i

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-0087 18 Pages (including cover sheet)

1. hoomduwon RNP developed an Ovewa integrated Plan (Reference 1 inSecdon 8), documentkn the divers and flexible strategies (FLEX), In response to NRC Ordw EA-12-049 (Rleference 2 InSectio 8).

The Owe IMWe ed Plan was submitled to tw NRC on Febmu-y 26, 2013. This endcour provides an Updat of M10soft accwvIehrne--. hi:cudng any hags to the complaro met*d, schedule, or need forrieWh/rexason and the basis I ay, that occurred ung th period February 26,2013 to July 30.2013 (hrea~fter rearred to as -fto update perlod'). This update is based on an pproved formal Engineefn Change-Evaluatlon (6W1:R1) that is d-W* wvewd and dein verfd.

L. M~eswAneROVmP1shmen1 The foowin mieone(s) have boen ope sk the ds pntw of the Overa Intesatd Plan (Rleference 1), and are cunt as of July 30,2013.

  • Complete Skrtgy Develokment
  • Submit Inegrated Plan 0 Complete t icion caton
3. Mi*tel Sobskib Satsr The toowin provides an update to Attacbmt 2 of the Overall integrated Plan. ft provides fm acvy stu of each Iem, and wh O expeted complion dae has changd. The dales are pWinr* dWats subect to chane when design and knpentaion detais e developed.

The revised mietndagtcmlton dtsdo not kinct the order Implementation date.

lrw" Aidf To"*

NNIMgel Complete Strategy Development Februar 2013 CoampletSDoNt Subm Integrated Plan Februwy 2013 CompOlete Re Not Au" 2013 Started Doa Not Februay 2014 Dae Not

&ft* 2014 Revised August2014 Not Started Dete Not

__________Revise February 2015 Not Strted Date Not

_ _ Revised Complete ModMcatlon tkfWction March 2013 Caom Date Not

___________Revised Complete Modification Development February 2015 Started ae NotA Complete Equment Procurement February 2015 Not Started Raevise E1-2

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/I3-0087 18 pages (includ cover sheet) _.... '_

Complete Equipmet PM oevelopment Febnuwy 2015 Not Started Dev Not Compket FSG Devekpmet Febru*y* 2014 Staroed D Not

___ ___ ___ Revised Isue FSG June 2015 Not Started is e N May 2014 Not Stared Ode Not Complet Training Intte Trai ma memn May2014 Not ed Not Complete Tranikg May 2015 NotStted Date Not November Not Stated Daft Not Coplt SafigAsemet2014 _____________

