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| issue date = 10/03/1985
| issue date = 10/03/1985
| title = Suppls Util 850904 Ltr Re Resolution of Fire Protection Concerns.Listed Replacement Pages Re Sprinkler Protection for Control Structure Elevation & Shutdown Paths Encl
| title = Suppls Util 850904 Ltr Re Resolution of Fire Protection Concerns.Listed Replacement Pages Re Sprinkler Protection for Control Structure Elevation & Shutdown Paths Encl
| author name = KEISER H W
| author name = Keiser H
| author affiliation = PENNSYLVANIA POWER & LIGHT CO.
| author affiliation = PENNSYLVANIA POWER & LIGHT CO.
| addressee name = BUTLER W R
| addressee name = Butler W
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000387, 05000388
| docket = 05000387, 05000388
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:'REGULATOR INFORMATION DISTRIBUTION SSTEM(RIDS)ACCESSION'BR o8510.080410, OOC~DATE!65/10/03NOTARIZED; NOFACIL:50387Susquehanna SteamElectricStationiUnitiiPennsylva 50386Susquehanna SteamElectricStationiUnit2'<Pennsylva AUTHBYNAMEAUTHORAFFILIATION KEISER<H,W.
{{#Wiki_filter:'
Pennsylvania Power8'ightCo~RECIP~NAMKlRECIPIENT AFFILXATION BUTLERgW~RiLicensing Branch2
REGULATOR   INFORMATION DISTRIBUTION                     S  STEM        (RIDS)
ACCESSION'BR o 8510.080410,         OOC   DATE!               65/10/03    NOTARIZED;     NO                cocKET e FACIL:50 387 Susquehanna        Steam
                                          ~
Electric Stationi Unit                    ii  Pennsylva          05000387 50 386 Susquehanna BYNAME                    Steam    Electric Stationi Unit                    2'< Pennsylva           05000388 AUTH                  AUTHOR  AFFILIATION KEISER<H,W.           Pennsylvania     Power                8'ight  Co ~
RECIP ~ NAMKl          RECIPIENT AFFILXATION BUTLERgW ~ Ri            Licensing Branch                    2


==SUBJECT:==
==SUBJECT:==
Supplsuti]650904.ltrreresolution offire~protection concerns.
Suppls      uti] 650904 .ltr re resolution of fire~ protection concerns. Listed replacement pages- re sprinkler protection for control structure elevation 8 shutdown paths SIZE; encl'ISTRIBUTI N  CODE: A0060    COPIES RECEIVED:L~TR.                       ENCL TITI E: OR  Submittal: Fire Prote'ction NOTES: 1cy  NMSS/FCAF/PM'PDR 2cys                                                                          05000387 07/17/62 Transcripts'L:
Listedreplacement pages-resprinkler protection forcontrolstructure elevation 8shutdownpathsencl'ISTRIBUTI NCODE:A0060COPIESRECEIVED:L~TR.
icy NMSS/FCAF/PM'PDR 2cys Transcripts;                                                             05000386 OLe03/23/84 RECIPIENT          COPIES                            RECIPIENT              COPIES ID CODE/NAME        LTTR ENCL                      ID CODE/NAME           LTTR ENCL' NRR  LB2  BC    01      3      3 INTERNAL: ACRS              11      3      3                  ADM/LFMB                                  0 ELD/HDS4                          0                  IE NHITNEYIL                            1 1 NRR STANGrJ      07      2.'                         NRR  &#xc3;ERMEILiJ06                        1 0 NRR/DE/CEB      09'4    2      2                  NRR/DL DIR                              1 1 1      1                  RGN1                                    1 1 EXTERNAL: 24X                                                    LPDR            03 NRC PDR          02"                                 NSIC            05                    1 1 NOTES:
ENCLSIZE;TITIE:ORSubmittal:
TOTAL NUMBER    OF COPIES REQUIRED: LTTR                        25  ENCL    22
FireProte'ction NOTES:1cyNMSS/FCAF/PM'PDR 2cysTranscripts'L:
07/17/62icyNMSS/FCAF/PM'PDR 2cysTranscripts; OLe03/23/84 cocKETe05000387050003880500038705000386RECIPIENT IDCODE/NAME NRRLB2BC01INTERNAL:
ACRS11ELD/HDS4NRRSTANGrJ07NRR/DE/CEB 09'4COPIESLTTRENCL333302.'2211RECIPIENT IDCODE/NAME ADM/LFMBIENHITNEYILNRR&#xc3;ERMEILiJ06NRR/DLDIRRGN1COPIESLTTRENCL'011101111EXTERNAL:
24XNRCPDRNOTES:02"LPDRNSIC030511TOTALNUMBEROFCOPIESREQUIRED:
LTTR25ENCL22 Pennsylvania Power8LightCompanyTwoNorthNinthStreet~Allentown, PA18101~215/770.5151 HaroldW.KeiserVicePresident-Nuclear Operations 215/770-7502 OCTO31985DirectorofNuclearReactorRegulation Attention:
Dr.W.R.ButlerLicensing BranchNo.2DivisionofLicensing U.S.NuclearRegulatory Commission Washington, D.C.20555SUSQUEHANNA STEAMELECTRICSTATIONRESOLUTION OFFIREPROTECTION CONCERNSER100450FILE841-2,143PLA-2541DocketNos.50-38750-388


