View source for RNP-RA/13-0080, Response to NRC Request for Additional Information Regarding Overall Integrated Plan Submitted in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation

{{Adams
| number = ML13233A313
| issue date = 08/08/2013
| title = Response to NRC Request for Additional Information Regarding Overall Integrated Plan Submitted in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation
| author name = Gideon W
| author affiliation = Duke Energy Carolinas, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000261
| license number = DPR-023
| contact person = 
| case reference number = EA-12-051, RNP-RA/13-0080
| document type = Letter type:RNP
| page count = 11
| project = 
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter:ENERGY.
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10 CFR 50.4 Soft RN       N13.040 AUG 0 8 2013 ATMN- Document C.0"o Ds sates -
UnWe                ePapkfy Com*Mssn WaSWngton,fp DC 20656G-Mi K B.ROBISON STEAM ELECMhC PLANT, UNIT NO. 2 DOCKETNO. O IRENEWEDUMISE NO. DPR-23 mwowas
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@VORALL NI            11MPLAN         IUTD IviNoMM94I" M1            S O Rehemnoes I. LetW re  fr enam Wadre to te U.S. Nudcer Regulaty ComfmsIon (Se . .RA-134)02), C00610 POW &LOWh COniWWy OvWW kftrasd Phlansh ReSpon to Marh12, 1Z 10oCoin"el Ord Modr6t Lnse iW R                       to R e f~rReM We pentFuelbd   Po Inlw ]rw'nnao (Cdo M~v~ EA.12-051), dated Fbupry 28,2013, ADAMS Accession Number ML308SAO08
: 2. NRC Liter fom E.j. Leeds to An Pow Reactor Licensees d Holders of Cn uion Pemi InActve or Doened Satus, lanc of Ordlrto Moxiy Lkwn Regard to RAWe Spen rW Poal         w"rwm, d ted Mrch 12,2012, ADAMS Accession Number MLI2064A79
: 3. NEI 12.02 lnWty Gukbim k CoMwpne          .h   NRC Oer EA. 12-05 1, -To A*&y Lcense wth R#gWd to Refable Spern Fuel PWo/,                   -Revision 1, doted AUgust 2012, ADAM$ AcpsionNumber ML12240A307
: 4. NRt Inhwim SiGuidane JNSG4.2,1203, Gopbno w*h Oder EA-12051, Orderto MIW* iketwes, W Rog&d to Ru wfmt ReM abl Speit Fuol Poo h/nthff tin, ReviIsin 0, dated August 29,2012, ADAMS Ac*esslon Number ML12221A339 S. NRC Leer *m Arsacl T.Buoh Colon (USNRC) to Pandy OGlson (Carolina Powe &
Lig Company&#xfd; Reqes for Additional Information Regawd Overal Ingrmated Plan In Resne to the Commission Order ModftI       Licenes with Regard to Spent Fuel Pool Intuwme      on (Order Number EA-12-0M), dated July 11, 2013, ADAMS Accession Number ML13189A056 o0!i

Uniftd S$ates Nucle Regulatocy Covmission Serl RNP-RA/13-000 Page2 of 2 Ladles and Genlimen:
By letlr dated Fdeuary 28, 2013 (i.e., Reference 1), Duk Energy Prgree Inc., formerly known as Caroline Power & LiOM Company, submilted an Oeall Inleg             Plan in response to the Mardh 12,2012, Commission Order modifying licenees wh regard to requirements for reliable Spent Fuel Pool (SFP) Inmsumerntaion (I 0., Reforeme 2) for the H. B. Robinson Steam Electc Plant (,IRSEP), Unit No. 2. Furthw, ft sta endorsed NEI 12-02 (i.e.. Reference 3),
with exceptions as documenited' In*inte     Staff Guidance (., Reference 4)
On July 11, 2013, (Le., Refteence 5), te NRC pvde          requa for adtonal ionnaton (RAI)
* ing       refned Overallnteraed Pln. in adm, forany partaote In          th is not mallabie wii the 30.day response period for the RA, the NRC sked IIURSEP to provide fth dabe the informiation wouldl be submitted. The response to the NRC There wno rg, r7y                             i i sum        . f yu hae
                                                                      .e any quesions regar isng ti s         ,i Iet(843)  c       l. R.                    eMI1320.
I declare under pernaty of perJury that te foreog is       and correct EecutedOn: A, W.R. Gideon Sie Vie Ptesident WRG/cac Enclosure cc:      Wr V.M.MoCree, NRC, Region II Ms. A-T.Silloch-Colon, NRC Project Menager, NRR NRC Resident: Inspector, HBRSEP, Unit No. 2