Plan 2014 _ Revised Cosplete O.N n .a"- May,2015 Not Smile Da% Not COoPIGS ............... Not Startd . . . eNot RNP FLEXCommnic an Ion NoDem Not Startd Not

~~~Cr June 2015NoStue EI-3

U.S. Nuclear Regulatory Commission Encloswe to Serial RNP-RA/M3-0087 18 Pages (including cover sheet)

4. Chare to comp i Me The oown summaes deribe chang to the oonplance method &adocumented in fth Overal Integrated Plan (leference I).

Miatat Co cng ad Hat Remov, PWR beod G m t Pioe I

1) RNPOIPp. 11 o74,para.4 t4Se:

The Steam Driven Awdiary FPeadw Pump (SDAFWP) wi deliver Cond ft ftrage Tank (CST) kvno to the 8G0. The AFW Sys*tm I reqi*ed to be in operation w"hin 27.5 ihae of event initiati, (Refernce 9). Wth AC poww ls the sm supy valNe to thNSAFWP mut be manually operded. Addllo*, wh AC pow lst. the AFW reuotng valves us be marwaly aop d. To lb*t No *urdW .ebwew opeator Meslown e of the *wn tbins of Ve deem smpply edreelatg vadws wl be moiled to opsie on OC p~r d will eapeal

-be oe beig opermad hmm Vh CowrN Room, (Open NOm 1.

InNeu of italng a Dirct Curmt Powwd Moor OpertMed Vae (DC MOV) on one stem supply to th Steam Driven Auwdry Feedawa Pump (SDAFWP) and a OC MOV on one Am" Fwavte (AFW) valve.,tecu t emergencs-g o mauay opening m e vslves will be re-taind. This is a proven tkicftW action In RNP pocedure (Ref. 4).

Open Itm 12 isdeleted MAlhmen 3,FPgur 3 Isrevise.

2) RNP OIP p. 11 d 74, para. 5s  :

The CST Is thO source of NAW. The tank and b level Instrwetton are nbm qulfe,(Reference 10); however, they are not Aro* ted rom vwind orM40e. 'inorder 11o cope with an ELAP for an ideinit time, thMe MY? nventory mut be made-up. C~rret coitime isu 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Nomal amo*eto tie Ltimate He Sink (UHS)

(La. Wae Rons). per Me restrto ou*t r N.N'12Oe, Seo0 is assmed to be unavailale -and 'toe UMS can oiyb cesdungpoftefi eqU~xien tioiestkon wil b Inhlget idto isdpn h CS, aClet Fwind a Imdnuls"Oe flow 13) and to add ain aente CST whic wit be sutkx ngg andI& *WOW to wi ~thante appkicalle hato", ( 0e"1~ 14). Thi*" ST may be hardVWe ID i Cbat

  • theeitnCST andor. to a new header such tha fte exWVIstin coul be bypassed In the event it,is unavaiabl. This Alrwtem CST wil be located at a highe eleatin to allow Due to loc*Win resftrions and proxmity to otherq**mnen,l ItIt not feasibe to protect fte CST againthih winds and missiles. InNou of hardenin fth crent Condenste Storage Tank (CSa) and level lnstrw*eti, the proposed Ahtrhate - esd to 4lOw time f Re" nal Response Ce suppot whut a need to ftrion to several water source$. Open item 13 Isdeled.
3) RPCO'p.1241f*, para.vfs te e Afternatmemans of reducing,or *nkiatln Ootnalosoftjr1, 4~ dtt64rtfs such asu-tmod"yh valveLCV.14iA, hav also been con~ded. ValveLOV-14l7A is fil-"openA 'ivia E1-4

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-0087 18 Pages (including cover sheet) pvides MnMeMty between the CST and th cnes hotwels. LCV-1417A wMt be convertd frvoma MNpen vv I* & ailoleed vlv to pmode luoss of CST hvownioy, (Open Oum S.

Upon kather rewvew an inveelgton, AN d1soered tha a preu attmpt to modily LCV-1417Aocuredln2010. RNP c odtht such a modlcatlon wes not faslble. In additIon, the potential loss of CST koetorfy Isaccounted for Inthe proposed A** see rs~sig elgifOatyblager volumeof 6aIIPIM-00.000 galon.

In lieu of modIno the hotMll makeu valve (LCV-1417A) from fall~open to f61-dlosed, the cuet strat to mnuyb o* the va wil orad (Ref. 4, Se O). OpenItm 16 is dted. Atftmt 3, Fogur 2Is revised.

4) RNP OIP p. 12 of 74, Me*ely dlbaJli its stales in part
  • One of fth thre tran of sOea supply and regulafti valves modified to operate with a DC powered actuator, (Oen Item 12).
  • Harden the existig CST ad CST Wlv (Ope Item s).
  • Chang LCV-1417A from fatlopen to fcwedt,(Ope tm 15).

