Text

Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - Updated Final Safety Analysis Report Markup, Revision 1. Part 3 of 3
	ML16004A359
Person / Time
Site:	Diablo Canyon
Issue date:	12/17/2015
From:	; Pacific Gas & Electric Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16004A363	List: DCL-15-152, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - Updated Final Safety Analysis Report Markup, Revision 1. Part 3 of 3; ML16004A354; ML16004A355; ML16004A356; ML16004A357; ML16004A361;
References
	DCL-15-152, TAC MF6399, TAC MF6400
	Download: ML16004A359 (101)
	v • d • e

DCPP UNITS 1 & 2 ESAR UPDATE TABLE 15.5-9A LOSS OF ELECTRICAL LOAD ANALYSIS ASSUMPTIONS & KEY PARAMETER VALUES Parameter Value Power Level 3580 MWt Reactor Coolant Mass 446,486 Ibm Primary to Secondary SG tube leakage 0.75 gpm (total for all 4 SGs); leakage density 62.4 Ibm/ft3 Failed/Melted Fuel Percentage 0%

RCS Technical Specification Iodine Levels Table 15.5-78 (1 pCi/gm CE 1-131)

RCS Technical Specification Noble Gas Levels Table 15,5-78 (270 pJCi/gm CE Xe-133)

RCS Equilibrium Iodine Appearance Rates Table 15.5-79 (1 IpCi/gm CE 1-131)

Pre-Accident Iodine Spike Concentration Table 15.5-79 (60 pCi/gm CE 1-131)

Time period of tubes uncovered insignificant Steam Releases 0-2 hrs: 651,000 Ibm 2-8 hrs: 1,023,000 Ibm 8-10.73 hrs: same release rate as that for. 2-8 hrs Iodine Partition Coefficient in SGs 100 Iodine Species Released to Environment 97% elemental; 3% organic Fraction of Noble Gas Released 1.0 (Released without holdup)

Termination of releases from SGs 10.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months Environmental Release Point MSSVs/10% ACVs CR emergency Ventilation :Initiation Control Room is assumed to remain on Signal/Timing normal ventilation for duration of the accident.

Control Room Atmospheric Dispersion Factors Table 15.5-9B Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-9B LOSS OF ELECTRICAL LOAD Control Room Limiting Atmospheric Dispersion Factors (sec/in 3)

Release point and receptor 0-2hr 2-8 hr ]8-10.73 hr MSSVs/1 0% ADVs to CR NOP Intake (Note 1) 8.60E-04 5.58E-04 5.58E-04 MSS Vs/i10% ADVs to CR In leakage (CR 2.78E-03 1.63E-03 1.63E-03 Centerline)

Note 1: Due to the proximity of the release from the MSSVs/1 0% ADVs, to the normal operation CR intake of the affected unit, and due to the high vertical velocity of the steam discharge from the MSSVs/10% ADVs, the resultant plume from the MSSVs/10%

ADVs will not contaminate the normal operation CR intake of the affected unit. Thus the

%/ s presented reflect those applicable to the CR intake of the unaffected unit.

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.51!0 Sheetl!of !

A SM/ALL LOS OFNq tC OtOlAT ACCIDENTE Tlhyroid Dose, remn 10 CFRPartQ !0

-GO,8 E-xfpe, e#edase*

8*Ox4t 4 1.2-x"'40

-0 CFR Part 100 2-5 2-5 Design b,-sis....

e 1.8-x-!04

5.

!0 Population Dosema e

Design basis ca.e 0-36 Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1 5.5- !1

SUMMARY

OF OFFSITE DOSES FROM

,AN UNDERFREQUENCY ACCIDENT

! 0CFR Part 100 3-0 300 E-xp5.ted-!0-e z.60xx!0-Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 12

SUMMARY

OF OFFSITE DOSES FROM A Sl.N(! F.flfl ('I H LTFP ('fINTRC)

A.£F.M.Rl Y *AJlT~uf.r~A*.Al Thyroid Dose.,.rem Sita

n Bondr;4-,,

2.in Horr Dein basis* cae E-x;er*

d-e;a s

~42 4

~75-x40 07043 Whole Body Doses, rem

~;+a I 2 n1 Inrmnr,,

0 I-Mi,rc I [37 _ "*t* r*.*#

10 CFR Part 100 Design basis case

~xpeeted-eas~

2-5 6.! x !04 25*

6.7 -x-1!04 Population Doses, man rem Design basis case

~peeted-ease-0*4 Revision 19.May 2010

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15.5-13 C.ALCUL. TED ACTIVIJv RELEASES~ FRnOM LOCA. EXPECTED CASE/r (CURJES N~ide 0-24w-2-84h 8-2A4-h-24-984-h*