==DearDr.Butler:==
Pennsylvania Power              8  Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/770.5151 Harold W. Keiser Vice President-Nuclear Operations 21 5/770-7502 OCT O3 1985 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler Licensing Branch No.         2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION RESOLUTION OF FIRE PROTECTION CONCERNS ER 100450                        FILE 841-2, 143                                  Docket Nos. 50-387 PLA-2541                                                                                        50-388
Thislettersupplements PLA-2529, datedSeptember 4,1985.Enclosedarereplacement pagesasfollows:~PaePage3ofConcern81DescritionofChaneReviseSection2.2toclarifyuseofnon-rated boundaries Page2ofRequest/f6inAppendixAtoConcern//1Figure6ofAppendixBtoConcern81Sprinkler protection fortheControlStructure Elevation 754'-0"supportsteelispartialprotection Shutdownpaths364wereaddedtozone1-6CFigure9ofAppendixBtoConcernPlShutdownpaths364wereaddedtozone1-6CFigure10ofAppendixBtoConcern81Shutdownpaths3&4wereaddedtozone1-6CFigure11ofAppendixBtoConcernlI1Addedtheamountofcombustible loadingforzone1-5C"FtaR.OA80<>0"8Seoo3I8510P"ADOCgOSOOO3.(lIDR(OO4 Qg081985Page2SSESPLA-2541ER100450File841-2,143Dr.W.R.Butler~PaeDescritionofChanePage3toAttachment 2ofAppendixBtoConcern//1Addednotestopageregarding thecontrolstructure Theabovechangesareeditorial clarifications whichdonotaffecttheconclusions oftheanalysis.
Shouldyouhaveanyquestions pleasecontactus.Verytrulyyours,H.W.KeiserVicePresident-Nuclear Operations cc:M.J.Campagnone
-NRCR.H.Jacobs-NRC iii)Identifying onacasebycasethespecificbarriercomponents whicharenotratedandproviding ajustification fortheiruse.Anyadditional fireratedprotection requiredasaresultofthisredefinition willbeinaccordance with10CFR50AppendixR,SectionIII.G.2.2OtherSafetyRelatedBuildings Themethodology usedintheControlStructure, theDieselGenerator buildings andtheESSWpumphouse wassomewhatdifferent sincethemajorityofthefirezoneboundaries arefireratedand,asaresult,ourfirezoneboundaries areequivalent tofireareaboundaries.
Forthesebuildings eachfirezonewasreviewedforitssafeshutdowndivision.
Firezoneshavingacommonsafeshutdowndivisionweregroupedintofireareas.Eachfireareawasreviewedtoassurethatallofitsboundaries werefireratedconstruction, orifanon-rated boundarywasacceptable.