Open Items 12,13, and 15 are deleted as desrbed I Items 1, 2, and 3 above.

Maihivt Cowe Coon mW we emo Val MR Po*ule Eqimen PhaS 2

5) RNPOiPp. 14of74, pra 3stifew ;4:

Aporble pump *8 be proue &Wd pistsgid emoteso pump amaOpen

""em IS.. To-meet 4+1. reurments,, a, adinl p wil b stored In aW designed per the criteria of WE12S ,Soeus t.3, (Open ftem19).ý Theses "M" pumps wil be capabl of taiaN suction from &a *urety-of Ibri sources (preferred source Isthe CST) and can be conneted directly kfo the AFW System. Makeup to tie CST can be via the skx iuh emegency fM connecdo valve, DW-2B6, (whic wil be modied to ca sndard FLEX fitg), (Open 1t0 20).- Ah addion oftmoeado wMbe prioedid fcr the CsT to .satsfy Waerat *tlt , (0pe fm 21). Atee-connection WI be added to the C AFW Pump dischwae loe, (Open. Iom 22), h wN aNlow the ptal pumnp bo supply the AFW systemn.

1. The portable pump for Stewm Ge* rat eno Coont System (AS)faed+c0a lt w4 not be pre-staged. The pump wI be stored Ina proced facily. Open Itm 18 Is d ele ted. ý ... ..
2. An additional owneto wi be added to the MtMatCST to satsy altev"a ortera (Open Item 21).
6) RNPOIPp. 14of74,para. 5stMes:

After dessurtzato is iated, It is deab to isolate the Safety Injectin (SI) accumnuhfsto W Mriso r to. prevent_ nitrogen kinjetion to -te ACS," whlVbWold inv*6de natura circulation oofd. AfterM anMAP, Wesver,'po~we to the SI aoourrwullotorleoleftii valves is, iuavafllab. Though IMe valves can Ibe nMantuelly operated, thei locationi *,Bde E1-5

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/1300)87 18 Pages (including cover sheet) contaimet pracludes accessiblity. The vvs am powed by WCC 5 as CC ond w be re-powee vim swNlhgw El or 92 at dwoU toO cw's with portaifl dis ge8nerat01s, (Open ftm 34 The RCS cooldown strategy will mainain SG pressures greaterthan 300 psig unti RRO su t is provkded inPhase 3. The Si Accumulator Isolatio "n wval not have to be cklosduntil that time. The Safety Injewio ($1) Accumulaor Isolation Valve wig be powered in Phase by Regional Repoe Center (RRC) suple diesel generators to be connected to El and E2. MCC5 and MOMS are pwered from El aid E2 respectivel, FLEX connctions will not be slded to MOOS and MOOS dirctly. Open Item 47 was Initiated to track the MCCO and MCO Alterrne power strategy whi Is not muired as a Phase 3 sttegy. Open Htem 47 is deleted and Open trm 25 is revised amount for this strategy. A#tt 3, Figure 6 is revised.

7) RNP OIP p. 14 o 74, para. 6 states:

Reactor core cooling and heat removal with the SG. unavailable during Modes 5 and 6 were also considered. UThe pomy tr tMOM to *upp poweto Use heglmg pu,, Is by energiz g 4V awblsgeer El ofT.The swtchgearwi be powered by moifying the current 480V switchgear El or E2 to Include connection ponts near the eist dlesel genrator that wi be cap" d swthng between the existing dke generator power feeds and the portable FLEX gnermor power feeds, (Open Iom 26). INE1 or 92 ore vaIl w seondary me thod wi entl t. fmg a mautu b'anftr ewitab wit po l gew or connotmlm 0* wi be installed r a oheging pvmp (Open tem 2?). The source of wae for e* targi1g pumps Iste MWNT.I Cwme,

  • MW Is eesmlooly quaiedo Mut Ws nt prbctsed frM wind or melseles. The RWST wit be hasmmns to precmet agminsi thse hm nr&d (Open Rem 41)

I. As noted in Items 6) and7 ) above, El andE2wl notbepoworedinPhase2. The same portable pump tht wl be used InModes 1-4 for reactor core cooling and Iea renoval with the SGs oval" wil be tvallb in Modes 5 &W8. RNP Is lropoeing a modified check valve bonnw t with-the aMroprW sized FLEX connections be instalied in the SI pump check valv during outage periods; this would be controlled in te shutdown risk managment prcedures. The secondary method Is accounted for with diverse FLEX oonnvdion ponts and redundt p r munits. Open Item 27 Is deled.