U.S. Nuclu "i"y       Camnmion Enclosur to Sods RNP.RNI3-0080 9 Pa" (mcdfng     morosee)
IMTEORATO LIC WSESK PLA SIIITTEof   REP DMINSO FOR R *T TO RESJuIREMSNT  WHS OIS         ORDER LJASILE SPEN  RU.NOPOOLVI WillGO WRUIUETmATIOO (ORDER WIME EA.124S1)

U.S.Nuclear Regulatory Commission Enclosure to Serial RNPfI3.000 Page 2 of povidethe*      oung
: a. For level 1. spec    how he identille elevation repremsen the HIGHER of the two points desculbed Inthe NEI 12.02 guldeno. for this levet.
: b. A clearly labeled seltch depkti the elevation view of the proposed typical muning aranmenwt for the poronm d inskumet chne consisting d permanent measurment chan equipment (e6., fbsed level senwsor           ad iln g weis, and mounrtin bts).
intdicat on $is se0tch ife datii valuwe rmpreentin Level 1, Level 2. and Level 3 as wen as #a top of go fue racks ndit on tis ktch Vi portion of the level sensor measuremen range thatts snittv to masuremen of the fuel pod lev. wih respect to the Level 1, Level 2, and Leval 3 ddiuM points.
W4$TRUMENT CHANNEL DESIGN OVERVIEW/ BACKOROUND The K. S. Robinson new wide range Spent Fuel Pool (SFP) level                   t     wA*consst of two permnenly   1  -fted Instetmst chnnels. The spti*lly aeperated channel wibe ue'd to mon*t            te SFP wow level over the co~inous span from norml operating down to the l              of the highest point of any fuel rack. Per NEI 12-02 guidance, neither of th#ed              requires, accs to the SFP ama during a Ss4 Desg Smals Event (9oEM).
Each Instrument channel wll uWas the Through Ar Radar technology. which has a wave gulded pipe and receivg horn located in the SFP me. The orfy part. of the meIsurement channel in the pool radiation         oronet are the metallic wavegulds and horn, which are not susceptible to th expected levels of raddlton. The eectronlis will be located In an aee that does not exced their 1x10 red analyzed limit. There Is no portion of the Through Air Radw level sensor that contacts the SFP water, nor is there any connection to the pool lner.
Each channel will have a becik-up bettery and shall provide Main Control Room (MCR) Wvel m*ont capability.
: a. H. B. Robinson evaluated the higher of the two points dewribed In the NEI 12-02 guidance, as follows:
o    The l"     at which re*liabl suction los occurs due to uncovering of the coolant inlet pipe, weir or v   um breaker (depein on the dssign), or o The level at which the water heigt assuming saturaed conditions, above the cenln of the cooling pump suction provides the required not positive suction head specified by the pump mauatrror engineering analyis.

U.S. Nucler ROg      o Comm       on Enclosu to Seri" RNP-RA13-000 Pae3of9 Bsedon analts (Ccweon R AP-IWCH-16?9, Reso 0)
A. The Wevl at whi~h re    le suctm e occs due to uncovi        of the coat l p*pe    is at elsation 270.0 feet.
: 6. The Wl at wh~ thwar h               aseng satated conditmi               oemrke of boete ost he coon pum suctio         ovmid te reuiW net pos     suction heed at nrmal lowt of 2100 gpm is at elevaton 2726 fe*et Terfor, H~SRlEP
* t Lev I to be at 27.6et ele       . Th isbsedm on the fo*A"n:
: 1. Spent fuel pool waw is onsv*vy assum l to be sotraed water.
: 2. Th.     ,Pcooin pump sution ip etert evaton Is269 feet 8 ces Wr Dr              g 19=074, fevbso     9. Itwo is a common scon t bwch to two psal                 parts
          **Oft- 000 pum       p Oft pumps A an &. By, iopeon of Drnw~n G0-               274,.
ReiIdon 9, toe longestpehis to the AK V".
: 3. d           poW*vctin head (NPSM) wM be asurm at raW syMtm ormtse as Meut bng M wotr is 2.6 e abomv eScton pipe Me or Oeato 2. fee The Februay 26,-2013 Overallospotegae Plen (01P) aemltW spcfedth SF Level Iat "apradmty 273 fe           vtio-. SWd oan       *eab idnaomon, SFP Lev I s revIs to 272.6 feet elvto.
: b. Bee skch n the folong pos.