==3.0 ASSUMPTIONS==
==Dear Dr.     Butler:==
&NRCGUIDANCE3.1Theanalysiswasperformed inaccordance withthefollowing NRCguidance:
 
a.10CFR50,AppendixRSectionIII.G.b.c~GenericLett'ers83-33and85-01.INRClettertoPP&LdatedApril18,1985whichstates:"Thereassessment ofnon-rated construction shouldbeinaccordance withguidancepresented atthesiteaudit.Thatis,toprovidereasonable assurance thatfirepropagation willnotoccurbeyondnon-fire-rated zoneboundaries, theboundaries shouldbeupgraded, tobecontinuous barrierswithafireratingsufficient towithstand theeffectsofafireinvolving in-situandtransient combustibles, withconservative margin.Ifboundaryconstruction isnotupgraded, yourreassessment shouldassumethatfirespreadwilloccurintothenextmostimmediate firezone(horizontally and/orvertically)."
This    letter supplements PLA-2529, dated September 4, 1985.                       Enclosed are replacement pages as follows:
3.2Theanalysisperformed wasbasedonthefollowing assumptions:
                    ~Pa  e                                        Descri tion of      Chan e Page 3  of Concern    81                            Revise Section 2.2 to clarify use of non-rated boundaries Page 2 of Request /f6 in                               Sprinkler protection for the Appendix A to Concern //1                              Control Structure Elevation 754'-0" support steel is partial protection Figure  6  of Appendix    B  to                    Shutdown paths 3 6 4 were Concern 81                                            added to zone 1-6C Figure  9  of Appendix    B  to                    Shutdown paths 3 6 4 were Concern Pl                                            added to zone 1-6C Figure  10  of Appendix      B  to                    Shutdown paths 3 & 4 were Concern 81                                            added to zone 1-6C Figure  11  of Appendix      B  to                    Added the amount of combustible Concern lI1                                            loading for zone 1-5C I
aOTheconcreteblockorreinforced concreteusedintheconstruction ofwalls,floorsandceilingsareacceptable asbeingfirerated.,b.Evaluation ofthefireratingofexistingdoorsbyFactoryMutualResearchisacceptable totheNRCstaff.C~Theunprotected structural steelwillbeshowntobeacceptable usingamethodology acceptable totheNRC.w3
      " 851 0P FtaR ".OA80<>0 ADOCg "8Seoo3                                                                      (OO4 OSOOO3          .
~h~pPPDNKP',QP1+~,'rP1hPfP'~tC FIREZONEBELOW/FIREZONEABOVESPRINKLER PROTECTION BELOWSTRUCTURAL STEELREQUESTNO.6PAGE2COMBUSTIBLE LOADINGUnit82-ReactorBuilding(Cont.)2-3B-N/2-4A-S 2-3B-N/2-4G 2-3B-W/2-4C 2-3B-W/2-4D 2-4A-S/2-5A-W 2-4A-W/2-5A-N 2-4A-W/2-5A-W 2-4G/2-5B 2-4A-W/2-5E 2-4A-W/2-5F 2-4A-W/2-5G 2-5A-S/2-6A 2-5C/2-6A 2-6A/2-4G YesYesYesYesYesYesYesNoYesYesYesYesNoNo16min16min16min16min15min15min15min4min15min15min15min6min6min6minControlStructure Elevation 754'-0SupportSteelJUSTIFICATION:
(  l I DR
Yes(Part)62minUnit81andI/2ReactorBuildings:
 