2. The prkmay source of water is.#* RWST for all non-missile hazard events. For missle hazard evenwt, a portable bonrat tanker protected against missiles is selected and will be stored in a prtected facility. It Is not feasible to harden the RWST due to originol design and proxmity 1#0te *qwlpminFl, AWn,4 isO 16,0000d.
8) RNP OPp. 1,of 74, pers. 2 states:

The ulthpoe source of cor pooling water (and th only one capbl of providing k*dft functioralt) is LUeke RobL The Ut.IS will withsta* d aseismc event as the earthe n dam is evaluated as seismically robust, (Reference 12). Due to a relatively long distance EI.G

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-0087 18 Pages (including cover sheet) between the lae and the plan, it isdesirable to use Service Wate (SW) pping as a flow path. The SW System Isconnected to theAFW Sytem via two locked valves (SW-I 18 amd AFW-24) located Of the south SW header which wi be opened, f needed, to rase water rom Lake Robinson to the suctim of the SOAFWP. Mechanical oonnections wi be added dki ectd:ino both to souih and norh SW heederwto allow &portal pump to connect, whe tafn suction dreotly hom Lake FRobinsonlard bypassg li SW pumps, (Open Rom 29).

To rable thb NOeaaew, WesseuO M M4 PC NM I Wt6 wi4 oredIn a roI ItIsl proed leatoo u s IheI w ut (OPs ftom o)

1. This strategy is moved to Phase 3 when h capacity, low hed pumpers wU be suppled by the ARC and connected to toe SW headers at the *ntake structure. The porta pumpers will not be stored ina robust structure new the ite structure. AFW sup* wNi be satisfied by sizing the Altebna C app0opriately
T based on decay het Sm"ov 1re m eM t LAe R* insW quaWW ty, and RM response times. Open Item 30 is deleted.
2. Current RNP strategies for Phase 3 wm also inudes a'poftbe pumper and water treatment fAcie to replsnish th Alternate CST ron ,oe Robinson for defite coping. The pumper we b stored ina protected storage fhclty.
9) RNP OIP p. 15, 16 of 74, Idesy UodUlsasni sae in part:
  • Stage N+1 poal pumps at Intako for SW makeu via SW piping, (Oen Item 30).

" Modify MOC 5 or MCC 8 to alow connection to portable geneaors, (Open oem 47

" Harden the RWST, (Open Itm 41).

Open Nems 30, 47, and 41 re defletd as dessrbed14 It.1sems67 Sab~ove.

Mahie COMr Coofin andMofte 1*ussat FWR P"%"Sqisut~hs 10)RNwOlPp. 19of?74, par& 2 staes*:

A generator of adequate c~ap*y will be delwre to the *fte from the,Regional Response center and w be cqb of repowen one train of dlwgi flow. Wkh one *emeg*y train powered, ft pIMn wi have greater operatXon fvlxty and the Sbit to add maler non-s"sal kad. PoWer wil be supped to as esy e6u66m during a Beyond Design Seafs ExternAl IEvit (BOES)W.

Two large FAC genertatrs (460 vAC,V SW 0 ) wil bevonnected to emewgcy busses El and E2 inPhse 3. This redundant capacity wil suppy RS dhagi, ver#a .on, lihtng, and the ability to fet s ig term RCS cooi using Insaed RH4R and COW puMps combined wkh portal pumper.,to supply SW fo COW, soing.

Maintain MCS IwveallyVotr, PWA Portl Eq*m Phase 2 11)fNPOiPp.23of74,paa.2*31tates.: .

Prikry Strate Tfnwy a e e Phu . rtains, aoohV hwentory cnro isto utilize the RWST and a-duargng pump; Currently, fte RWST is seismically qualiie, but Is not El-7

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-0W7 18 Pages (including cover sheet)

Potente from wind or missiles. The

  • W Nlbeladen*d to potet agains teMS hlamrde, (OeM m 41) The prim y strotey to supply poser to the o.Ier purs- Is by energlaing 46W swltshgeller Vl or ft. Tha ewltebgear wil be Powered by moifi Vie euun4W Sw ilohpar El orE to Ifllud oanb* eetio pindte near Use geet power feewd ewd lmpo MX wgeeaom powberf (Openf em M V El or a ae wON , In sesonda melhod will entoll ukhnt a manual tlranser s,, that anm be sed wt, jotaM genera or eneoone Nauw be Installed for