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U.S. Nuclear Regulatory Commission Enclosure to Serial RNP-RNI3-M Page SolO Provide a learly labeled sketch or marked-up plant drawing of the plan view of the SFP am, dep*ting the SFP insde dmensrion, te piwnnd                      &#xfd;cPlaoMen of the primary and backup SFP soensors, and the proposed routing of lhe cables tat wi extend ftom h sensors towrd the location of the local electronics abets and reed-oudsplay devices In te main control rom or amrate acessible locaton.
Ikformetoi       is not aveleble win the *day response period for Oth RA. Duke Energy anticpae ubnhhng a response to R-2 inthe Febuary 2014, Six Nth Statu Report for the ImplementI of Order EA-12-061.
Prow"deOwfoUA*Q:
: a. The     design crilris       will be     to estimate inludin     stdc  Weh tlhatlods   anusdual   loads the  totalWadn Descre    the rmtodoog       tha wIdevk*(
on the mountig      be used to eate e toW loading, inclv of design basis                              sismdi loads and the hydrynmic lo              that could result from pool slohing or oh e                 that could accom n such eismic
: b. Adescriptlim o the manner Inwhich the Wee sensor (and sftn well, f approprate) wil be atcheod to th refueling foor andor o support structures for each planned point of attahment of ft probe assembly. Indicate ina schematic the portion of th level sensor thatWwm m N poi of au mnt for mo                                ing or electrical innections.
: a. A dsorlptlcn of te mnne by whic the meh.ical connctis wi aa                              the level stme*nt to pemwnetSFP structurs so as            Support the le srenor asmlw.
Rnorw      to Isnot availble Witin the 30-day response period for this RAI. Duke Energy anticipates response to RAWI In the February 2014, Six Month Status Report for the Implemeti amin, ofOdr             12-01.,
Provide the foilowtrg:
: a. A desciton~ of toe specific method or combina~tion of methods you intend to apply to demonstrate teelabltyo the VI-lperanniywl"WN installedf equipment under BeyWOnd-esgn-Ba10sis(m)arntle temperatur, humidty, shock, vibration, and radiation conditions.
: b. Adescription of the tesin and/or analyses that wil be conducted to provilde asurane OWa thf equpment WIN perform reliably under the worst-casecredible design basis loadin at the location             he equipmert wil be mounted. Include a discussion of this seismic there relablity dem*oftrafton as It applies to a) the level sensor mounted In the SFP area, and b) aM control boxes, elcroiso reed-out and re-transm Itting devices that wil be employed to convey the lee information from th lol sesor     m to'the            operat or emergency respoers.

U.S. wcer Rguory C mission Enclour to Serial f               13.oo8o Pae a of 9
: c. &#xfd;A description of theo spoclfc metho or combiation of metlods that will be used to confirm the reliablity of the permanent    y in*t*lled equipmnt such that tlwin a seimnic event the Instrument will mintain Its requlred ccuracy.
information Is'not amalele_1 within the 304ey response period for this RAI. Duke Energy antcpae s itting &reIponse to RAJ-4 in fte 1Fney 2014, Six Month Staus RIpt for the pl n on of Order EA-12-061.
Provide the kolowkvg
: a. Adeecription of how the two chamnel. of the proposed le1 meurem system Ineamh pod meet this reqiremen so               the* potential for a comon cmume eent to advesely
                 ~ both cannels Isminimizd to the, e00 praticable.
: b. F~urt nftn deein the design                       , nd Instalation o* each *evi measurment sysite, coneistngof evel nmor electronics, caling, and reedout devlw           . Address how independenoe of these omonenf of the prmawy ad beck-up channels is achee through the appcao of independent power sourome. physical and                 "setswpation, 1"indpedec Of Signal een to the, loaions) of the, readout devicess, and the idendneo the dislays.
Information*s -not,aawllabbs            the SO-ey issponse period for Ofth     RW.* Duke Energy aintiip.tes submlitng a resose toRAI-5 i thefbruary 2014, 8ix Month Status Report for the Implementatlon of Orde EA-2-0W1, Provide t*ne      owin a1.      Adcrpinof the e~cleticl altenate currn power sources and capacitis for the Wriwy end backup channels
: b.       Ifthe levkl me              chnels rwe to be powervd tlrough a battery sysemm (elther div*c* or through an U~nintequtiW Power Supply). please,provide the design criteria that will be applied to size the battery Ina anner that ensure, with mwgin, #tht the chaW wil be *vahaW to run reliably and continuously following ft oset of the 808 event for the nm duraon needed. omnsistent with the plWa milstion st0ategles for 808 eernal evnts (Order EA-12-049).
fbesponee Io RAI-4:
Information Is not vakble within the 30day response period for this RAI. Duke Energy anticipates submiWng a response to RAI.4 in the February 2014, Six Month Status Report for the Implementation of Order EA-12-051.

