ML15176A535
| ML15176A535 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/17/2015 |
| From: | Pacific Gas & Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| DCL-15-069 | |
| Download: ML15176A535 (65) | |
Text
DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 -3201-4.4 -40ASSUMPTIONS USED TO CALCULATEPOST ACCIDENT CONTROL ROOM RADIOLOGICAL EXPOSURESA. Power LevelB. Activity Released to Containment Atmosphere1 Iodine, % Of core iodiRe inventon;0. E-lemenfal, % of core inventor'b. Organic, % Of core iodine inventor;fc. lPa;rt-icu,-la;te, % of core iodine invcntOr;2. Noble gases, % of coreinntr3. Other fiGsi9oRn roduC. Decay, Clcanup, and Leakage in Containment Atmosphere1. Radiological decay includeSIdire Spray cleanupb. OrganicG. Particulate3. factor (DF) cut off for Gpray, elemental4. Time post LCA spray start,5. Fmqltcr cleanup Of containment atmosphere-. IN g-lnasesb. KPleble gases2-522.754,004-0080 seeeods.NaneWARPNoneRevision 12 September 1998 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 321 of 3ASSUMPTION'S USED TO CALCULATEPOST AGGIOENT CONTROL ROOM RADIOLOGICAL EXPOSURESOBA-Gase6. Containment leakratea First 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sgb. Remnainder of acident periodD. Rcirculatioan Leop Leakage1. RHR leakage rate2. StarFt f RHR leakage3. Duration of RHR leakage4. C;harcoal filter eAciencY for0Fre lea r-, e of. RH. IR eaka geF. a. C IodinRe filter efftciency(1) Elemental,%(2) OrFganicý,(3) Particulate, -Ab. Noble gas filter efficiencYEE. Me4Ateorology (atmospheric dilution factorsfro~m the- con-ta-inm:ent to the conrol1 room)F. Control RoomA Ventilation Flowratcs1. Flowrate of contaminated airinfiltrating the control room2. Feorate Of press-rization air intethe room3. FowRatA Of rcircFulated control roomq airthrough cleanup filters0. 1,04 peF day0.06,04 peF day50 gpFn24 hr-s0 5 hQO~Q070TAMA 15~-24900Gfmn2100 rfmnRevision 12 September 1998 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 32 Sheet I of 3ASS'JMPTIONS USED TO CALCULATEPOST ACCIDENT CONTROL ROOM RADIOLOGICAL EXPOSURES09A-GaseG. Dosay and Cleanup in Control 1. Radiological dlecay *ncludedYe2. Filte-rr c oeap of r(1) Elemental 5k(2) Organic "(3) Particu4ato )"b. Noble gases Q0/eH. Contro! Room Comnplex Volumne (total for 170-ftg(Units 1 and 2)1. Control Room Occupancy F~actorS1. 024 hewrs2. 24 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />s3. 96 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 04(a) Although a subsequent sacty evaluation showed that thc Design D ae e coefficieRt Of 31 hr4 (fF- 2600gpm spray header flow)should be reduced toapproximnately 20hr4(fo 2166 gpM spray header flow),the potential offsitc dose inGerase due to this changc is e~dremcey small and can be Gonsideredinsignificant (Reference 30).Revision 12 September 1998 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-33ESTIMATED POST-AGGIDENT-LOCA EXPOSURE TO CONTROL ROOM PERSONNELDURING INGRESS / EGRESS (HISTORICAL)GammaExposure,Radiation Source rem98ALOCABetaExposure,remThyroidExposure,rem1. Radiation from airbornc fission productpostulated to enter the control roomNotUsed2. Not UsedDirect radiatien to the cOntrolFOM 49~Mfission prod-ucts in tho con~taipnment6tFUGtUFeTable 5-.5-see-See-Table 155-0.032003. Not UsediDe....rear fromradiation to the centrol0Q02200fiss6io produc'ts in the containmentleakage plue4. Radiation from airborne fission productsin the containment leakage plume to-control room personnel duringroom perconnel du wing egress ingress5. Direct radiation from fission products inthe containment structure to controlroom personnel during egress-ingress(53 5-minute trips)0.00660.0220.02434.7200Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-34STEAM RELEASES FOLLOW!NG A MAJOR STE.A.M L!NE BREAKTime4Pefe40-2-h4 24-8-hSteam release fromA ruptured pope, Ibm ,471,_00 --Steam release from relief valyes, ibm4 394,000 83(GNote: All stewm relcaces listed aboye arc for RSGs. OSG MSLB steam rcleases, which arc used in theM51=6 dose analysis of record, are listed in item 11 of ScctiOn 15.5.18.2.1.SUMMARY OF OFFSITE AND CONTROL ROOM DOSESMAIN STEAM LINE BREAKDose(TEDE, rem)RegulatoryLimit(TEDE, rem)Maximum 2-hour Exclusion AreaBoundary Dose-Pre-incident iodine Spike-Accident-Initiated IodineSpike30-day Integrated LowPopulation Zone Dose-Pre-incident iodine Spike-Accident-Initiated IodineSpike30-day Integrated Control RoomOccupancy Dose-Pre-incident iodine Spike-Accident-Initiated IodineSpike0.10.7252.5<0.10.2252.552.04.1Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATENote:1. The maximum 2-hour EAB dose occurs during the following time period:-Pre-incident iodine Spike 0 -2 hours-Accident-Initiated Iodine Spike 7.6 -9.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sRevision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-34AMAIN STEAM LINE BREAKAnalysis Assumptions & Key Parameter ValuesParameter ValuePower Level 3580 MWtReactor Coolant Mass 446,486 IbmLeak rate to Faulted Steam Generator 0.75 gpm (conservative assumption);leakage density 62.4 Ibm/ft3Leak rate to Intact Steam Generators 0 gpm (all leakage assumed into faultedSG)Failed/Melted Fuel Percentage 0%RCS Tech Spec Iodine Conc. Table 15.5-78(11 pCi/gm DE 1-131)RCS Tech Spec Noble Gas Conc. Table 15.5-78(270 pCi/gm DE Xe-133)RCS Equilibrium. Iodine Appearance Rates Table 15.5-79(1 pCi/gm DE 1-131)Pre-Accident Iodine Spike Concentrations Table 15.5-79(60 pCi/gm DE 1-131)Accident-Initiated Iodine Spike Appearance 500 times equilibrium appearance rateRateDuration of Accident- Initiated Iodine Spike 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />sInitial Secondary Coolant Iodine Table 15.5-78Concentrations (0.1 pCi/gm DE 1-131)Secondary System Release ParametersIodine Species released to Environment 97% elemental; 3% organicFraction of Iodine Released form Faulted SG 1.0 (Released to Environ without holdup)Fraction of Noble Gas Released from Faulted 1.0 (Released to Environ without holdup)SGRevision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-34AMAIN STEAM LINE BREAKAnalysis Assumptions & Key Parameter ValuesParameter ValueLiquid mass in each SG Faulted: 182,544 Ibm (max.)Intact: 92,301 Ibm (min. and initial)Release Rate of SG liquid activity from Faulted Dryout within 10 secondsSGTime period when tubes not totally submerged Insignificant(intact SG)Steam Releases from intact SGs 0-2 hrs: 384,000 Ibm2-8 hrs: 893,000 Ibm8-10.73 hrs: Same release rate as that for2-8 hrsIodine Partition Coefficient in Intact SG 100 (SGs fully covered)Termination of release (0.75 gpm leak): 30 hrs when RCS reaches 212 OFFaulted SGTermination of release from Intact SG 10.73 hour8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />sRelease Point: Faulted SG Outside containment, at the steam linebreak locationRelease Point: Intact SG MSSVs/10% ADVsCR Emergency Ventilation : Initiation Sigqnal/TimingInitiation (signal) SISUnaffected Unit CRVS inlet damper fully Within 12.6 secondsclosedAffected Unit CRVS inlet dampers fully closed Within 38.8 secondsControl Room Atmospheric Dispersion Factors Table 15.5-34BRevision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-34BMAIN STEAM LINE BREAKControl Room Limiting Atmospheric Dispersion Factors (sec/rn3)Receptor- Release Point 0-2hr 2-8 hr 8-10.73 hr 10.73-30 hrCR NOP Intake -Faulted SG (Break Note 1Location)CR NOP Intake -Intact SG (MSSVs/10% 8.60E-04ADVs) -Note 2CR Inleakage -Faulted SG (Break 1.24E-02 7.35E-03 3.01 E-03 3.01 E- 3Location)CR Inleakage -Intact SG (MSSVs/10% 2.78E-03 1.63E-03 1.63E-03ADVs)CR Emergency Intake & Bypass -7.65E-05 4.78E-05 1.86E-05 1.86E-C5Faulted SG (Break Location)CR Emergency Intake & Bypass -Intact 1.57E-05 9.60E-06 9.60E-06SG (MSSVs/1 0% ADVs)Notes:1. ARCON96 based %IQ s are not applicable for these cases given that the horizontaldistance from the source to the receptor is 1.5 meters (which is much less than the 10meters required by ARCON96 methodology).2. Due to the proximity of the release from the MSSVs/10% ADVs, to the normal operationCR intake of the affected unit, and due to the high vertical velocity of the steamdischarge from the MSSVs/10% ADVs, the resultant plume from the MSSVs/10% ADVswill not contaminate the normal operation CR intake of the affected unit. Thus the x/Q spresented reflect those applicable to the CR intake of the unaffected unit.Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABL E 15.5 40 (HISTOGRICAL)LONG TERM ACTIVIITY RELEASE FRACTIONSFOR FUEL FAIL UREI CCIDENTSRelease Fractoni434 47374-4e2.51 :f n-ýOi.02 x 43!04Q-45.34 14.424_1O444i3554Kr-85 1 .! x tX-e433 8.6 344oXit-4&3MX-e43S 4497-r&4OXe 433M 5.52ixt.Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 41 Sheet 1 of 2ACTIVITY RELEASES FOLLOW~hiG A LOCKED ROT-OR ACCIDENT (CURIES)13i8.643 1 4--783E1732 1.21Er 1 2. A 1"Ei 433 7-.7-3EI 3.4725E01-4-34 670861ii2 4.067-F=2353.673E 1-A067E-O131ORG 0301!320RG 070 0-0-330RG 070 07013400 0-01-35RG 050 0-0130 0P014-32PAR 070 070133PAR0 001-434P-AR 0 070070 070Kr 83M 976E 1 4281EKF-86 1.2282E1 14.610E 1KF-85M 4.9366E- 4.169! E0K- -2949EO0 8.647-1-Kr-88 8-5004E-0 5.4137E0Xe33 23226840E2Xe433M 3.386E0 5.4188E0Xe4135 2.0293E4 2.2393E4lXe 135M 3.026E-I 0Xe 139 9.120F4 0Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETARF1 G-Al Rhapt I Af2ACTIVITY RLEASES FOLLOWIG A LOCKED ROTOR ACCIDENT (CURIES)E u p ep-t ed QCasoe0-2-hfNuGlidei--32l4341-3411351431 RG1432ORG1--1-,38ýb1-340RýG1436ORGP--434PaARI432PAR14133PARI-,34PAR1 436PARKF-83Ml F-85MXe 133Xe4133MXe4136Xe4135MXe 138!.I09E-21.~223F=8849E--33784E-0700-007094-.456E-22.087E I2.825E-!10706E1.6405.670E 22.386E 33.875E 24.001 E 41.425E 207007007007007007-0o07o0-00700703.770E-3a2.379E 14932E--25482E--334.28-E-0-2.366F=4Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-42SUMMARY OF OFFSITE DOSES-AND CONTROL ROOM DOSESFLROM A-LOCKED ROTOR ACCIDENTThyr-4d rem10 CER Part 100Design bassis- c-aseExpeoted Gas@30 0,303009.9766 -549W.Ahole Body E=XpectL:: Mb MWMHIc;RtpA. -A nrnh'¶10 CFR Part 100Design basis caseExpeeted GaseDesign basis caseExpeGted Gase2544-73-40I a-5~4254-.34404PeoulWation [Doses, man rem0-.321(1-40Dose(TEDE, rem)RequlatoryLimit(TEDE, rem)Maximum 2-hour Exclusion AreaBoundary Dose'30-day Integrated LowPopulation Zone Dose30-day Integrated Control RoomOccupancy Dose0.80.22.42.5255Note:Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATE1. The maximum 2-hour EAB dose occurs between 8.73 -10.73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />.Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-42ALOCKED ROTOR ACCIDENTAnalysis Assumptions & Key Parameter ValuesParameter ValuePower Level 3580 MWtReactor Coolant Mass 446,486 IbmPrimary to Secondary SG tube leakage 0.75 gpm (total for all 4 SGs); leakagedensity 62.4 Ibm/ft3)Melted Fuel Percentage 0%Failed Fuel Percentage 10%Equilibrium Core Activity Table 15.5-77Radial Peaking Factor 1.65Fraction of Core Inventory in Fuel Gap 1-131: 12%Kr-85: 30%Other Noble Gases: 10%Other Halogens: 10%Alkali Metals: 17%Isotopic Inventory in Fuel Gap Table 15.5-80Iodine Chemical Form in Gap 4.85% elemental95% particulate0.15% organicSecondary Side ParametersInitial and Minimum SG Liquid Mass 92,301 Ibm/SGIodine Species Released to Environment 97% elemental; 3% organicTime period when tubes not totally submerged insignificantSteam Releases 0-2 hrs: 651,000 Ibm2-8 hrs: 1,023,000 Ibm8-10.73 hrs: same release rate as that forRevision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-42ALOCKED ROTOR ACCIDENTAnalysis Assumptions & Key Parameter ValuesParameter Value2-8 hrsIodine Partition Coefficient in SGs 100Particulate Carry-Over Fraction in SGs 0.0005 by weightFraction of Noble Gas Released 1.0 (Released without holdup)Termination of releases from SGs 10.73 hour8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />sEnvironmental Release Point MSSVs/10% ADVsCR emergency Ventilation : Initiation Signal/TimingControl Room is assumed to remain onnormal ventilation (CRVS Mode 1) forduration of the accident.Control Room Atmospheric Dispersion Factors Table 15.5-42BNote 1: Due to the proximity of the release from the MSSVs/10% ADVs, to the normaloperation CR intake of the affected unit, and due to the high vertical velocity of the steamdischarge from the MSSVs/10% ADVs, the resultant plume from the MSSVs/10% ADVs willnot contaminate the normal operation CR intake of the affected unit. Thus the X/Q spresented reflect those applicable to the CR intake of the unaffected unit.Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-42BLOCKED ROTOR ACCIDENTControl Room Limiting Atmospheric Dispersion Factors (sec/m3)Release point and receptor 0-2hr 2-8 hr 8-10.73 hrMSSVs/10% ADVs to CR NOP Intake (Note 1) 8.60E-04 5.58E-04 5.58E-04MSSVs/1 0% ADVs to CR In-leakage (CR 2.78E-03 1.63E-03 1.63E-03Centerline)_______________ I ____ [ ____ I ____Note 1: Due to the proximity of the release from the MSSVs/10% ADVs, to the normaloperation CR intake of the affected unit, and due to the high vertical velocity of the steamdischarge from the MSSVs/10% ADVs, the resultant plume from the MSSVs/10% ADVs willnot contaminate the normal operation CR intake of the affected unit. Thus the X/Q spresented reflect those applicable to the CR intake of the unaffected unit.Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 44COMPOSITE SOURCE TERM FOR FUEL HANDLING ACCIDENTIKI T r-L El I--I LUAMIV IMIt DI III 11 lKINIfCGmRPG~iGSourcGe Termatv Ahtdi -goAGUY-ty at 100-Heum AfteFShu~tdown4Cilat 400 hFG)Pool Artivty-(CIat I O-h-FS)5 PRI 2FFHB Activity Basedon DF-200 for-ledene6(Clat 00 r-s4-132 7-.283E+G5 3.42E+ 4O-3E-04 250965!--3 .-3783EA-0,4 34.44-434 !0 0 04-4-35 2.689E=+04 443 -+ 0,22-2_4-83M 8_-46-,4 -9.554 Em 0 &.5764F 0 1.574E 08__-9.04 +5 3v678Q--g2 0.09607G4 0.0050704Xf-8" &7353&E+G3 6.360c:+0 342 3443.25K+-87 3 0 0 0Kf--- 5-446E05 1.5-0E 05 2.2275E 0g 2-22745E06Kr-8x .855E+05 0 0 0Xe-3-14m 5.661 E+03 5469F-+ 9029 902-83Xe-1-33 3-487-E-44 1.30E+04 24-54,9 2454-.Xe-133 9,499E-1 694544G 6 4- 4484- 4404-Xe-1. -5M 2.02! E+05 4.264E+00 0.7035 _ _-Xe4 22884-+05 !.327E+03 2-48 -5 2485Xe-4-37 9-440-0 0 0 0Xe-43 94-7-E-+G5 0 0 0Where:ThO .... Rh _ .h4A l S afft.