  • ski pu*. (Open Mim 2) Cables, can be conne*ted between the porta diesel generator and primary "ndInterface c m by utifn a quick-connec sysem. The atd sie "d the geneto will be defemilnad at a lerdae, (Open Item 42).

Aernative Strew An afternsat metod for boraled water makeup Is to use a portable positie d Icment pump connec dlredly to the Sae*t lecftn heades from th RWST. A mechanial FLEX cmnection will be added to the RWST and a prkry and alterne connecdion wil be added to the S systm, (Open Itm 32). Guidance in WCAP 1701 specfykin RCS vtvoy pose dsplaement pumpe sd at:

  • gW at an estirmaed 1500 psig wl be folOWed, (Reference 6).
1. Inablt of Low Laokage Sea (SHEILD) is sc*Ndu in he upcomng R2 uage.

RCS makl wUill not be required forat eastft first ? days othe evenw as ealuated by WCAP-17601.P, Reactor Coolant System Response to the Extended Loss of AC Power Event for Wsti;nghuse, Combuion Engnewri and BWacck &Wilcox NSSS Design ) (Rfow e 3, Section 0). RCS makeup capability Isnot required until phlas 3.

The 480 VAC emergency busses wI be energized using RRC genem Inphase 3, allowing for &hagin pump avallabilIty and the closur of the SI accumulato isolation valves. Powering bo4h **mg**y busses provides for redundancy. The*can pumps wi not be required InPhase 2 and portable eketr generator conwions will not be installed. Open tem 27 Isdeleted. The beated watersour cs aret RWST for nonmiss hazard events and a porlafe boralon tanke to be stoWed ina probecd facwlt.

2.RCS boration will be acoBese Ninga'wuM- portable high pressur pumpers from the Refueling Water wSt Tank (RWST) or portab bo tanks stored in a prtcted faclty. The RWST wI not be hrdned gainstwind and missiles. Open Ntm 41 Is deleLed. 480 VAC emergency busses El and E2 will not be energized inphm 2.

12) RNP OIP p. 23 of 74, idnty M- o- states inpail:
  • Harden the RWST agais wind and missiles (Open Item 41)
  • Install portable geneato onnection on a chargin pump, (Openi item 27)_

Open Oe 41 n n 2*eR deleted as descrid Initem, 11 abxoye.

'Safety11Fu"1neton upport, PR installed E##*WOeW Phas 1

13) RNP OIP p. 41 o 74, para.2 states Essent-a Instn-mentation El-S

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RAII3-0087 18 Pages (including cover sheet)

A sWgnifcn arnount ont m is relied upon to monior key reactor paraeters.

Thoseistmetio channe*s powered by station baftetere, would be umavakimbe upo battery depletion. ThM F strategies to improve battery coping are necessary a a result of tenood toes d Phm s1. Th*is w be aeomplahod by lhisoftqalg whl, nons-eafet relaed haft emu esqpie of prvlding m ovevr ia hour mimm capaOity (i ounor t X s.,tregy hW tos tht UO iadlln of mnw bedms wi best meat .1gM hour A" i's16mme Skia he- ..........m. of this modlUnilon ellegWs th" Ay to Dmo ply wit Va tow eyWol 01mmIltms saty deed

@nserg wi etvalat whelier a kite delg opion aim AMy cherp to ft strmatgy wN be up~d*n*th Apo A *M3 submMAL) (Open bm 4Uý

1. In Neu o kstal additoa staio ba4edes. as backup to the &isln viAlW batWeres, RNP Is kistalln FLEX power connecion point to each of the 4 atmn battery a

dwgerm t can be qulcM y cornncled to one df2 diesel gener tht* wil be staged inthir protected deployed posto. Pr*emia SLAP bettery copin analysi indkict there is sllet time to aconplah thi sttgy vwen al equipme" and Mc1ie pre~smged.

conneTWons

2. Open em 48 Isde~ltd.

L. M"efor VL".11 L ON ftA1 I OW sodmlsVe *0 * " INASt RNP expects to comply wih the order mplemetan dole and no reWle la Isrequed at this time.

Opn loma u Overnal -graed Pla end rlatv* E lntn The following tale providea unmuy of the open items doclmnentend in the Overall Integrated Plan. Tthr are no open itms to the Draft Safety Evaklutn MIdetd at this time.

t"nm# OpW. "m Dasorpil _ ___