-gDy

-t-8-1 0.4!05E0 0-0-0 0 b4~0.8675E-02 0-0 0-0 0-0 0-1-434 0.7392E-02 0-0-0 0-0 0-0 443,8 0.!829E-01 0-0 0

0--

I1!31ORG 0.1"121E 01 0.3356E 01 0.4701E 01 0.184!E-0!

.46E0

! !320RG O.178nE 02 0.1556E 02 0.2210E-03 0.343!E-06 0.6!138E-1!7

!43AORG 0.!3!4E-02 0.2862E-03 04780 0-074 11!350RG 0.51 39E 02 0.8365EB02-0.710 0.!933E 03 0.-730E ! !31-PAR 0,0 0-0-

'0-0 0-0

! !33PAR 0-0-

0-0 0-K-'Fr3M1 K-38M Xe-133M X~e-1-35 Xe43,8

0. 3823EB 00 0.1535B 0!1 0.561750 02

0. 9285B 00 0.6662EB 0!1 0.1289B 00

0. 39 57E 00

0. 3085EB 00 0.2869E 0!

g.6227E 00 0.-!,192E 01

0. 2650 E 0!1 0.1190B 02 0.6268E 03 0.1035E 02 0.36 8 EB-01 0,4257E 02 0.16 89EB 01 0.2130EB 01 011!8gB 01 0,413gB 03 0.!1826EB02 0.7!07EB!0 0.181g.0 10 0.l757EB01 0.7387E 01 g.1022EB05 0.1097B 0!

0.73509B 03

0. 8236 B 01 0.3887B 01 0.1070E 28 01917E--3-!1 0-8243E-03 0.87-75E-06 0.1515EB22 0.!6!8E09 0.1169B 01!

0.55g6B 01 0.1721E 01 0-0 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TA.BLE 15.5 !'!

I-*i*!<n I--I A l'*h"*

i*

^ i"*r-- It'll ir'lll--l-I\\

i. :D.! ! :l li. *. ! *-! I /\\!

! !V!

! ¥

.I-*. *-.! P.*..':P.'*. PP*.t JPd! LD]t.P. - U*<-h!t-P.*

"--./\\*13 DP.*.*.*- IL.'J.W.l*-31 O2Hr 2-8Hrk 22~Hr 2",96 Hr

!1131QR

!-!320RG

I--33RG I-135 ORG

!-132 PAR I 135 PAR Kr-85M Xe-4,-M 0.2705E 02 0.6207E 02 O.7063E 02

0. 57!2 E 02 0.7310E 02 0.8325E 02 0.111!E 03 0.9175E 02 0.1011E 03 0.2018E 03 0.!761E 03 0.2823E O4

0. 3817 E 01

0. 7090 E 01 0.1684E 05 0.4250E 03

0. 71 02E 01 0.8506E 03 0.250-!,E 0' 0.2170E 03 0.8763E 02 0.2169E028 0.2838E 03 0.2713E 03 0.5392E 03 0.35rSE 03 0.7487E 03 0.1!660E 0'!

0.1861E 0-!

0.818"!E 0-0.,-942E--5 0.1212E 0"1 0.1655E 05 0.4 137E 01 0.6552E 01 0.556!E 03 0.!62E-02 0.8078E 03 0.2015E 00 0.2668E 0.6951E 03 0.2327E -02 0I4-E- 0.2557E 00 0.3335E 03

0. 50 97E 03 0.2723E 0-!

0.7273E 02 0.2388E 04 0.!211E 06 0,28!9E 0"!

0.2028E 05 0.1690E-06 0,!!61E 06 0%0 0.1070E 01 0.9240E 0!

0.5263E-03 0.28!IE-06 0.3l4gE 0.6579E 03 0.35!l4E 06 0.1151E 00 0.!11 5E 01I 0.1191E 03 0"1*575'am-0a3 0.2220E 0,2205E-06 0.376gE-04 0.1316E 0"!