- e .hf .,n -A4..Pool act-,tv at 100 hoUrs -xa.5x ees faleand£~~sA ~- .IRHO ~arW.tivW-at 100 houre- (ýA100' .2 for- iodineRevision 16 June 2005 DCPP UNITS 1 & 2 FSAR UPDATETSAhE15.545 geet4- f-2ASSUMPTIONS FOR FUEL HANDLING ACCIDENT IN THE FUEL HANDLING AREAA- Pre accGidcnt Opcration1. Core Poc V3580 MWt43- Highest Power FucIF-k Asrsem,-Fbly Characteristics1. Radial pcaking factor445G7 Fuel Assembly Damage1. Nuwmber of fuel rods pr pasrembly 2-642. Number of fuel road-s ruptured peFr asembly 2-643. Number of fuel assemblies damaged 4 Gap Activty rFractions6Aedi~ne 040aR. Emlemcntal(197b. -Oqa~iG 0.00025A- Partic~ulatge 04Q2. Neblegase&a. Other than Kr 85 04-0b. KO r 85 pouSGap Activity Releaseu Fractions4-2. Noblega6e& 4-3. Other fission products NeReFission Product Release Depth 23 egtG- Spent Fuel Pool Decontamination Factorsa. Elementa! 5w0b. Organ~iG 4-N~4eG. Particulate Nonet2. NJoble ga~es 43. Other fission products NoAneRevision 17 November 2006 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 Sheet ! ef 2ASSUMPTIONS FOR FUEL HANDLING ACCIDENT IN THE FUEL HANDLING AREAH, Dcay and Cleanup in Fuel Handling Building1. Radiological decay credit NeR2. Radiological cleanup crdG Nene4, Fuel Han~dling Building Volume 435,000-t.1. Fuel Handling Building Filter Efficiencies Not rrpd44e4K- Fuel Han~dling Building Exhaust Rate4,00Gn4= Atmospheric Disper-sion1. Radiological decay credi Neign2 2E (BO) 0 to 2 hr 4nLPZ (1 kmn) 0to 8hF 2fFSt9 24 h~ 4 5F= regm~A& to 2n h 3.3F= 7eeýR;ýM, Off-site Breathing Rates Tab!1 .5 7-(*Assumes the FHB Yentilation operates contin;uously to maximize the F=HB exhaust to the early-stages of this event with Or without offcite power-.Revision 17 November 2006 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-47SUMMARY OF OFFSITE AND CONTROL ROOM DOSESDOSES FROM FUELHANDLING ACCIDENTIN THE FUEL HANDLING AARE-ACCIDENT IN THE FUEL HANDLING BUILDING ORCONTAINMENTDose Regulatory(TEDE, rem) Limit(TEDE, rem)Maximum 2-hour Exclusion Area 6.3Boundary Dose1-FHA in Fuel Handling 1.5Building-FHA in Containment 1.530-day Integrated Low 6.3Population Zone Dose-FHA in Fuel Handling 0.2Building-FHA in Containment 0.230-day Integrated Control Room 5Occupancy Dose-FHA in Fuel Handling 1.1Building-FHA in Containment 4.7Note:1. The maximum 2-hour EAB dose occurs between 0 -2 hours.Revision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-47AFUEL HANDLING ACCIDENT IN THE FUEL HANDLING BUILDING OR CONTAINMENTAnalysis Assumptions & Key Parameter ValuesParameter ValuePower Level 3580 MWtNumber of Damaged Fuel Assemblies 1Total Number of Fuel Assemblies 264Decay Time Prior to Fuel Movement 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />sRadial Peaking Factor 1.65Fraction of Core Inventory in gap 1-131 (12%)Kr-85 (30%)Other Noble Gases (10%)Other Halides (10%)Alkali Metals (17%)Isotopic Inventory in Fuel Gap (Decayed 72 Table 15.5-47Chours)Iodine form of gap release before scrubbing 99.85% elemental0.15% OrganicIodine form of gap release after scrubbing 57% elemental43% OrganicScrubbing Decontamination Factors Iodine (200, effective)Noble Gas (1)Particulates (oo)Rate of Release from Fuel PuffEnvironmental Release Rate All airborne activity released within a 2 hourperiod (or less if the ventilation systempromotes a faster release rate)Revision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-47AFUEL HANDLING ACCIDENT IN THE FUEL HANDLING BUILDING OR CONTAINMENTAnalysis Assumptions & Key Parameter ValuesParameter I Val u:e:Environmental Release Points and RatesAccident in SFP in the FHB -Release flow -Plant Vent -46,000 cfmratesFHB Outleakage-Ingress/Egress locations -30 cfm-Miscellaneous gaps/openings -470 cfmMinimum free volume in FHB above SFP 317,000 ft3Accident in Containment -Release flow rates -Open Equipment Hatch -All airborneactivity released in 2 hrsMinimum Free Volume in Containment above 2,013,000 ftWOperating FloorCR Emergqency Ventilation: Initiation Signal/TimingSignal(s) available to switch the Control Room Radiation signals from gamma sensitiveVentilation System (CRVS) from normal intake monitors that initiate closure of theoperation (NOP) Ventilation (Mode 1) to CR normal intake dampers and switch thePressurized Filtered Ventilation (Mode 4) Control Room Ventilation System fromfollowing a FHA normal operation Ventilation Mode 1 toPressurized Filtered Ventilation Mode 4.Radiation Monitor Analytical Safety Limit 1 mRPhrDelay time for CRVS Mode 4 operation, 22 seconds (see below)including monitor response, signal processing,and damper closure timeRadiation Monitor Response Time 10 seconds (conservative assumption) -(Refer to Section 15.5.22.2.4)Radiation monitor signal processing time 2 secondsNOP Ventilation Damper Closure Time 10 secondsBounding Control Room Atmospheric Table 15.5-47BDispersion Factors for FHARevision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETEDE Expocuroc, rcmRegu4latory1/2LmiDesign basic GacoDe"ign basic -ase5Revision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATE4-TABLE 15.5-47BFUEL HANDLING ACCIDENT IN THE FUEL HANDLING BUILDING OR CONTAINMENTControl Room Limiting Atmospheric Dispersion Factors (sec/m3)Release Location / Receptor I 0-22 s i 22 sec -2 hr I 2-8 hr I 8-24 hr I 1-4 d I 4-30 1Control Room Normal IntakesContainment Hatch Release I-Affected Unit Intake 2.61 E-02 ----- --Non-Affected Unit Intake 2.88E-03 --Plant Vent Release-Affected Unit Intake 1.67E-03 ----- I-- --Non-Affected Unit Intake 9.1OE-04 .... .....FHB Out-leakage points-Affected Unit Intake 6.98E-03 ----- ---Non-Affected Unit Intake 2.93E-03 ----- ------------ -----Control Room InfiltrationContainment Hatch ReleasePlant VentFHB 0Control Room Pressurization IntakeContainment Hatch ReleaseNote 1: Release from the Containment Hatch: applicable to FHA in ContainmentNote 2: Release from Plant Vent / FHB Out-leakage: applicable to FHA in FHBRevision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-47CISOTOPIC GAP ACTIVITY -FUEL HANDLING ACCIDENTSingle Fuel Assembly (Decayed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)Activity Gap Fraction Gap Activity perPer AssemblyAssembly (w/o PeakingNuclide (Ci) Factor)1-129 2.07E-02 0.10 2.07E-031-130 3.29E+02 0.10 3.29E+011-131 4.09E+05 0.12 4.91 E+041-132 3.99E+05 0.10 3.99E+041-133 9.73E+04 0.10 9.73E+031-135 5.01E+02 0.10 5.01E+01KR-83M 2.51 E-04 0.10 2.51E-05KR-85 5.75E+03 0.30 1.73E+03KR-85M 1.77E+00 0.10 1.77E-01KR-88 7.73E-03 0.10 7.73E-04XE-127 9.64E-02 0.10 9.64E-03XE-129M 5.28E+01 0.10 5.28E+00XE-131M 6.96E+03 0.10 6.96E+02XE-133 8.31E+05 0.10 8.31E+04XE-133M 1.88E+04 0.10 1.88E+03XE-135 1.07E+04 0.10 1.07E+03XE-135M 8.18E+01 0.10 8.18E+00CS-132 2.16E+01 0.17 3.67E+00CS-134 1.25E+05 0.17 2.13E+04CS-134M 1.04E-03 0.17 1.77E-04CS-135 3.01E-01 0.17 5.12E-02CS-136 3.1OE+04 0.17 5.27E+03CS-137 7.10E+04 0.17 1.21E+04RB-86 1.16E+03 0.17 1.97E+02RB-87 1.37E-05 0.17 2.33E-06RB-88 8.63E-03 0.17 1.47E-03Revision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 48DESIGN INPUTS AND ASSUMPTIO2NS FOR FUEL HANDLINGACCIDENTS INSIDE CONTAINMENT-Sh~eet 1 of 2Par-amoeWGonta*Rmef4CContainment Free Vo-lume (ft)Containment Volume aboev Fuel Pool (ftf}Purge Line Flowraatc to- Environmment (CFM)Depth of IW a er.Above Damaged Fuel (ft)Iodine DecentaminatiOn Factors:Inrgqanic (ElementalOverall EffectiveExfiltration Rate (oft)Duration of Release (rcc)Time of Accident after ShutdoWn (h-r)Number of Failed Rodegap Activity Released from. DPamaged Rods %)Noeble Gases other thanp Kr- 85IednResIodine Gap -IeFgaR4iG-Values Assumed for Generation of Inventories:Reatom-r-,q Power (%RTP)1Reactor Poer. (MMt)Radial