1I AReogional Responise Centers (ARM) playj k wil be Staited deveoped to support RNP dn "beyonddesig basis everts

2. Figure(s) (sWe plot plan) showing FLEX equpment soaeStarte foctions and dployq t mutes w be provided. Fures w_ be captxedinEC8 2 Rev. I...,
3. Deploymedt stategies wil te icarporated Moan Not $StMd
4. RNP wi kroplemen th prograiv conbros inaoonce Not Stard with NEI 12*06.

5., Equpnt asoculrnowith tOhes strategies Q, be %oed Strted as cormmeroai equormnot with design, storage, maintenance, _____

EI-9

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/I 3-0087 19 Paw(QaqLudt cover s*h)..

testig. and con~pfigrton conro Inawcrdlanc with NEI 12-oS, Section 11.1.

6. The unaaidilt y Of equipmet adapial oncin tht dcly peftm a RFX mtto staty wi be M ~ usirv ow pls euimen M"n gukdeine devolod inaccordac wit NIa * -, Son 11 5
7. PMgra= and proesest be astobiuhed to r Notes personnal prficeny into m ,aonof bayode bsl evenUt developed d maitain!d in accordanve wih NEI 12-06, Section 11.8.

S. The FLEX Wstei an basiswlwInhe mmINained inoal Staed*d R"EX ba*s documerf

9. Ecxistplant riIu p m*nor rc e .will.h NoS moded to m tav

- -* re ,OWhngsot the plat dfsign, physica bidngI and m e mos otures w"m not adversely inlooac "happroved FME stbrategies in ccda" with NEI 12-06, Section 11.8.

10. Appicabetrini ii gitiated tWi~oug toe Syswtemti Appoach sho to Tan (SAD) proess will bc r to t kiftnplsmetlo o FLEX._____
11. A owna has been s d between t*h* ite and the Pooled Slot ed Equipmet Invenor ComanVy to provide Phase 3 seivces AP ook desrobng tOe coordiwton tesglobtwen RNP and the Reinal Respons Cente w*A be developed. ______
12. To it the rew po-vwent opemtorti, an ofte Strategy Dieted three tnra of the steam supply ad regulhting valves will be modifed to operate on DC powr witwit be cmpixl o be, operated fm te Cor" Room.
13. Modcat*ion will be N-iMtiatedto harden the CST agns" d Strawty Deld and missles.,_____
14. n alt.nae CST-wil l d whichd wN be stiftWs

- "9ug!d and qaIfiD S to withtn the applcabl hazards. _____

15. LCV-1417A witbe converted mifroalopen alv toefed Stowra eed csed valve to rave a fatln to dce toe vlve Ina&.,e*

- manne f h andthry to prcueloss of MST wet(OLA .

Asesicl qualified preesure sorc capable of uplyn N Sare 16.

a hours of SOR P0 W oertIon weN be installd.

17. Sbtepecifi procedure and'o PSjs it heo developed usng Stile induatryuidance*to addess the critei in NEl 12-06, So* .IIA... .
18. A portble a pump will be procured aid puo noa dt Pr*e-tg Wq

____ onenat pump area.1 El-10

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-0087 18 Pam 0u ng cover sAeMet MWem I Open WtM-5ssipion ________

19. To meet N+O reqsuirent for Item 18 above, an additional StMte Deted pumnp wil be stored ina builin designedl per the, criteria of NE 1I2-MS Section 11.3_._
20. Valve,oW-20 to be mn e to include FLEX connections. Not Started
21. Anaditionalconnctionwill be povifdedfor&teAternatetate

, to satisfy prim and alternate cftr.

22. Ateeonneo*t*on will be ddd to theC AFW Pump Not StrW discherg. _
23. e niogn Moa tks r PORV) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> oopin Not Starsed Surat *o I relocated so a protected location.
24. iing cornmnet poa foith port" ftoge tank W St Nat

" wilb mdfied to include quickconnets_ _ _ _ _

2M. The SI accumumto lation valves will be e-ore ia NfStared sw*lcw El or E2 with portable diesel gew ato.

26. Modify the current 46V sww er E1 or E2 and existing Not Started dieWs enerat sto Include pofta dWsl generator connection points ner the exiin diesel genraor wombI of wAthin bet te eo ig diesel generator powe feefs and portable FLEX generator power feeds.
27. IfEl or E2 we u*aa-, th secondary hWo will eStrategyD utizin a mwnu tran , witich with portale gneraor connections that will be Installecd for as+/- "ng pump