U.S.Nuclear Regulatimy CoWMmiso Encowur to Sera NP4 I3-00S0 Page?o of RA&I.       ---- kvt Provide the fo*win:
: a. An stimat of the expected inkunmeit channel *c         y       mn (e.g., inpwc of spa) under both a) rmmadSPP loe cc dis (a may Leel I or higher) and b) at the OS coniinkm (I.e., radiation, iemipeakt, humidity, poet-seismic and poetahock conditions thatwoul bw pr           fthe SFP eve woos t the Leve 2 and LewI 3cdatum
                                               #n
: b. A description of thw ethd g thatW will be used for determining the nmmdmm allowed deviation *rm gosuent e            chne design cucy tha will to emplcye under norml operating conditions a oan. acoopteme orioeion for a calibration procedure ,to flag o operators and to %slia          that the cdha requires adjuAment to wthin the nomal
                -mo design accucy.
Reponsm to RAIM7 kVormaton Isnot mav*abl witithhe304    E        rspns period for fthi 1A.
me                         Duke Energy anticipates m     nga response to RAI- innthe Februawy2014, Six Month $tatus Report     t        idmplement of Order EA-12-,.O.
Provtde the fookwi:
: a. A descriptin of the capa06"t and prvisions the piroposed level sensing quipment wMR have to enable periodic
                                  -t-stin and culbrallon, including howm i capability on             t equipvmet to be tested lns*W.
: b. Adeasripton of how such testn and calib*tin w0il enl th c              of regular chnnel chcdks of each independent dhne agnt the other, and agans*t any other permanently-Installed $FP level isrmnain
: c. A descripton of how calti tet and functioned checks will be perormed an the freluency at w~h they will be concded. Discs how the suell                           will be
: d. Adescioption of,       preven 11at ~w  ane ancetas l    are requird to be peformed during nomal opermtiom, and the planned maxium survellance.
Inft         Is not avalable wih the 30.day response perlod for ftis RAI. Duke Energy antcpates submltting a respone to RAt- Inth Fseony 2014, Six Month Stalus ReW for fth            , Implemeta of Order EA-12-O.1.

U.S.Nuclear Regulatory Commission Enclosur to Seiml RNP-RNA13004 0 paoe 6 of 9 tam mmmoml Provide the folowing:
: a. The speific loctio for the primaery and backup Instrument channel display.
: b. Since both the pritmary and backup diplay locations we not in the main control room, plemme provide a deecription of li location for the prmary and backup displays includng prmaory and alternate roumt evaluaon, habitabi*ty at display lootion(s), continual meouroe aniabliftv for persone responswl to pwroptoy read dieplays, and provsions for communv-Lionsw with decision makers fore        ft varu SFP drain down scenarlos anc
               -~m even*
: c. The reasons justlfn why the slocions soeleced wl0 enable the Information from these Instruments to be cormidered "pmpy mccei.ble Iinclxude consideration of various drain-downmn~arios.
n~imdam voormloo.
Ination Isnot eavalle within the 304ay                  p eod sn for Is RAeI. Duke Energy anltcipates sub     ng a response to RAI-9 hi the Februay 2014,8k Month Status Repot for the implmenttin of Order EA12451.
Providefth:lowing.
: a. A ist of the opent (both normal ad abnorma response) procedures, calblbrtot procedureis, mainten procedures, and inmpeciuoni poceur that wi be dovelop for u     of the SFP istrmewnt      in aanmnner that addrees the order equiremenmt.
: b. Abri description d the pc*if t c0hnicalobc              to be ac*ieved w"tin each pmrockdr.
Uyour plan incomrporaes ft ue of porta spent fuel eve monift componmts, please Include a description of the objectile to be achievd wit regard to the storage locati and provisions for Installation o the po*ritle oomponents when needed.
Information Isnot wavalable wViti the 30kda response period for this RAI. Duke Energ an*mtipts submittin a reeponse to RAI-10 In#th February 2014,8Si Month Status Report for the' Impleentation of Order EA-12-051.
Provide the fbowkn:
: a. Further Wnformation describit the mintene             end testing progra fth lNs will t sand Implement to nsure hat reu*a                  ng and calibration Is performed and erifid by Inspection and audit to deons*tl          confomance with design and system readinems req*iemft. Include a description of your plans for ensuing that necessary channel checks, functonal tests, perodic calibration, end maintenance will be conducted for the lee measumwent system ndt uppo
: b. A description of how the guidance InNEI 12-02 Section 4.3 mgarding compensato            lracons for one or both nortnctioning camela wil be addreo        d.
: c. A dosacption of the cvom            toiy actions to be taken In the vient that ore of  *th strument cha*nlen   cannot be restored to functional   iatus wthin 90 days.

U.S. Nudge Ropg     y Commso Enlosr to Sea RP-RNAI3-0060 Page 9of 9 ResponseI RADI1:
nfbmaton Isnot avNebl within the 30-dy response pst for this RI. Duke Energy antcptes submlwgt a respes to RAI-I 1 Inte FOeray 2014, Six Month Stb Report for the IplWemnostaion of Order EA-12-06i.}}