Peaking F~actorDo-se Conmversion Factors for Iodine Species (REMCim);44g4-.2341-2400400ý26943g4-406.44E*033.13E+040Revision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 48 Sheet-1 of2DESIGN INPUTS AND ASSUMPTIONS FOR FUEL HANDLINGACCIDENTS INSIDE CONTAINMENTPmter VaheControel Room (CR) Input Data:Conrol1 RoomA Volume (Ul +UJ2) (cu1bic feet) 17-70000Flowrates (CF=M)FlRoI-ratc of contaminated air into CR 24--1-Flowr.Agatc of recirc CR air thru filtcrs 0CR pres-surizationm air filter--Filter QePth phzodiRne FilteFr EfficienR---lemeP9GF9 f1 ~"0-Pa~iG~4ate 9"0CR Occupancy F~actoFrs:0 24, h'Fs 4 E-96 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />sAtmospheric Disper~sion Factors (6ecý0m68 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5;2 96 hurs 349E-405A6 720 hors 2.27E-0-Control Room Infiltration:8 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> .49E 4Q~024 06 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 1-,08-0496 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 629E=-06Exclu-1sion Area Boundar,' (EAR), 800 m~eterS:LwPopul1ation Zone (L=PZ=), 100009 meters:R8-24 hous 422E-054 -30 days 3.40E 07Control Room Breathing Rate (Fn 4iseG)y 3.4-7~-E4Offsite Breathing Rates (1.5EeG }0-8 :24 hours 1.75E 941 -20 days 2.32F= 04Revision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 49ACTIVITY RELEASES FROM FUEL HANDLING ACCIDENT INSIDECONTlAINMl=ENT (lURE r-N4GIke 0-2-hf14,'4 299.06251432 250.9654434 0!1435 0.0222KF 83Fn 1.5764E 08KrF-85m 0.0060704KF 853143262K-r87- 0Kr-88 2.2275E 06K-F89 0Xe 4344M 902.385Xe4-33m 212459Xe 133 444084Xe 135m~ 0.70356xt43- 2481955Xe 137 0Xe 139 0Revision 15 September 2003 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 50SUMMARY OF OFFSITE DOSES FROM FUEL HANDLING ACCIDENTINS IDR CONITA1MENTThyroid Exposures, remCnAtrM Rt4n11 -1 G. I --Fp-----3G4)aysQ+a On, ,nrf'~.n, ~ Lip. are10 CFR Padr 100Gase39-(GQG4Q9)22.343w0V':noie t~eGV FMme~r~pion 1i-XEsUreG. remRGGR#91 Repm-!an- mmyc,-SieBua Rda .Rl.,n, 4 n. u10 CFR Part 1 00Iease bsi5 (GOG 19)2-4Population Doses, man remDcsigR basis caseExpeeted GaseRevision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATEYAMSI~ r! 4V V=Sh e et I f-2 I.ACGT-1VEP4 RELE 16 A -E 2 G FOLLO'AAIN'G .ROQD E JECGTI1-ON ACC IDENTý (C UR IES)6"-1414321432I1431RG1320RGb4 3ORG14340RG,1 135ORG1 434 PA R14 32PAR1422ARI1424PARKr 85Xe 433MXe 435O09765EO 20 4578r, GO70,1E34e02O.1729E0G20-004- 660096r 00-0 r n250ar0 09.7006Ego10.35700 000.43326 0i0.257-7-F010.79i3rE09Z8h0-00-00-0 8,--4047-Eq0-0 ,5--90?28-0 -0,28-0 E-40-.7-26i, 9E--204&r.0.,3650r,-94-(M4424-E--400.279.24-Va-#F0-0049426-820 44776- 010364-2-00-096m30-0G0-00-2440 4064r 040 E3r 00-02F500. i0 ri0Revision 11 November 1996 DCPP UNITS 1 & 2 PSAR UPDATETABLEr 15.551F9 Shoot 1 9f 2AGTI"ITY RELE.SES8 rOl-lGOANG A. ROD EJECTION ACCIDENT (CURIE!S)NuG~e 0- 2 h-hi R 24 hr 24-96-hr143 a464fir-0a 40 401132 a-~54 04 04 04 01 133 0.424;Er 040 -1134 0.2963r503 40 40104 04 04 0-G3114O4RG 040440441 132ORG 0404040401-4330R 0.404411340RG 0 40 40146OQRG 0 40 40114R4AI 0.4 0 40I 132PAR 040 04 0 40I-432AR 04 0 40 -1434RA 0044 04 01 13PAR 0 40 40K 240 2$122rE04 9.30956 04 0 3GR4r, 02 0.1757EF!05 041063E1i6Kr E .539 0.15 699E01 0.4260601 01 48420KF 85M a.700 9.28896E00 946899 Go 0.37020A75-KF ~za 627-a 024OW020. 192.2E08a 154$45g23KFR 0396 40600-148-0 IROF an0 Q~F_0.164BE140Xe 13056~eg 04404RE0 G.41360 0.7250r.02 0.4469903Xe 13M 0.9286E 04 0.2560 06492rE00 0.8236E00.59 gXe 436 O6aw2E0a 0.4 49GE 4 0 4926P 04 0,287. g 04a 4E24 .Xe 135M 0 422g9E04 Q062686044 07~407r_4 0 4070r. 29Xe 138 04967E0 0 )4036E048 0484QrM ii 190r.~0 0-Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-52SUMMARY OF OFFSITE DOSES AND CONTROL ROOM DOSESROM A-CONTROL ROD EJECTION ACCIDENTDose(TEDE, rem)Re.qulatoryLimit(TEDE, rem)Maximum 2-hour Exclusion AreaBoundary Dose1-Containment Release-Secondary Side Release30-day Integrated LowPopulation Zone DoseContainment ReleaseSecondary Side Release30-day Integrated Control RoomOccupancy Dose-Containment Release-Secondary Side Release6.30.70.76.30.30.253.40.5Thyroid Exposures, remaSite lDenda ,nrn 2 -.n arem10 CFR Part 100Design b-asis csExpeuted Gase3003.3-x404300164-449Whole Pedy F=XPosur~eS, remc;.-. fl R n n,, -m ~ ta r10 CFR Pat 100Design basis case2-52514x4.344Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATEFixp9Gted Gase 3,64-9-4OPopulation Doses, m~an remDoerin basis cGase 04Exper~ted Gase .2Note:1. The maximum 2-hour EAB dose occurs between 0 -2 hours.vl-Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-52ACONTROL ROD EJECTION ACCIDENTAnalysis Assumptions & Key Parameter ValuesParameters ValueContainment Leakage PathwayPower Level 3580 MWtFree Volume 2.550E+06 ft3Containment leak rate (0 -24 hr) 0.1% vol. fraction per dayContainment leak rate(1-30 day) 0.05% vol. fraction per dayFailed Fuel Percentage 10%Percentage of Core Inventory in Fuel Gap 10% (noble gases & halogens)Melted Fuel Percentage 0%Chemical Form of Iodine in Failed fuel 4.85% elemental95% particulate0.15% organicRadial Peaking Factor 1.65Core Activity Release Timing PuffForm of Failed Iodine in the Containment 97% elementalAtmosphere 3% organicEquilibrium Core Activity Table 15.5-77Termination of Containment Release 30 daysEnvironmental Release Point Same as LOCA Containment LeakagepathwaySecondary Side PathwayReactor Coolant Mass 446,486 IbmRevision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-52ACONTROL ROD EJECTION ACCIDENTAnalysis Assumptions & Key Parameter ValuesParameters ValuePrimary-to-Secondary Leak rate 0.75 gpm (total for all 4 SGs); leakagedensity 62.4 Ibm/ft3Failed Fuel Percentage Same as containment leakage pathwayPercentage of Core Inventory in Fuel Gap Same as containment leakage pathwayMinimum Post-Accident SG Liquid Mass 92,301 Ibm / SGIodine Species released to Environment 97% elemental3% organicTime period when tubes not totally submerged InsignificantSteam Releases 0-2 hrs: 651,000 Ibm2-8 hrs: 1,023,000 Ibm8-10.73 hrs: same release rate as thatfor 2-8 hrs.Iodine Partition Coefficient in SGs 100Fraction of Noble Gas Released 1.0 (Released without holdup)Termination of Release from SGs 10.73 hour8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />sEnvironmental Release Point MSSVs/1 0% ADVsCR emergency Ventilation: Initiation Signal/TimincqInitiation time (signal) 300 sec (SIS Generated)312 sec (Non-Affected Unit NOP Intakefully Closed)338.2 sec (Affected Unit NOP Intake fullyClosed with full Mode 4 EmergencyVentilation Operation).Control Room Atmospheric Dispersion Factors Table 15.5-52BRevision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-52BCONTROL ROD EJECTION ACCIDENTControl Room Limiting Atmospheric Dispersion Factors (sec/m3)Release Location I 0-2hr 2-8 3hr 10.73- 24-961 hrReceptor 24hrCR Normal IntakesContainment leakage-Affected Unit Intake 6.84E-03-Non-Affected Unit Intake 2.24E-03MSSVsI10% ADVs-Affected Unit Intake Note 3 .-----Non-Affected Unit Intake 8.60E-04 .----CR InfiltrationContainment leakage 3.22E-03 1.85E-03 7.29E-04 7.29E-04 7.15E-04 6.64E-04MSSVs/1 0% ADVs 2.78E-03 1.63E-03 1.63E-03 1CR Pressurization IntakeContainment leakage 6.45E-05 4.05E-05 1.65E-05 1.65E-05 1.38E-05 1.12E-05MSSVs/10% ADVs 1.57E-05 9.60E-06 9.60E-06 .