0. 706!IE 25 0.12 52 E 27 0,9 4,0

0. 3227E 01!

0.8557E1!0 0.2665E-3!

0.!834E-0!

0.1033E 01 0.1070E-09 0.6728E-02 0.~3341E-3!

0.2293E 0!

0.2578E-12 0..9827 E 01!

0.1113E 02 0.1530E1!9 0.43 92E 06 0.2556E 0'!

0.91E0 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 15 I I--I v I.,

U U1 I

L Z1,*I-.

I.-IU*1I1-<

UU-t" IJxlirL IIJMtlI. N I i

/-. \\IK/V.:*

- yIII-I

-, iU 1W L/,..-

\\

~ (X.,. l-IM),

Distanoc From Rolcaso Point, mctcrs NiucAid 800 4*gg

ggg 4000 WOO

~OO0

ggg-11 !3ORG

! !33ORG J1!3IORG

!11350RG I 1332PAR I-t131P-AR 11!35 PAR 0*3~83E05 0.127-E-03 O.2268E 05 O.2-!79E 0-!

O.4031E 05 0.7820E 05 O.1792E 03 0.98! lE 01 0.!45&E 05 0.1663E 03 0.7511E 06

0. 33!l0B 0-1 0.2591Bp06 0.5 026EB 05 0,0

0. 2636EB 03 0.151!9B 05

0. 5398 B-01 0.8017B 06 0.8763B 05 0.9115B 0-!

0.1132B 0s 0.1820B 0-!

0.1125EB0s 0.2761BE 0 0,0 9,0 0.1097Bp03 0.64"15E 06 0.2216B 04 0.3336E-06

0. 3616EB 05

0. 3805EB 01!

0.1719B 06 0.7573Bp05 0.5929EB07 0.1150B 05 9,40 0,0

0. 5060EB-01 0.2971BE-0 0.!36E 04 0.1539B 0s 0.!82E 05-0.1756E 01

0. 7933EB-07 0.3495B O§ 0.2 73 5E 07 0.5307-E 0,0 0,0 0.3!0!1B0,1 0.1!823B-06 0.6350E-05 0.9432E 07 0.1076E 0"!

0.4802E 07 0.21A2E-05

0. 1577B 07 0.3252E 06-9,0 9,0 9,0 0.1217EB01 0.7332EB07 0.254E-05 0.37-94E-07 0.4147-E-06 0.1328B 05 P.19 56EB 07 0.86!-5E 0O

0. 57 lE 08 0.1308B 06 0,0 9,0 90=

Q,0 0,0 TOTAL 0.!249E 02

0. 8030 B 03 0.1116EB03 0.18 37EB 03

0. 8179 B-01 0.5109BE01 0.2090EB01 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 17 THYRID#"*P DOSE3Q[ 30P DAY CO"NTAINlMEN"&T LED,#AKAGEI EXPECI'TEDI C*AS (REM)l~~l/

Di#stanc rmRleaseP

-ete-s.

N*e 80 00 2000 4000

-7000 410000

-0200 1110.7456E 3

079E03 0.2636E 03

~

0. 07 03 Q'Q8-84 030!E 0.1247E-04 14,-04323E0 0-.28A!7 E05

-440-

.45-0 0.2974 E 06

0. !823E-06 0.732E-07

-P42, 0.!527E 03 0.98!4E 04 0.5308E 0"!

02216E-04 0.1036E 01 0.6350E050 4-434 0,2a6gE--g5 045E0 0-0-E0 0.3336E-06 0.!53~9~E-06 0.9432,E-07 0.3794E-07

-I43,5-0.2179E 04

.59E 0.8763E 04E0 0.!82E 05-0.103!

5g.44--

!-!310RG 0.1252E 02 0.754!3E03 0.3960E-03 0.1 587E 03 0.7223F-0"4 0.4452E-04 0.1752E-04 I-1--2-GRG 0.2250E-05 0.1438E-05 0.7382E-06 O-32-70-OE-g 0407-6 g0)2426-0 0.371-3E-07 I-! 33ORG 0.20916E03

0. ! 80E-03 0.6707E-04 0.27516E01

0. !57E-04 0.7734 E-05 0-.307160-5 I1!34ORG 0.4!E 031-55E-0,8 0!3E0 0.72226-07 0.3332E-07 0.2042E-07 0.8215E608 11!35ORG 0.2352E604