ltAllfirezoneshavesprinkler protection belowtheexposedstructural steel'xcept forFireZonesl-lE,1-1F,2-1E,2-1F2-4G,2-5Cand2-6A.Inthesefirezonesthemaximumcombustible ratingis18minutes,andminimaltransient combustibles areexpected.
Page 2          SSES        PLA-2541 Qg 08    1985                                          ER 100450  File 841-2, 143 Dr. W. R. Butler
Finally,thein-situcombustibles inthesefirezonesaregenerally locatedneartheflooratadistancefromwherethestructural steelformingthefireareabarrierislocated.CONTROLSTRUCTURE:
                  ~Pa e                              Descri tion of  Chan e Page 3  to Attachment 2 of                  Added notes  to page regarding Appendix  B to Concern //1                  the control structure The above changes    are editorial  clarifications  which do not  affect the conclusions of the analysis.
Automatic detection andprotection isprovidedbelowtheexposedstructural steel.Themajorityofthecombustibles intheareabelowtheexposedstructural steelarecables.Themajorityofthecablesarelocatedeitherbelowtheraised(computer type)floorintheControlRoomorin2hourfireratedcablechasesonthenorthandsouthwallsofthecontrolstructure whereonlyonestructural memberiseffected.
Should you have any questions please contact us.
Thereisapproximately 20feetbetweentheraisedcomputerfloorandtheexposedstructural steelsupporting elevation 754'-0.Finally,theControlRoomcomprises themajorityoftheareabeneaththissteelanditiscontinually staffed.EXEMPTION REUEST:Exposedstructural steelsupporting theidentified fireareabarriersisacceptable anddoesnotrequ9.refireproofing.
Very  truly yours, H. W. Keiser Vice President-Nuclear    Operations cc:  M. J. Campagnone  NRC R. H. Jacobs  NRC
djk/h188c3:del CONTROLSTRUCTURE FIREAREACS-1CS-2CS-3CS-4CS-5CS-6CS-7CS-8CS9k*CS-10~*CS-11CS-12CS-13CS-14CS-15CS-16CS-17CS-18CS-19CS-20CS-21CS-22CS-23CS-24CS-25CS-26CS-27CS-28FIREZONE(S)0-21B,029A 0-22B,0-29C,D0-21A,0-22A,0-22C,0-23,0-24A-G,0-25A,E0-24I,L0-24K0-24J,0-25B,0-26B,S,0-27F,0-28P0-24L,M,0-25C,D,0-26C,D,0-26T,V,0-27G,H,0-28Q,R0-28S0-26A,E-N,P,R 0-27A-E0-28ASubzoneI(RoomC-613)0-28C0-28E0-28G0-28H0-28J0-28BSubzoneI(RoomC-604)0-28M0-28N0-28ASubzoneII(RoomsC-611,C-612)0-28T0-28D0-28Fn0-28BSubzoneII(Rooms'C-605,C-606)0-28I0-28K0-28L0-29B,0-30A,B**Thesefirezonescontainnosafeshutdowncablesandfunctionasastbufferiesfirezone**Thefloor/ceiling betweenFireAreaCS-9andCS-10hasunprotected supportsteel.SeeExemption RequestNumber6.tag/h253c3:del 4~~>.~at.COMOQlLL2.-1I.Ql(yy<~N/AOelg~z=si'/O<Ozg2-46Q~Q4l-l47l:QIQi~s/Og/'4G010>,O+/04 igIIII'AI'1-4/9Ql.I-IZQIO<Q~Q4~NAI~2GB-QIQ<Q>Q4~s2-4FsQaA~2-4FQIQ<SQ4~N/A0-HOI02P204NOI!IE.it/"8QlI~l-6)FP0~04~NIA1-QlQ2I~I4F10204~I-IS'lQiQ~Q4.i.~le0>~~e0~2-4EQ!Q<Q>04I~Z-I.CQlQ>Q<I1-2l'~Q4~NIA~I-IOQIQ<O>Q40>O~1-13'/020~04
 