----Note 1: Containment leakage: Used for Containment release scenario; based on Containmentpenetration area release point.Note 2: MSSV /10% ADVs: Used for Secondary System Release Scenario;Note 3: Due to the proximity of the release from the MSSVs/10% ADVs, to the normaloperation CR intake of the affected unit, and due to the high vertical velocity of the steamdischarge from the MSSVs/10% ADVs, the resultant plume from the MSSVs/10% ADVs willnot contaminate the normal operation CR intake of the affected unit.Revision 11 November 1996 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 63POST LOCA DOSES WITH MARGIN REIRULATION LOOP LEAKAGEf'C'NIT-RO DROfVM GCgDIDAT(', 096CC OC,Gamma -BetaWhl e --siContainment leakageRHR pump akageE~xpccted recirulation loo okReoirculatien loop leakage:1.85 gpm, with ltration,- r0.1 86 gpnm, with nR flltFationPlu-me radiation (cgress ingroes)Other direct radiation pathwaysTOTAL CONTROL ROOM OPERDATOR DOSES10 CFR PART 50 APPENDIX A, GD- 19 LIMITSSITE BOCUNDARYContainment IeakageRHR pump 6eal leakageExpected recirculatien loop leakageRocirUlatiOn loOP leakage:1.8gpmn, with charcoal filtration, orG,4189 gPmA, With no filtFrafenTO-TAL SITE BOUNDARY DOSESPathwayContainment leakageRHR pump soal leakageExpected Freirculation loop leakageRecirsulation leop leakage:11.07 gpm, with charcoal fi'tration,-or1.11 gpma, with no filtrationTOTAL LPZ= DOSESNotes052218 454.7-20-.90,03040,0oooooa0,000@0,006go~o~so9.00144a3484.72Gamma0,0gWhoe edNotes0-522-Gamma0,Qoi 0.292-4-2 0.003Notes044239009010 CFPR PART 1 00 DORR LMWTSNetes:1. RHR pump soal leakage of 50 gpmA for 30 Fminutec, 6tarting 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> after the start of the LOCA, SeeT-ables 15.5 21 and 15.5 33.2. Additieoal frerculation loop leakage, existing at the ctart of the LOCA and continuing for 30 days,2 T;;krn from Tnhlp I1A5 22Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATET-ABLE 15.5 64PARAMETERS USED IN EVALUATINGRA.DPILOGIGAL CONSEQUENCES FOR SGTR ANALYSISSheetI-ef2A. oro. pwe- level, .'At3580B. Total stear.. geReFateF tubei4eaKaele4-.0prF9r t- rpmC. ReacGtorcolant act*ty.I Accident initiated snike2. Pre accident spike3. Noble gas acti'.'ty1 IC.i.gram. of D.E. 1 131 arc p .restedin Table 15.5 65. The iodineappearance rates based on an iodinespiking factor of 335 assumed for theaccident initiated spike are presented inTable415-5-6-6Primar; cool-Ant iod-ine activities baseon 60 I*Ci~gram of D.E. 1131 arein Table 15.5 65The inui~a! RO noble gas activities baseon 1% fuel defects are presented inTable 15.5 67Dose equivalent of 0.n1 Ci/gm of 11 31,presented in Tabme 15.5..65.D. Secondar; system initial activityE. Reac-tor cool-ant mnass, grams6F. initial ste.gr~ams,:am aenerator mass (each),G. Offsite powerH. Primar; to sec..fre intact SG, hrsLot-a time9 Of re-ac-tortrip,a.4 iea,.,e GUUWLati8I.Species, of iodine100 percen÷t elementalRevision 19 May 2010 DCPP UNITS I & 2 FSAR UPDATETABLE 15.5 64PARAMETERS USED lN EVALUATINGAL CONSE=QUI ENCESig FOR SGTR.ATD ANALYSISlSheet 2 of 2!I. Activity Release DataA. Ruptured 6teamA generator1. Rupture fo2. Flashed rupture flow3. iodine scrubbing efficiency41. Tota! cteam release, lb5. Iodine partition coefficientSee Figure 15.4.3 6b anrdSee Figuro 15.4.3 11 aRndTa;p1&4-44Net 4TedSee FgRem 15.4.3 9 and T-phla EA 141-R~R-fl~shedLI -L 004,9B. InRtact steam generators1. To9tal priMar; to secondary leakage,gpm2. Total steam release, lbs3. lod;Re partition coefficient4-.0See Figure 15.4.3 10 and-Tab;; 1i-. 444--oC. Condenser1. iodine partition; coefficinD). Atmospheric dispersfion factors400See Table 156.5 68TABLE 15.5-64SUMMARY OF OFFSITE AND CONTROL ROOM DOSESSTEAM GENERATOR TUBE RUPTUREDose(TEDE, rem)ReaqulatoryLimit(TEDE, rem)Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 64Sheet-2-ef-2PARAMETERS USED IN EVALUIATINGRADIOLOGGICAL CONSEQENCE IFhrFROR SGTR ,ANAL YSISMaximum 2-hour Exclusion AreaBoundary Dose1-Pre-incident iodine Spike-Accident-Initiated IodineSpike1.30.7252.530-day Integrated LowPopulation Zone Dose-Pre-incident iodine Spike-Accident-Initiated IodineSpike30-day Integrated Control RoomOccupancy Dose-Pre-incident iodine Spike-Accident-Initiated IodineSpike0.1<0.1252.550.60.3Note:1. The maximum 2-hour EAB dose occurs during the 0-2hr time period:Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 64PARAMETERS USED IN EVA LUATNG-AL EC' E Ir- SR FOR SGTR ANIAI YSlSheet 2 fTABLE 15.5-64ASTEAM GENERATOR TUBE RUPTUREAnalysis Assumptions & Key Parameter ValuesParameter ValuePower Level 3580 MWtReactor Coolant Mass 446,486 IbmTime of Reactor Trip 179.0 secTime of isolation of stuck-open 10% ADV on 2653 secthe Ruptured SGTermination of Break Flow from Ruptured SG 3402 secthat flashesTermination of Break Flow from Ruptured SG 5872 secTime of manual depressurization of the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />sRuptured SGBreak Flow to Ruptured Steam Generator that Table 15.5-64C, Column "A"flashesBreak Flow to Ruptured Steam Generator that Table 15.5-64C, Column "B"does not flashTube Leakage rate to Intact Steam Generators 0.75 gpm (total for all 4 SGs;conservatively assumed for 3 intactSGs); leakage density 62.4 Ibm/ft3Failed/Melted Fuel Percentage 0%RCS Tech Spec Iodine Concentration 1 pCi/gm DE 1-131(Table 15.5-78)RCS Tech Spec Noble Gas Concentration 270 pCi/gm DE Xe-133 (Table 15.5-78)Revision 19 May 2010 flCýDD I INITO I Q' 0 CAD I I1flATCTABLE 15.5 64PARAMETERS USED !N EVALUATINGDAMlrnl ft~lKl0Cnl IrCllpr-C Cnt"D C~t"Z_YM AIKIAI VC1l0Sheet-2-ef2TABLE 15.5-64ASTEAM GENERATOR TUBE RUPTUREAnalysis Assumptions & Key Parameter ValuesParameter ValueRCS Equilibrium Iodine Appearance Rates Table 15.5-79(1 pCi/gm DE 1-131)Pre-Accident Iodine Spike Concentration 60 pCi/gm DE 1-131 (Table 15.5-79)Accident-Initiated Iodine Spike Appearance 335 times TS equilibrium appearanceRate rateDuration of Accident-Initiated Iodine Spike 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />sInitial Secondary Coolant Iodine 0.1 pCi/gm DE 1-131 (Table 15.5-78)ConcentrationsSecondary System Release ParametersInitial SG liquid mass 89,707 Ibm / SGIodine Species released to Environment 97% elemental; 3% organicSteam flow rate to condenser from Ruptured 63,000 Ibm/minSG before tripSteam flow rate to condenser from intact SGs 189,000 Ibm/minbefore tripPartition Factor in Main Condenser 0.01 (elemental iodine)1 (organic iodine and noble gases)Steam Releases from Ruptured SG Table 15.5-64C, Column "C"Steam Releases from intact SG Table 15.5-64C, Column "D"Post-accident minimum SG liquid mass for 89,707 IbmRuptured SGRevision 19 May 2010 DCPP UNITS I & 2 FSAR I .PDATETABLE 15.5 64PARAMETERS IUSE=D IN E'VAIIUATINGRADIOLC.ICAL CON£FPOt/NCE£.S 'OR £aTR ANAl YRISSheet 2 of 2TABLE 15.5-64ASTEAM GENERATOR TUBE RUPTUREAnalysis Assumptions & Key Parameter ValuesParameter ValuePost-accident minimum SG liquid mass for 89,707 Ibm per SGintact SGsTime period when tubes not totally submerged insignificant(intact SG)Fraction of Iodine Released (flashed portion) 1.0 (Released without holdup)Fraction of Noble Gas Released from all SGs 1.0 (Released without holdup)Iodine Partition Coefficient 100Termination of Release from intact SG 10.73 hrsEnvironmental Release Points Plant Vent: 0 -179 secMSSVs/10% ADVs:179 sec -10.73 hrCR emergency Ventilation : Initiation Siqnal/TiminrqInitiation time (signal) SIS: 219 secUnaffected Unit inlet damper closed:231 secAffected Unit inlet damper closed:257.2 secControl Room Atmospheric Dispersion Factors Table 15.5-64BRevision 19 May 2010 r'~~f~~fl 1 IMIT 4 ) -OA I.,-. TABLE 15.5 64Sheet 2 of 2PARAMETERS UJSED= IN EVALUATINGD rI~If f'IfAl t 11.IC'fIr I Ifr^ Cf'-r A NIAl /~TABLE 15.5-64BSTEAM GENERATOR TUBE RUPTUREControl Room Limiting Atmospheric Dispersion Factors (sec/m3)Release Location / Receptor 0-179 s 179-257.2 s 257.2 s- 2 h 2-8 hr 8-10.73 rCR Normal Intakes-Plant Vent 1.29E-03 _ __.