.43E0 0.7955E-05 0.3261E605 0.1198E605 0.9202E 0-3676-0E-6 P3-! !PAR 0-0-

0-010 0-0 0,00-I !35PAR 0-0, 0-0, 0-Q,

-TOT-AL-0.4!E02.46E--g2 0*g4E-g2 045-06--3

0. 1,56E 03 0-4560 0.35656E-04 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 19 WHOL'1E: BODY3r~ DOSE~l 2 HOUR'*

CONtTAINMENr-T LErAK*AG*E:

EXPECTEDi CAS:E (REMi)A i-134-0.342E 00

.95 6

0!7E0 0.4474E 7 0.2065E-07 0.1265E 07 058E L'3 0,274A06 F*

009r A0-8020cc 07 0 q2AA4 07 0.53EoA' 7

0-945AEI00 0-84*

n 41n43 3

0r-n I4***

0.12E0 0*A-28 n'-

0.!742E-07 n"nEn b--14 g-44E0

.!5 6

0.65!707 o.2711E 07 0.!25!E 07J 0.7867E-08 0.3084E-08 1150.4245E-0g 0.2729E06

.5!E0

.600 0.288!E 0.!6E-07 0.-7!02E-08

! !3!OR0 O,!055E 06 0.6781E 07 0.3731E 07 0.!552E 07 O.7163E 08 0.4389E-08 0.!766E 08

!- 2QRG 0*6066E-07 0.3899E-07 0.2A4E-',E0,7-0-,924E-0=4

0. !!7E08 0.2523E-08 0.10!5E-08 1 1330RG O.!"1,3E 06 o.9082E 0

.95

-2707 7

-59 80.5876E-08 0.2364!E-00

! !34OR~G 0.3277E 07 0.2106E 07 0.1!58E0,7-0,48!9E 08 0.2224E-08 0.!363E08 0.5482E 09

!-1350RG 0.1339E 06 o.8608E 0

.7",E0

.!7E 07-90908 0.570E 0g 0.22"A4!E-08 b1AR0-0-0 0.0 0-0-0 0~g 0-0

! !35PAR 0-0 0-0-

0-0 0-0 0-0 0-0 Kr-330!!5 6

.23E0 0.6771E 07 0.2817E 07 0.!300E 07 0.95 80.3204E-08 kr-85 0.!49E00 0.94 395 05 0.5192E 05 0.2160E505 0.99~67 00 0.6!0806.25E0 K*9 000E 05 0.57815E05 0.3181E505

~ 0.1205 0.6108E506 0.3743E-00 r-.-g.7--4 0.3083E 04 0-.16965018 0.7058E 05 0.3256E 05 0.!99E-05 0.8028E-00

-88.!0803 0.6735E 04 0.30 -0 0.1515".!E01

.!!E0 0.4358E05 0.!753E-05 0.!24E 03 0.8097E501 0.1153E50-!

0.1853E01 0.8550E-05 0.5239E-05 0.2108E-05 X13A0.285gE-05 0.1708E505 0.9396E506 03~90950-6 0.1804E506 0.1105E506 0.1117507g X~e-l33 0.17615E01 0.3062E501 0.1!6815 E01 0.7006E 05 0,3233E-05 0-.1981-5-05

~

99-X-e13SM 0.8720E 96 0.5605E506 0.3083E-06 0.1282E506 0.591 85 07 0.3627E-07 0.1159E-07 Xe-1..38 0.46-8

.69E0

,3353505g g-400,E-g 0.6437E-06 0-,945E--06 TOTL.3653

.0

.38 3

0 2!E0

.33 4 g-.4-78-0

!E 0.6112E505 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 21 WhHOLE BODYA'*

DOSEl:

30R DAY CONMTA'INMEN*T I =LE(At"AGE EXPECDI::TEDI CASE:: (REM)l" D-_istaneo From Relac "ont

,ee 1131t 0.30A2E 00 0.!955E 06 0.1075E-06 0.1174E 07 0.05 70.1265E 97 0*:089E-0&

0.24 6

0.!62E 06 0.8039E-07 0.83M4E07 0.1513E 07 0.95E 8

03804E 08' 0.4 !90E 06 0.2693E 0

.!",!E0 O.612E-7 0284E-0.! 42E40

.00E0 1--14 O-At4aE--06 0AO~g-1---O7 0.2714!E-07 0.!25! -E-07 0.-7667-E--O 0.3084E-08 I1!3!ORG 0=5-109E-06 0.3078E-06 0.1616E 06 0.6474E 7-0.2947E-07 0.!8!6E-07 0.71 87E 08 1-432O0,-