~A~N/AQa4lA2'02"13'IQ>Q>Q4.'~N/AIOBAYS52"t-0=2,70-0"LQXUzC)aXJIZ,Q57.4:::3G.34.53'l.5.=.30.52'027.5FLOQPPLANeEL.175-IER-ER-SCALE-DATE-DRAWN-23.520.C0;077/5NO.DATEER.DECIMALREVISIONRIACTIONAL LOCATIONCODECH.BYAPPROVEDCHECKED-LEADER-APPR'D.APPR'D.DESCRIPTION PINN$Yl.VANIAPOND.RaLIGHTS(ONPAHYALLENTOWN, PA.APPROVEDI
iii) Identifying    on a case by components which are not case the rated  and specific barrier providing  a justification for their      use.
/~J~IK+gl"4p'lV,I~$'L l'I1ttt86806%CFS88EBCQHS8680MC5586806588KlCRKR8IHIKEY)08HIKEY8608H'/8680D880EJ%%88Kl%X>68~/%%9898+r~m$V(es4sssosi~me
Any  additional  fire  rated protection required as a result of this redefinition    will be in    accordance    with  10CFR50 Appendix R, Section    III.G.
~rII4'~,h~'Ii~~ppQ'9t(ia,~1p,7+@id~~'t.vEgop>af
2.2   Other Safety Related Buildings The methodology used in the Control Structure, the Diesel Generator buildings and the ESSW pumphouse was somewhat different since the majority of the    fire  zone boundaries are      fire  rated and, as a result, our fire zone boundaries are equivalent to fire area boundaries. For these buildings each            fire zone was reviewed for its  safe shutdown division. Fire zones having a common safe shutdown division were grouped into          fire  areas. Each fire area was reviewed to assure that    all of its boundaries were fire rated construction, or    if a  non-rated    boundary was acceptable.
/o/C~~CZ5869055[a~a8690K~>%IS9KH/KR89K)g][la~aCKS8660M/$K55986OHHCKRISe~~SSSS8690H/890H$&RQ~586 rl,P)p,qvt4t.,Jer7,I;l,
3.0 ASSUMPTIONS & NRC GUIDANCE 3.1  The  analysis  was performed    in  accordance with the following    NRC guidance:
~.4r'A-.872-8'r84b'-3'L-84b!-J'N.838'-7'-
: a. 10 CFR  50, Appendix R Section        III.G.
AOL020304SL8L8'-3'80b'-J.'Lr799'-J.'-4C 0344144'4SL-.77I'-J'L~7824-LOrN-.78j.'-LO' N-7494-3-'rrA'll~r-rc03OH~z-444-r2-2-8AOL0282-bA-N0204J-bA-9Q4Q3.-8AOL028~1,-444OL0208~1.-44~.44 Q4.QeA-r733'3-'L73.9'-J.r
: b. Generic Lett'ers 83-33 and 85-01.
:OLO22-4A-903J.O032-4bOL02H~C-~-4QS,O~QO~~3--4A-90304J--4A-NOLH4L-4bOL02BJSOL0304A.g~gggble0+.~.~eQglN889'9'-3A 0304302-3b-NOLJ.-3A0304L-3b-N'OL02IBL-.883'0'.878'-0'L-.
I c~    NRC  letter to  PP&L  dated    April  18, 1985 which  states:
870'0'-84b'-0'8'8'-Lb 03042LAOL027~~LObAYSe'27'-0'=27P'-0'--
                "The reassessment of non-rated construction should be in accordance with guidance presented at the site audit. That is, to provide reasonable assurance that fire propagation will not occur beyond non-fire-rated zone boundaries, the boundaries should be upgraded, to be continuous barriers with a  fire rating sufficient to withstand the effects of a fire involving in-situ and transient combustibles, with conservative margin. If boundary construction is not upgraded, your reassessment should assume that fire spread will occur into    the next most immediate        fire  zone (horizontally and/or vertically)."
3-A0304~~r@SACS'&#xc3;-LHSf J.I'OL428'-8'SSG7X'ONC-C68CALS4HCN>>FZCUK'Pj-t-.u I'A4:tpt'pit1,)4'il~I}}
3.2   The  analysis performed    was based on the      following assumptions:
aO    The concrete  block or reinforced concrete used in the construction of walls, floors and ceilings are acceptable as being fire rated.
        , b. Evaluation of the fire rating of existing doors by Factory Mutual Research is acceptable to the NRC staff.
C ~  The unprotected    structural steel      will be  shown  to be acceptable using a methodology acceptable to the            NRC.
w3
 