-MSSVs/10% ADVs (Note 1) 8.60E-04CR Infiltration-Plant Vent [1.26E-03 ----I -----MSSVs/10% ADVs 2.78E-03 2.78E-03 [1.49E-03 1.49E-01CR Pressurization Intake I-MSSVsI1 0% ADVs { 1.57E-05 7.65E06 7.65E-LRevision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATET.ABL 1RI =45.566 5IODINE SPECIFIC ACTI\/ITIESIN THE-F PR IM.ARY Af rD SrEC OND[l'AVRY COOLAN' v+-' SGTR ANALYSS v143214331434t-4350.204i~1430758947.6442.2466.78873436.340070940.02040.411130.01390.0689(a) a6.ed on!1, 60 and 0.1 of Dose E',Spccifications (Referenc~e 22).iivaient 1 431i consiste~nt mitn the uu-G-'R iecnnpipca:Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATET.ABLE I 15. 5 6 6IODINE SPRIKE APPEARPNCE RATES SGTR ANALYSIS(CURIESiSECOND)2-469 4-.92 444 275340ý The accident initiated spike appearance rate is 335 times the equii~brium appcaranco rate. Theequilibrium appearanco rate is calculated based on a total letdoWn flow of 113 gpmA. ThiS total-is6 comprised of 120 gpmn with Pe~fect cleanup, a letdown flow Wnce~taint' of 12 gpmR, 10 gpmn;A nn+FnrA r-.+n ,-nk +l +l !ea Ia!L',na~ A 1i mm nitlnod'fial 1ýLa~n ^ frnn fha rp-j-+^rýri v r-wcxw wr uww cm OTO ur" VC1 cxqý, um RF .- _qGGGaf4-sYste4:Av°Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 657NOBLE GAS SPECIFIC ACTIVITIES IN THEREACTOR COQ'W-,ANITw BASED ON 1% FUEL DEFECTS SGTR ANALYSIS2 .523Xe 133n 3.9i14Xe 133 256.3Xe4135m 044Xe 136 8.663Xe-138 0.56KF 85M 2.414KF 85 6.209B'-ased on a 2 ycar fuel cycle at a core powcr of 3580 MOt, a 75 gpmn reactor coolant system lctdOWn flowrate. and a A004 dpminealizetr iodintz rcmoA;Al effic~iencyRevision 16 June 2005 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 68ATMOSPHERIC DISPERSION FACTORS AND BREATHING RATES SGTR ANALYSISOFFS!TE EXPOSURE-Tie -,,,, Arwu e ..ea .e,,, Lew Pepulation B R2-8 2.2 x le4 3.47 x !0-42--9 2-.24-144 347-xý40CONTROL ROOM EXPOSURETime Centreo Room Filtc,- d Room, Control Ro.-mProssurizatio U.filteed 8Weathing Ratew0-8 7.05 4 4:-4 3.4,7x-148-24 5.38 X .9-x-4-O4 &47-x-4-424-96 3. --1 X8 !-0-- 4 3.4744-04>62.27 W !4-04 3.47-x-!0-4Note 1:Due to the proximity of the release from the MSSVs/10% ADVs, to the normal operation CRintake of the affected unit, and due to the high vertical velocity of the steam discharge from theMSSVs/10% ADVs, the resultant plume from the MSSVs/10% ADVs will not contaminate thenormal operation CR intake of the affected unit. Thus the X/Q s presented reflect thoseapplicable to the CR intake of the unaffected unit.Revision 16 June 2005 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-64CSTEAM GENERATOR TUBE RUPTUREBreak Flows and Steam ReleasesBreak Flow and Steam Release within each Time IntervalA B C DTime Flashed Un-flashed Ruptured SG Intact SGsfrom Break Break Flow Break Flow Steam Steam ReleasesReleases(sec) (Ibm) (Ibm) (Ibm) ibm)0 1678 8422 187822 563100179 2217 30003 10527 42565853 12121 90754 113657 1182653 1355 15906 0 1462953 779 23177 0 854673402 0 45026 0 971644324 0 16870 0 92374739 0 23892 0 291035872 0 0 0 1033007200 0 0 270000 1,342,40038628 0 0 0 0Note: Data in row for T=0 is applicable to time interval between T=0 sec to T=1 79 sec (typ)(a) Regulatory Guide 1.1, Reyision 2, June 1974 (Note: Although rcvisiOR 2 was refc~rcned in theanalysi s, the breathing rates are the same as those in revis~ion I which is the DCPP licensingRevision 16 June 2005 DCPP UNITS 1 & 2 FSAR UPDATE15.-5 6 9THYROID DOQSE CONVERSION FACTORC ST AAYINUokde1431i4321433'434143514.0 x10 ReRmCufie)6.2 x103 Rem/Ci~u4.1 x Q5 Re miG wfi4.7 4Q3 Remi ufie)3.4X4g4(RemiCufie}SIntem~Won~I Commies~on on RadioIoc~icai Protection PubIic~tion 30, 1979.Revision 18 October 2008 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 709AVERAGE GAMMA AND BETA ENERGY FOR NOBLE GAS, SES SGTR ANALYSIS(MeVdis)Ng~llde +1-31 0,39 04-91132 24 0-52I i33 0-6 0421434 2-.6 0761-435 474 0743Xe434R4 070029 0-4-6Xe133m 0,02 0724Xe1-33 0703 044Xe-435m G-.43 0.099Xe135 02-5 0,32Xe-438 4-2 0,46K86G44 Q-.2-Kr 85m 0-71602KF 85 0.0023 0-.2-5K-_7-9 14KF88 0725(a) ENIDFl 223, ctobeFr 4975 (Reference 36)Revision 16 June 2005 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 71OFFSITE RADIATION DOSES FROM SGTR ACCIDENT-Value --Alloeable Guideline1. AGcId~ent initlatea Iod6ne DE=,-lUio, Area O-u.da ' (0 2 hr.)T-hyroid ODE-LoGW Population Zone (9 8 hr.)Thyroid ODE-2. Pre Accident Tdine SiExclusion Area Boundary (0 2 hr.)Thyroid ODELoW Population Zone (0 8 hr.)Thyroid ODE-3. Acciden~t Ini;tiated lodinc Spike4-303w03w0Exc-Jusion Area Bo11 AC-1a FWfloe Bogy Gamma 'UULow Po9pulation Zone (0 8 hr.)Whole Body Gamma DDE4. Pre Accident Initiated Iodine SpikeWhole Body Gamma DoseExclusion AFea Boundarf (0 2 hrWhole Body Gamma DDELow Population Zone (0 8 hr.)Whole Body Gamma DDE04020-32-5-I I --f'% 1-1 i i O~e i1Mii G+ AW. F8Fm Flab 191n zppFOWeU mU rt-mu Plow au en 4,0,6 KefeFo iu~co15..202.1(6 Tor funnher diSGUssin.Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 72CflINT-OL R Mffl~ PAPAFIAITID USE IN~f lid 1AA IATIKI( AD~fIG!GI 'CifALCONMRFOLENICES POR RQT-R ANIAl Y212Control -Room -Irolatio-n Signal Generated- Tome o-f Sa I~e-44~r- rn'-Delay in Cont-rol Roo-m IsolAtion A~ftper Isolation Signal is 35 seGG~dSGenefated__Control Room Volume 14O7O,-G"3Control ROOM Unfiltered In -leakage 40-.-fnControl Room Unfiltered I&nfoNormal 4200-.friEmrmgencY Mode G-ofmControl Room Filtered InflowNormal Mode -flEmnergencY Mode 2440-GfmIControl Room F=iltered Reci~rcultoEmergencY Mo.Qdep 2400-efmControl Room Filter Efficienc 9"0Revision 16 June 2005 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 74CONTROL ROOM RADIATION DOSES FROM AIRBORNE ACTIVITYIN SGTR ACC!DENT.Acc-iden-t InitiatedP~e AGGiden~Guideline, remThYFGid M(0 30 days-)Whole Body DIDE(9 30 days}Betza Skin SDEr(0 39 days)0,2Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5 75SUMMARY OF POST LOCA DOSES FROM VARIOUS PATHWAYS(l OF 410%THYROID DOSES, remaEA1- 2 heur10 GrFR Part 100Containment LeakageRHR Pump Sea! (50 gpm)Pre existing leak (1910 cclh4r)300i0 .0a9a147223004g~gi07009241-2T-etalW--HOLEF RODY DORPS rmmEAR 2 how%10 CER Part 100Ggntainment LeakageRHR Pump Seal (60 gpm)Pre existing leak (1910 ýh")Tont;;2-53,243,272-50.2930700.0030.296Revision 19 May 2010 DCPP UNITS 1 & 2 FSAR UPDATETABLRIE 15.5 7-6",AOLE BODY DOSE CONVERSION FACTORSxDOSE EQUJIVALENT XE 133Nu~ideKF-85Fm 7.4R-F 15 (Sy mFBq-s"K-r- ,4. 1 4 (Sy, ,.BKFr-88 1.02E 13 (Sy m3iBXe-33F 1.37E 15 (Sy mWBXe 133 1.56E 15 (SV m1Xe 13m 2.0 F 4(Sy-mF/8q-sXe435 !.!E-4 (Sy mBXe-1-3 5.77-F I4 (Sy m/Be-sS-,-Tble 111.1 of Federal Guidance Repo"t 12, EPA 02 R 93 081, 1993.04 Noto the qAOQR use;cnsr-miv vluS wi.th respect to the above.
DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-77DCPP EQUILIRIUM CORE INVENTORY (Power Level: 3580 MWth)Dose Significant Isotopes including the Parent, Grandparent and 2nd Parent IsotopesACTIVITY ACTIVITY ACTIVITY(CURIES) (CURIES) (CURIES)AG-110 2.67E+07 IN-125 8.46E+05 SB-125 9.63E+05AG-11OM 6.92E+05 IN-127 1.86E+06 SB-127 9.14E+06AG-111 7.09E+06 IN-129 3.55E+06 SB-129 3.25E+07AG-111M 7.09E+06 IN-131 1.09E+06 SB-130 1.08E+07AG-112 3.16E+06 IN-132 2.85E+05 SB-130M 4.38E+07AG-115 6.21E+05 KR-83M 1.14E+07 SB-131 7.67E+07AG-1I15M 2.60E+05 KR-85 1 11 E+06 SB-1 32 4.70E+07AM-239 4.90E-01 KR-85M 2.33E+07 SB-132M 4.37E+07AM-241 1.32E+04 KR-87 4.65E+07 SB-133 6.32E+07AM-242 9.40E+06 KR-88 6.43E+07 SB-134 1.14E+07AM-242M 8.54E+02 KR-89 7.94E+07 SB-135 5.46E+06AM-243 5.28E+03 KR-90 8.48E+07 SB-136 8.63E+05AM-244 3.79E+07 KR-91 5.83E+07 SE-83 5.38E+06AM-245 1.12E-03 KR-92 3.12E+07 SE-83M 5.65E+06AS-76 3.05E+03 KR-93 1.07E+07 SE-84 2.04E+07AS-83 7.02E+06 KR-94 5.OOE+06 SE-85 9,54E+06BA-137M 1.30E+07 LA-140 1,85E+08 SE-87 1.32E+07BA-139 1.76E+08 LA-141 1.61E+08 SE-88 7.15E+06BA-140 1.78E+08 LA-142 1.57E+08 SE-89 2.49E+06BA-141 1.59E+08 LA-143 1.48E+08 SM-153 6.04E+07BA-142 1.51 E+08 LA-144 1.31E+08 SM-155 4.30E+06BA-143 1.29E+08 MO-99 1.84E+08 SM-156 2.66E+06BA-144 9.93E+07 MO-101 1.69E+08 SM-157 1.70E+06BR-82 4.44E+05 MO-103 1.62E+08 SN-121 8.43E+05BR-82M 3.88E+05 MO-104 1.33E+08 SN-123 6.43E+04BR-83 1.13E+07 MO-105 9.97E+07 SN-125 5.25E+05BR-84 2.10E+07 MO-106 5.86E+07 SN-125M 1.58E+06BR-85 2.31E+07 NB-101 1,59E+08 SN-127 3.69E+06BR-87 3.67E+07 NB-104 5.10E+07 SN-127M 4.95E+06BR-88 3.52E+07 NB-95 1.66E+08 SN-129 1,28E+07BR-89 2.45E+07 NB-95M 1.89E+06 SN-129M 1.17E+07BR-90 1.35E+07 NB-97 1.59E+08 SN-1 30 3.28E+07CD-115 9.17E+05 NB-97M 1.50E+08 SN-13i 2.83E+07 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-77DCPP EQUILIRIUM CORE INVENTORY (Power Level: 3580 MWth)Dose Significant Isotopes including the Parent, Grandparent and 2nd Parent IsotopesISOTOPE. ACTIVITY ISOTOPE* ACTIVITY ACTIVITY(CURIES) (CURIES) (CURIES)CD-115M 4.43E+04 NB-99 1.07E+08 SN-132 2.28E+07CD-121 7.67E+05 NB-99M 7.35E+07 SN-133 6.21 E+06CE-141 1.63E+08 ND-147 6.59E+07 SN-134 1.07E+06CE-143 1.50E+08 ND-149 3.90E+07 SR-89 9.05E+07CE-144 1.26E+08 ND-151 2.08E+07 SR-90 9.67E+06CE-147 6.18E+07 NP-238 6.20E+07 SR-91 1.13E+08CF-249 2.46E-02 NP-239 2.16E+09 SR-92 1.22E+08CM-241 3.54E+00 NP-240 6.23E+06 SR-93 1.39E+08CM-242 5.88E+06 PD-109 4.73E+07 SR-94 1.39E+08CM-244 1.31E+06 PD-109M 3.12E+05 SR-95 1.25E+08CM-245 1.26E+02 PD-111 7.09E+06 SR-97 4.68E+07CO-58** O.OOE+00 PD-112 3.14E+06 TB-160 1.87E+05CO-60"* O.OOE+00 PD-115 7.84E+05 TC-99M 1.63E+08CS-132 5.75E+03 PM-147 1.68E+07 TC-101 1.69E+08CS-134 2.41E+07 PM-148 1.88E+07 TC-103 1.65E+08CS-134M 5,63E+06 PM-148M 2.83E+06 TC-104 1.40E+08CS-136 7.01E+06 PM-149 6.43E+07 TC-105 1.18E+08CS-137 1.37E+07 PM-151 2.10E+07 TC-106 8.80E+07CS-138 1.85E+08 PM-153 9.77E+06 TE-127 9.03E+06CS-139 1.72E+08 PR-142 9.47E+06 TE-127M 1.52E+06CS-140 1.54E+08 PR-143 1.47E+08 TE-129 3.1OE+07CS-141 1.17E+08 PR-144 1.27E+08 TE-129M 6.30E+06CS-142 6.80E+07 PR-144M 1.76E+06 TE-131 8.28E+07CS-143 3.41E+07 PR-147 6.52E+07 TE-131M 2.04E+07DY-166 4.91E+02 PR-149 3.57E+07 TE-132 1.41 E+08EU-154 9.OOE+05 PR-151 1.23E+07 TE-133 1.09E+08EU-155 3.83E+05 PU-238 5.22E+05 TE-133M 8.93E+07EU-156 3.90E+07 PU-239 3.06E+04 TE-134 1.75E+08EU-157 4.12E+06 PU-240 4,87E+04 TE-135 9.68E+07EU-158 1.01E+06 PU-241 136E+07 TE-136 4.29E+07EU-159 5.15E+05 PU-242 3.34E+02 TE-137 1.45E+07GA-72 1.71E+03 PU-243 7.36E+07 TE-138 3.65E+06GA-77 1,66E+05 RA-224 5.16E-01 TH-228 5.14E-01GD-159 8.91 E+05 RB-86 2.50E+05 U-239 2.17E+09GE-77 6.48E+04 RB-86M 2.07E+04 XE-131M 1.42E+06 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-77DCPP EQUILIRIUM CORE INVENTORY (Power Level: 3580 MWth)Dose Significant Isotopes including the Parent, Grandparent and 2nd Parent IsotopesISOTOPE* ACTIVITY ISOTOPE* ACTIVITY ISOTQPE* ACTIVITY(CURIES) (CURIES) (CURIES)GE-77M 1.70E+05 RB-88 6.60E+07 XE-133 2.01E+08GE-83 1.24E+06 RB-89 8.57E+07 XE-133M 6.42E+06H-3 6.10E+04 RB-90 7.86E+07 XE-135 4.92E+07HO-166 258E+04 RB-90M 2.53E+07 XE-135M 4.30E+071-129 4.OOE+00 RB-91 1.05E+08 XE-137 1.84E+081-130 3.58E+06 RB-92 9.35E+07 XE-138 1.70E+081-130M 1.92E+06 RB-93 7.89E+07 XE-139 1.25E+081-131 9.90E+07 RB-94 4.13E+07 XE-140 8.66E+071-132 1.44E+08 RB-95 2.01 E+07 XE-142 1.33E+071-133 2.01 E+08 RH-103M 1.66E+08 Y-90 1.02E+071-134 2.22E+08 RH-105 1.08E+08 Y-90M 7.71 E+021-134M 2.07E+07 RH-105M 3.43E+07 Y-91 1.19E+081-135 1.92E+08 RH-106 7.53E+07 Y-91M 6.57E+071-136 8.73E+07 RH-109 3.65E+07 Y-92 1.23E+08I-137 9.40E+07 RN-220 5.16E-01 Y-93 9.41 E+071-138 4.80E+07 RU-103 1.66E+08 Y-94 1.50E+081-139 2.22E+07 RU-105 1.21 E+08 Y-95 1.57E+081-140 6.06E+06 RU-106 6.68E+07 Y-97 1.26E+08IN-115M 9.17E+05 RU-109 3.16E+07 ZN-72 1.71E+03IN-121 7.55E+04 SB-122 1.57E+05 ZR-101 9.55E+07IN-121M 7.82E+05 SB-122M 1.57E+04 ZR-95 1.65E+08IN-123 6.87E+05 SB-124 1.21E+05 ZR-97 1.58E+08SB-124M 2.34E+03 ZR-99 1.66E+08Note:* Isotopes in Bold Font are dose-significant for inhalation, submersion