0-1467-E-06 0W-~46aE--O-0O9OE--07

-469-7-E-07 0.-7822E-0g 0.4796E-0B 0-4927-7.08 11!330RG 0.5738E 06 0.3511E 06 0.1865E 06 0.590 0.8448E-07 0.2!22E-07 0.8435E-08 I1!3IORG 0.3992E 07 0.28566E07 0.!4!11E 07 0.5870E 08 0.209 0&

0.!680E-0&

0.-677E-09 i 1350RG n Ano28En6 0.2522E,06 n0.136l2_n6 0.5,590r-7 n

45RIn E I

-0*I 07 6301E08*

P4!3!PAR 0-0,0 0-0 0-0-

0-4-!42~PAR 0,0 0,0 0,O 0-O Q0O 0-0 0,0

! !33PAR 0-O 0-0 0-0 0-0 0-0 0-0 0-O 14!-!.PAR 0-0 0-0 0-0 O-0 O-O 0-O O-0 b1! 5PAR 0-0 0-0-

04g 0-0 r-,M0.3536E06.23E06 0.!24!E 06 0.5!5!E 07 0.2375E 07 0.!456E07-0.5&5!E 0&

0.289E03 0.1162E 03 0.5620E 01!

0.206 0.908E05 0.59E0 025E0 Kr-,M 0.2744E 04 0.1717E 04 0.0267E 05 0.3800E-05 0.1744E-05 0.010 0.4283E-06 K--.-0.71 59E 01 0.4596E 04.22E 04M 0.!050E 4 0,18'!,6E-5,27-05 0,11!95E 05 Kr-S8 0.2116E 03 0.!53E03 0.8172F 04 0.303 0

0.!612E-01 0.9801E-05 0-,8968E--05 Xe

-0.1222E 02 0.-dE0 030E0 0.1298E-03 0.5784E-04 0.3588E-01 0.1383E-04 Xc--t33M 0.21!37E 01 0.!22 E 04 0.6179E 05 0.2385E 05 0.1072E 05 O,6632E-06 0.2578E 06 X-e-l-88 0.2!!3E 03 0.!283E 03 0.6775E 01 0.2729E-04 0.1211E-01 0.7661E 05 0.3010E 05 Xe-l38 0.951G--05 0.6-142-05 0.3362E-05 0.61454E-06 O03955BE--069Bp

-TO-T-A.L-02 E2 0.1169E 02 0.51gE--03 0.2319E-03 p.104!E 03 0.4!

4 0.25!0E 01 Revision 11 November 1996

DCPP UNITS I & 2 FSAR UPDATE TABLE 15.5-23

SUMMARY

OF OFFSITE, CONTROL ROOM & TECHNICAL SUPPORT CENTER DOSES LOSS OF COOLANT ACCIDENT 3

SUMMARY

OF EXPOSURE FROM CONTAINMENT LEAK.AGE* 4 Dose (TEDE, rem)

Regulatory Limit (TEDE, remn)

Maximum 2-hour Exclusion Area Boundary Dose 1.

30-day Integrated Low Population Zone Dose 30-day Integrated Control Room Occupancy Dose 2 30-day Integrated TSC Occupancy Dose 2 5.6 25 25 1

3.7 (0.7) 4.1 (1.3) 5 5

Thyroid Dose.,.r.m 10 CFR Port 100 Design basis case ExpeGted-ease 42-O10~

30-_

139f20X-1-0 4-Whole Body Doses, rem EAB 2 Hours 10 CFR Part 100 Design basis case

~xpeeted-ea 25

(-4 2-5 644-x-1-0 4 Population Doses, man rem Design basis case 9324 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE Note:

1. The maximum 2 hr EAB dose is based on the assumed RHR pump seal failure resulting in a 50 gpm leak of sump water occurring at t=24 hr for 30 rains. This release pathway is considered a part of DCPP licensing basis with respect to passive system failure. If this assumed release pathway were not included, the maximum 2 hr dlose at the EAB would occur between t=0.5 hrs to t=2.5 hrs (i.e., during the post-LOCA ex-vessel release phase and would be 3.4 rem.