28. To provide prmary ;ar altenate connection for portabl Not Started pumps, an alernate mechwial tee-cannection will be
29. MehaiR cal concions i wi beF adde4 direcay* both toe Not Sierded south and north SN headem to alloWaonnecton of a
30. N. portable pumps will tb procur*d*aid tored,ina rbust Pre-9a00i structre Ina protected location nrw Oh Intake strte in Straty Deleted

-.... suppo.of Item 29 above.

31. During odes 5 a" ,G,aportable pupwillM be usedi to take s from the RWOT or poabl tnker and doec uction p to thei SI header. ____-1
32. Primar and alternate mechanica FEX conecftio wWl be Not Stauted added to the Stheder.,
33. Drain vae (18) at the bae oxthe MRST wtoe modified W

___to algn i tthe standardized connection tpe _____

34 Srutuesto Pvieprotecto fteFEXeuMMn il o tre be buil prior to fth FLE kimllmen'-t- date.

35. Ili RNP ptocedhirseaid Proorams must -be deveoped to Not StaWe E1-11

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-0087 18Pa (including cover se)

Itm # ,pen em Osemlpleon.

address sorag structure requireme .to, deployment path equrment and FLEX oq mt qu relative to

___the hazards applicable to RNP.

38. Necessary mofca os will be m e to exsting SSC Not Started

_onne to facilitae RE(umnt FLEX deploymes

37. Necessary mion wIi b* m wdoting Not Started fenoes, structures or security parameter to facilitate flax A. 'he eupn %t 1o n points wilbe designed to Sr wihtnd ft !a!c" exteral zards.

W. . The mwen for cornecting t PhMa S generator will tb Not Sarted Ide~tfle based on the seeclto nt location of ft

_ geneor.

40. Low eakge Reactor Coolant Pm (CP) seals wil be Not Started
41. faden tf RWST against wi and ns s Strateye
42. Actual sized o tortob thmned al a later ime. .....
43. A onnme over-pressue ard ovr4.pwature analysis Comnpleted wi be peulromed. Calculation RNP-iWMECH-1877
44. The resolution o methd for SFP level determ .inon Isbeing Started addressed b e a ke inepon to Order 12-01.
45. To
  • SFP Ientory. a porIabl pup equipped wi Sintain Sar suction an dscae lies and compan hos connections

___wil be Available.

46. The alternate sre for SfP cooling is to povide Ww* No Started via Installed SFP piping w~ih Wrl reqt modifAtlon. Two Emergency Coolin Connectins (ECC) can be used for extMea fMln to robust pipn. These connetons wi be used with porable pumrp to draw water from diverse

_ _locations directly Wt fte pool.

47. Alternte* *ethods for powerig the 4"V MCC and 8 Strategy Deleted require Oeter bus modification to ace6mmodate t diesel generator connector, or the addition of a new diesel generator connection Integrated into vertical panel design allowing for full horigzontal bus amipecity.
48. Inst" --4emeta, nort-oste related bH~rle capable of Strategy Deleted Providing. an overall eigt how minimuom capacity (the currerit FLEX strategy indicates OW the addition f niew batteries Will bestmoet the eight hour recsd wt. Sinftce 'e Nlmpnea of hisnimodificallon chlene th ability to EI-12

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-007 181Pam inclding cover sheet Meom om*wt th two cycle monimnent early detaie enginern will evaluate whoth a betler deeg option

49. To retain SO wide r lmWaa level indicaton th*gho* an NoW Started evo, tor power srip for the Atrain SO wid rane lev ins trimentat-o will be moved to sithr the Aor B safety
50. AM*"cbl aroef of ft Twbine &"uildlgw be analysed or NotSare hardened to provide an adequa l, of assurance of "1. pfo rx d tte-Jicthet.. . randor

.VHAC Isneeded to beyond eht hrs. ...,

52. Emergecy plant gn modiostonM to ISNoMPOrt LED Not Started tecino y WIl be ntaWted tereby creasing the efletve

- of f battery packs

53. Ad " potable "nwil be pmmr to fctaltef No

- im on ofth FLEX teOn .