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REQUEST NO. 6 PAGE 2 SPRINKLER FIRE  ZONE BELOW/               PROTECTION BELOW FIRE  ZONE ABOVE                STRUCTURAL STEEL              COMBUSTIBLE LOADING Unit  82  Reactor  Building (Cont.)
2-3B-N/2-4A-S                          Yes                          16 min 2-3B-N/2-4G                           Yes                         16 min 2-3B-W/2-4C                            Yes                          16 min 2-3B-W/2-4D                            Yes                          16 min 2-4A-S/2-5A-W                          Yes                          15 min 2-4A-W/2-5A-N                          Yes                          15 min 2-4A-W/2-5A-W                          Yes                          15 min 2-4G/2-5B                              No                            4 min 2-4A-W/2-5E                            Yes                          15 min 2-4A-W/2-5F                            Yes                          15 min 2-4A-W/2-5G                            Yes                          15 min 2-5A-S/2-6A                            Yes                          6 min 2-5C/2-6A                              No                            6 min 2-6A/2-4G                              No                            6 min Control Structure Elevation 754'-0                      Yes  (Part)                 62 min Support Steel JUSTIFICATION:
Unit  81 and I/2 Reactor Buildings:
lt All fire zones have sprinkler protection below the exposed structural for Fire Zones l-lE, 1-1F, 2-1E, 2-1F 2-4G, 2-5C and 2-6A. In these steel'xcept fire  zones the maximum combustible  rating is 18 minutes, and minimal transient combustibles  are expected. Finally, the in-situ combustibles in these fire zones are generally located near the floor at a distance from where the structural steel forming the fire area barrier is located.
CONTROL STRUCTURE:
Automatic detection and protection is provided below the exposed structural steel. The majority of the combustibles in the area below the exposed structural steel are cables. The majority of the cables are located either below the raised (computer type) floor in the Control Room or in 2 hour fire rated cable chases on the north and south walls of the control structure where only one structural member is effected. There is approximately 20 feet between the raised computer floor and the exposed structural steel supporting elevation 754'-0. Finally, the Control Room comprises the majority of the area beneath this steel and  it is continually staffed.
EXEMPTION RE UEST:
Exposed  structural steel supporting the identified fire area barriers is acceptable and does not requ9.re  fire proofing.
djk/h188c3:del
 
CONTROL STRUCTURE FIRE AREA                  FIRE ZONE(S)
CS-1                    0-21B,029A CS-2                    0-22B, 0-29C,D CS-3                    0-21A, 0-22A, 0-22C, 0-23, 0-24A-G, 0-25A,E CS-4                    0-24I,L CS-5                    0-24K CS-6                    0-24J, 0-25B, 0-26B,S, 0-27F, 0-28P CS-7                    0-24L,M, 0-25C,D, 0-26C,D, 0-26T,V, 0-27G,H, 0-28Q,R CS-8                    0-28S CS  9k*                 0-26A,E-N,P,R CS-10~*                  0-27A-E CS-11                    0-28A Subzone  I (Room C-613)
CS-12                    0-28C CS-13                    0-28E CS-14                    0-28G CS-15                    0-28H CS-16                    0-28J CS-17                    0-28B Subzone  I (Room C-604)
CS-18                    0-28M CS-19                    0-28N CS-20                    0-28A Subzone  II (Rooms  C-611, C-612)
CS-21                  0-28T CS-22                  0-28D CS-23                  0-28F                                    n CS-24                  0-28B Subzone  II  (Rooms 'C-605, C-606)
CS-25                  0-28I CS-26                  0-28K CS-27                  0-28L CS-28                  0-29B, 0-30A,B*
* These    fire zones contain    no safe shutdown cables and  function as a stbu fferies fire zone
** The floor/ceiling between Fire Area CS-9 and CS-10          has unprotected support steel. See Exemption Request Number 6.
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Latest revision as of 14:20, 3 February 2020

Suppls Util 850904 Ltr Re Resolution of Fire Protection Concerns.Listed Replacement Pages Re Sprinkler Protection for Control Structure Elevation & Shutdown Paths Encl
ML18040B123
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 10/03/1985
From: Keiser H
PENNSYLVANIA POWER & LIGHT CO.
To: Butler W
Office of Nuclear Reactor Regulation
References
PLA-2541, NUDOCS 8510080410
Download: ML18040B123 (15)


Text

'

REGULATOR INFORMATION DISTRIBUTION S STEM (RIDS)

ACCESSION'BR o 8510.080410, OOC DATE! 65/10/03 NOTARIZED; NO cocKET e FACIL:50 387 Susquehanna Steam

~

Electric Stationi Unit ii Pennsylva 05000387 50 386 Susquehanna BYNAME Steam Electric Stationi Unit 2'< Pennsylva 05000388 AUTH AUTHOR AFFILIATION KEISER<H,W. Pennsylvania Power 8'ight Co ~

RECIP ~ NAMKl RECIPIENT AFFILXATION BUTLERgW ~ Ri Licensing Branch 2

SUBJECT:

Suppls uti] 650904 .ltr re resolution of fire~ protection concerns. Listed replacement pages- re sprinkler protection for control structure elevation 8 shutdown paths SIZE; encl'ISTRIBUTI N CODE: A0060 COPIES RECEIVED:L~TR. ENCL TITI E: OR Submittal: Fire Prote'ction NOTES: 1cy NMSS/FCAF/PM'PDR 2cys 05000387 07/17/62 Transcripts'L:

icy NMSS/FCAF/PM'PDR 2cys Transcripts; 05000386 OLe03/23/84 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' NRR LB2 BC 01 3 3 INTERNAL: ACRS 11 3 3 ADM/LFMB 0 ELD/HDS4 0 IE NHITNEYIL 1 1 NRR STANGrJ 07 2.' NRR ÃERMEILiJ06 1 0 NRR/DE/CEB 09'4 2 2 NRR/DL DIR 1 1 1 1 RGN1 1 1 EXTERNAL: 24X LPDR 03 NRC PDR 02" NSIC 05 1 1 NOTES:

TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 22

Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/770.5151 Harold W. Keiser Vice President-Nuclear Operations 21 5/770-7502 OCT O3 1985 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION RESOLUTION OF FIRE PROTECTION CONCERNS ER 100450 FILE 841-2, 143 Docket Nos. 50-387 PLA-2541 50-388

Dear Dr. Butler:

This letter supplements PLA-2529, dated September 4, 1985. Enclosed are replacement pages as follows:

~Pa e Descri tion of Chan e Page 3 of Concern 81 Revise Section 2.2 to clarify use of non-rated boundaries Page 2 of Request /f6 in Sprinkler protection for the Appendix A to Concern //1 Control Structure Elevation 754'-0" support steel is partial protection Figure 6 of Appendix B to Shutdown paths 3 6 4 were Concern 81 added to zone 1-6C Figure 9 of Appendix B to Shutdown paths 3 6 4 were Concern Pl added to zone 1-6C Figure 10 of Appendix B to Shutdown paths 3 & 4 were Concern 81 added to zone 1-6C Figure 11 of Appendix B to Added the amount of combustible Concern lI1 loading for zone 1-5C I

" 851 0P FtaR ".OA80<>0 ADOCg "8Seoo3 (OO4 OSOOO3 .

( l I DR

Page 2 SSES PLA-2541 Qg 08 1985 ER 100450 File 841-2, 143 Dr. W. R. Butler

~Pa e Descri tion of Chan e Page 3 to Attachment 2 of Added notes to page regarding Appendix B to Concern //1 the control structure The above changes are editorial clarifications which do not affect the conclusions of the analysis.

Should you have any questions please contact us.

Very truly yours, H. W. Keiser Vice President-Nuclear Operations cc: M. J. Campagnone NRC R. H. Jacobs NRC

iii) Identifying on a case by components which are not case the rated and specific barrier providing a justification for their use.

Any additional fire rated protection required as a result of this redefinition will be in accordance with 10CFR50 Appendix R, Section III.G.

2.2 Other Safety Related Buildings The methodology used in the Control Structure, the Diesel Generator buildings and the ESSW pumphouse was somewhat different since the majority of the fire zone boundaries are fire rated and, as a result, our fire zone boundaries are equivalent to fire area boundaries. For these buildings each fire zone was reviewed for its safe shutdown division. Fire zones having a common safe shutdown division were grouped into fire areas. Each fire area was reviewed to assure that all of its boundaries were fire rated construction, or if a non-rated boundary was acceptable.

3.0 ASSUMPTIONS & NRC GUIDANCE 3.1 The analysis was performed in accordance with the following NRC guidance:

a. 10 CFR 50, Appendix R Section III.G.
b. Generic Lett'ers 83-33 and 85-01.

I c~ NRC letter to PP&L dated April 18, 1985 which states:

"The reassessment of non-rated construction should be in accordance with guidance presented at the site audit. That is, to provide reasonable assurance that fire propagation will not occur beyond non-fire-rated zone boundaries, the boundaries should be upgraded, to be continuous barriers with a fire rating sufficient to withstand the effects of a fire involving in-situ and transient combustibles, with conservative margin. If boundary construction is not upgraded, your reassessment should assume that fire spread will occur into the next most immediate fire zone (horizontally and/or vertically)."