and direct shine. The parent, grandparentand second parent of the isotopes in Bold Font are also required to address daughter product in-growth.The group of isotopes needed to determine the "submersion and inhalation" dose in the Control Room and at theSite Boundary is typically a subset of the isotopes listed above in bold font, and represent a small group ofreasonably long half-life isotopes with significant inhalation dose conversion factors which dominate the TEDEdose.To determine the total effective dose equivalent (TEDE) resulting from inhalation and submersion following aLOCA, the DCPP LOCA dose consequence analysis uses the default group of 60 isotopes provided with computercode RADTRAD 3.03 plus 13 additional nuclides that were deemed to be dose significant (i.e., Br-82, Br-84, Rb-88, Rb-89, Te-133, Te-133m, Te-134, 1-130, Xe-131m, Xe-133m, Xe-138, Cs-138 and Np-238).** Co-58 / Co-60 are activation products that are developed external to the core and typically do not appear in theequilibrium core inventory DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-78PRIMARY AND SECONDARY COOLANTTechnical Specification Activity ConcentrationsNuclide Primary Coolant Secondary CoolantNue(uCi/am) (uCi/m)Kr-83M 1.87E-01Kr-85M 6.60E-01Kr-85 5.60E+00Kr-87 4.41 E-01 -----Kr-88 1.22E+00 -----Xe-131M 1.88E+00Xe-133M 1.92E+00Xe-133 1.29E+02Xe-1 35M 4.07E-01Xe-1 35 3.76E+001-131 7.87E-01 8.06E-021-132 2.99E-01 1.94E-021-133 1.16E+00 1.08E-011-134 1.67E-01 4.78E-031-135 6.68E-01 5.09E-02 DCPP UNITS 1 & 2 FSAR UPDATETABLE15.5-79PRIMARY COOLANTPre-Accident Iodine Spike Concentrations & Equilibrium Iodine AppearanceRatesPre-Accident Spike Equilibrium Iodine ActivityRCS Concentrations Appearance Rates into RCS(60 pCi/gm DE 1-131) (pCi/sec)Nuclide (PCi/gm)1-131 47.2 7.18E+031-132 17.9 7.78E+031-133 69.5 1.25E+041-134 10.0 8.91 E+031135 40.1 9.91E+03 DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-80ISOTOPIC GAP ACTIVITYLOCKED ROTOR ACCIDENT / CONTROL ROD EJECTION ACCIDENTFraction of Core Gap Fraction of Core GapCore Activity Core ActivityCore Activity in w/o Peaking Activity in w/o PeakingActivity Gap Factor Gap FactorNuclide (Ci) LRA (Ci) CREA (Ci)LRA CREAKR-85 1.11E+06 0.30 3.33E+05 0.10 1.11E+05KR-85M 2.33E+07 0.10 2.33E+06 0.10 2.33E+06KR-87 4.65E+07 0.10 4.65E+06 0.10 4.65E+06KR-88 6.43E+07 0.10 6.43E+06 0.10 6.43E+06Xe-131M 1.42E+06 0.10 1.42E+05 0.10 1.42E+05Xe-133M 6.42E+06 0.10 6.42E+05 0.10 6.42E+05XE-133 2.01E+08 0.10 2.01E+07 0.10 2.01E+07XE-135 4.92E+07 0.10 4.92E+06 0.10 4.92E+06Xe-138 1.70E+08 0.10 1.70E+07 0.10 1.70E+071-130 3.58E+06 0.10 3.58E+05 0.10 3.58E+051-131 9.90E+07 0.12 1.19E+07 0.10 9.90E+061-132 1.44E+08 0.10 1.44E+07 0.10 1.44E+071-133 2.01E+08 0.10 2.01E+07 0.10 2.01E+071-134 2.22E+08 0.10 2.22E+07 0.10 2.22E+071-135 1.92E+08 0.10 1.92E+07 0.10 1.92E+07BR-82 4.44E+05 0.10 4.44E+04 0.10 4.44E+04BR-84 2.1OE+07 0.10 2.1OE+06 0.10 2.1OE+06CS-134 2.41E+07 0.17 4.1OE+06 -CS-136 7.01E+06 0.17 1.19E+06 -CS-137 1.37E+07 0.17 2.33E+06 -CS-138 1.85E+08 0.17 3.15E+07 -RB-86 2.50E+05 0.17 4.25E+04 -Rb-88 6.60E+07 0.17 1.12E+07 -Rb-89 8.57E+07 0.17 1.46E+07Note: Values reported reflect the core isotopic gap activity assumed for the LRA and CREA. Thesevalues have to be adjusted for a) the failed fuel percentage (10%) and b) peaking factor (1.65), prior toassessing the associated dose consequences.For the isotopic gap activity associated with the FHA refer to Table 15.5-47C.
DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-81CONTROL ROOMAnalysis Assumptions & Key Parameter ValuesParameter ValueFree Volume 170,000 ft3Unfiltered Normal Operation Intake Total 4200 cfm +/- 10%Unit 1:2100 cfm +/- 10%Unit 2: 2100 cfm +/- 10%Emergency Pressurization Flow Rate 650 -900 cfmMaximum Unfiltered Backdraft Damper 100 cfmLeakage during CR Pressurization OperationCarbon / HEPA Filter Flow during CR 1800 -2200 cfmPressurization OperationEmergency Filtered Recirculation Rate 1250 cfm (minimum)Pressurization Intake and Recirculation 93% (iodine)Carbon/HEPA Filter Efficiency 98% (particulates)(includes filter bypass)Unfiltered Inleakage 70 cfm (maximum)(Normal and Pressurization Mode) Includes 10 cfm ingress / egressOccupancy Factors 0-24 hr (1.0)1 -4 d (0.6)4-30 d (0.4)Operator Breathing Rate 0-30 d (3.50E-04 m3/sec)
DCPP UNITS 1 & 2 FSAR UPDATETABLE 15.5-82TECHNICAL SUPPORT CENTERAnalysis Assumptions & Key Parameter ValuesParameter ValueFree Volume 51,250 ft3Filtered Rate (HEPA only) Normal Operation Intake 500 cfmFlowNormal Intake HEPA Filter Efficiency(includes filter 98% (particulates)bypass)Filtered (Carbon / HEPA) Pressurization Flow Rate 500 cfmFlow through Carbon / HEPA Filter during 1000 cfmPressurization modeFiltered Recirculation flow rate during Pressurization 500 cfm (minimum)modePressurization Intake and Recirculation Carbon / 93% (iodine)HEPA Filter Efficiency (includes filter bypass) 98% (particulates)Unfiltered Inleakage 60 cfm (maximum)Includes 10 cfm ingress/egressOccupancy Factors 0-24 hr (1.0)1 -4 d (0.6)4-30 d (0.4)Operator Breathing Rate 0-30 d (3.50E-04 m3/sec)