54. SItriS to ge te R sof cOmmuN nicaIs sysIems Not StAe wil be develope per NEI 12-OS Section 322(0).
55. ang studis WI be pformed inO rdanc wit NotNtRri RFI and NEI 124-01 to nsure adequate staff Is available to support, ans, opr FLEX eqpent Inthe tme anqd

_necessary.

5S. Phme2 battery copn w ir portable diesel genero Nost to powr the batterycwaers nd te Battery Room e*a fans inorder to remove ,rogengas ao mulain during

57. M erU swic tranu compatible for quik portb No Started diesel generato connection, wI be Insralled to dictly power the battery ,,are

, .., j W

58. P" nt cab andOw ra y WI be Wiae to make ca" Not.Started dpoment drt to te battery dUchagemrand Battery R.om gust fafnst feasible. _____
59. Existin instrument rackWibe moilld to anal Strategy Deleted monitorin of key pararraters using portabl equipmeL See Opeitem 72
80. Manualvtanser sWhes With the abWIhff tquck-cnnct to Not Started portal 5kW dese geneator wil be Installed to prOVide

____ventlatin to the Baftty Rooms.

61. A a" s of HVAC m for...eraTs!NT Stone, wilbe

.. perore be on ares #iwypffiw Itout.

coolig valalefor nde*nie cpin __________+ +

E1-13

U. S. Nuclear Reglatory Commission Enclosure to Serial RNP-RA/1340087 1 Ifr (includiuf covr sheet

62. Po tobefn bloweslg nert will be procured and uied to stowte proid forced coorweclon.
83. AIMP w acquire afupumpin ' OWh that can be N&

used to oxWO anrd delv fuel al.

64. Xn ansis Go eih fu convimpt r of alN ....

_p~ortabl gene- mequipe.nt wI b pidm.e..

65. fsons wl ben madefor anldelve* Aft
  • toRP 'NotSwat befor al onsile fuel isdelete .

6K. 6& d t PVRO tak wi be used ind*.emin Owe iiit m*imum f rate ad pffpin capacity wluired for bortMed wowtrmk.eup,

67. ft equiInt mna ncewilm be perfme in .... I accordaMne whth te rquirement of NEI 12-06, Section 11A 5
68. An wanayi wI be pekomed to dtemine the radiation Not State
89. An anaelysis wil be performed to determn the comodiie Not Started
70. Tmaportation *eint will be provided to move lam g NotM Stre skktV*he mo equipm*en td. ph htm tt.

,ded

71. AddkWWna or revised coniceptual swkethe wil be provided int Started future des as ngineeintpod "s ma.ture ftom

- conceptual detig to finald*!esdtn

72. Develop procedures, references, a tables to d"et*i key Started pararmetrs us a poft*

- M in the isrment racks.

The following Ae provides a sumrmay of nrw open items added to Oe Ovr ntWgaed

73. EA-12-040, eqires that statu reports be subm91ittd CcswilWI an six monyth kftevole folowing ftheubmita of fte Owera New Open Item Intgraed Plan, urd co fmplac Isachelve. Ptovide fth six 3 Will tra& fth monthm status, report to lansingf for processIng.2/81Upte
74. Implemet the RNP intgroatd plan for Order Eh-12-049 4so$atd stated In fth sumal. If plans chang, ensur tha the changs we reflected Infuture six Month status. re owtta are requird to be submtte per the Order. Ensure Open, Items listed InRNP-RW13-0022 (iLe., $68897), ape 78.- Movefi existing %'WC bnetrlads to fth W invsto and Not Started

___disconnect the *C"inuerw from the "A Station Battey.______

79. Revise SAM and pothe RNP Emergenc procedures to Saitdw E1-14

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/13-0087 18 Pages (includin cover sheet) hncude FLEX responme and neted setvot.

Note; This actvity / sope does not hine df o#er se p*edura they w be revsed as pet of M&

OWs Imp. imn. Mod mtesnchdsk~

OdlcWeMunste and is ip-W Suiw*p~

huoue * [* 6

,..Zthnt Enseue of this Istrumemn is aomOus for in nw 0

Ernur no c~dlt 880 okoubt we mmoved fopo Whe w kmk "dk~eVoui r

4-e 1.w DEnOrgLAN OtWde Modifyin U I

I E1-15

U. S. Nucler Regulatory Commission Enclosure to Serial RNP-RA/ 3-0087 18 Pages (including cover sheet)

Atls*Fw -hm 3

Figure3, FME Connectio Locatios - kWmechai;al - Core Coo"ki - 80 Malem4 (Open bte 71)

/11 ANN /'V w

~A 'i.

El-16