3.2 The analysis performed was based on the following assumptions:

aO The concrete block or reinforced concrete used in the construction of walls, floors and ceilings are acceptable as being fire rated.

, b. Evaluation of the fire rating of existing doors by Factory Mutual Research is acceptable to the NRC staff.

C ~ The unprotected structural steel will be shown to be acceptable using a methodology acceptable to the NRC.

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P ',QP 1+ ~, 'r P 1 h P f

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REQUEST NO. 6 PAGE 2 SPRINKLER FIRE ZONE BELOW/ PROTECTION BELOW FIRE ZONE ABOVE STRUCTURAL STEEL COMBUSTIBLE LOADING Unit 82 Reactor Building (Cont.)

2-3B-N/2-4A-S Yes 16 min 2-3B-N/2-4G Yes 16 min 2-3B-W/2-4C Yes 16 min 2-3B-W/2-4D Yes 16 min 2-4A-S/2-5A-W Yes 15 min 2-4A-W/2-5A-N Yes 15 min 2-4A-W/2-5A-W Yes 15 min 2-4G/2-5B No 4 min 2-4A-W/2-5E Yes 15 min 2-4A-W/2-5F Yes 15 min 2-4A-W/2-5G Yes 15 min 2-5A-S/2-6A Yes 6 min 2-5C/2-6A No 6 min 2-6A/2-4G No 6 min Control Structure Elevation 754'-0 Yes (Part) 62 min Support Steel JUSTIFICATION:

Unit 81 and I/2 Reactor Buildings:

lt All fire zones have sprinkler protection below the exposed structural for Fire Zones l-lE, 1-1F, 2-1E, 2-1F 2-4G, 2-5C and 2-6A. In these steel'xcept fire zones the maximum combustible rating is 18 minutes, and minimal transient combustibles are expected. Finally, the in-situ combustibles in these fire zones are generally located near the floor at a distance from where the structural steel forming the fire area barrier is located.

CONTROL STRUCTURE:

Automatic detection and protection is provided below the exposed structural steel. The majority of the combustibles in the area below the exposed structural steel are cables. The majority of the cables are located either below the raised (computer type) floor in the Control Room or in 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire rated cable chases on the north and south walls of the control structure where only one structural member is effected. There is approximately 20 feet between the raised computer floor and the exposed structural steel supporting elevation 754'-0. Finally, the Control Room comprises the majority of the area beneath this steel and it is continually staffed.

EXEMPTION RE UEST:

Exposed structural steel supporting the identified fire area barriers is acceptable and does not requ9.re fire proofing.

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CONTROL STRUCTURE FIRE AREA FIRE ZONE(S)

CS-1 0-21B,029A CS-2 0-22B, 0-29C,D CS-3 0-21A, 0-22A, 0-22C, 0-23, 0-24A-G, 0-25A,E CS-4 0-24I,L CS-5 0-24K CS-6 0-24J, 0-25B, 0-26B,S, 0-27F, 0-28P CS-7 0-24L,M, 0-25C,D, 0-26C,D, 0-26T,V, 0-27G,H, 0-28Q,R CS-8 0-28S CS 9k* 0-26A,E-N,P,R CS-10~* 0-27A-E CS-11 0-28A Subzone I (Room C-613)

CS-12 0-28C CS-13 0-28E CS-14 0-28G CS-15 0-28H CS-16 0-28J CS-17 0-28B Subzone I (Room C-604)

CS-18 0-28M CS-19 0-28N CS-20 0-28A Subzone II (Rooms C-611, C-612)

CS-21 0-28T CS-22 0-28D CS-23 0-28F n CS-24 0-28B Subzone II (Rooms 'C-605, C-606)

CS-25 0-28I CS-26 0-28K CS-27 0-28L CS-28 0-29B, 0-30A,B*

  • These fire zones contain no safe shutdown cables and function as a stbu fferies fire zone
    • The floor/ceiling between Fire Area CS-9 and CS-10 has unprotected support steel. See Exemption Request Number 6.

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