2.

The dose presented represents the operator dose due to occupancy. Value shown in parenthesis represents that portion of the total dose reported that is the contribution of direct shine from contained sources/external cloud.

I,--The dose received by the operator during transit outside the control room is not a measure of the "habitability" of the control room which is defined by the radiation protection provided to the operator by the control room shielding and ventilation system design. Thus, the estimated dose to the operator during routine post-LOCA access to the control room is addressed separately from the control room occupancy dose and is not included with the control room occupancy dose for the demonstration of control room habitability.

As demonstrated in Section 15.5.17.2.4, the dose contribution to the operator during routine access to control room for the duration of the LOCA is minimal. (a)

Th....

e vaue corr.pon to th.rii...ayis

3. ()

Te EB Whle odydos of.61remis 369 m.amm and 1.92 rem, beta Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TARI F 1 532-4

,Shaet--l-f 5 ASSUMPTIONS USED TO CALCULATE OFFSITE EXPOSURES FRO PS QM4~*LOCA t'IDC'I II ATIrNI C1C1D I r'AVZAC-2I NI TU-lr Al III IADV DI~ Ill r-l~lNIC_

A. ECCS, C.,ontain,.cnt Foan Cooler, Co*ntanmont Sprayl Sytefm Opration ECOS trains functioning

2.

Containment fan coolcrs functioning

3.

Containment spray systecm trains-functioning B

Activity Depo..s-ted in Cota*{inmentf Recircul~ation S'-mp Water Iodine (Cre,,*v, in';entor; base on both U 235

&Q PU 239" fissio~ns)

-xpae~te*i Ta ble 11!.1 7; (I "frart. of 0.015;!"

131,1q32,133, 11.5g,O!82i0 Expected I;BA

.k-gA a

100% of gap-11.1 7; (11!27, 1290, 13,15g, re. fract.

a 1.25'; (! !27,2, re.*

fractof 0.30; 11!31, 132,1!33, 131, 135 re I. fra t. of 0.1!0) 99.75% of gap iodine 903g, OCi 97A4g, -O5!0Gi a

a 10 0,./ of40 gap ra fract. of ! 131, 132, f4at*o 0.10)*

ra (1)* 1127 (2) 11!2g (3 1131132133,31!35 g99.75%0/ of gap 4,03g,O0Ci 97,8.45x!0=

Revision 12 September 1998

DCPP UNITS 1 & 2 FSAR UPDATE

.T.ARI F 15.5

-O

,Sheet ! of 5 ASSUMPTIONS USED TO CALCULATE OFFS!TE EXPOSURES FROM POST LOCA CIRCULALTION LOOP LEAKAGE IN THE AUXILIARY BUILDING (2) 11!29

c.

Total iodine

2.

Nob~e-Gases Other fission product*s C.

Containment Recircu..lation Sump Decay-

1.

Rd*ioloical decay credit

2. Clenu rei

2.

AccuJmulator water, gal.

~xpeGte4 0% of gap iodine 0,0 0~0 0,0 0~0 Ye&

None 93,960 25,010

~xpeGted 0% of gap iodine inventor; 0,0 0,0 0,0 4,a~4ga~4o6gi 0,0 0,0 l!g, 0Ci gBA 0,-25% of gap iodine-

02g, 42.12x0G

&.5g,

&47x!O0G*i os',ieo Nene 93,960e Yes N9n~

25,010 Yene Nbge Revision 12 September 1998

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15.5 2'!.ec ASSUMPTIONS USED TO CALCULA.TE OFFSITE EXPOSURES FROM*

POST LOCA

('IDC'I I1 ATIt'NIM I (Vt*E I EAV*ACŽ-

NIM TUC Al lVll IADV [D li ~f~lN"C-Expected E-xpeced DBA D.

Volume of Water in Which Activity is-

-Depstd(dltd otd

3.

Refueling, wate.r storage tank, gal.

'1. Total, gal.

1. pH of leakage-wateF-350,000 00 262,030 169,O000 2-,h2-20 84-242

2.

Temperature of leakg atr F*-Lee-o eake-Rate G.

Duaration of Loop Leakage

1. Time after LOCA leakage begis hr-

2.

Time after LOCA leakage

3.

Total* du, rat*io'n of loop 420 1910cc/hr.

~33~

2-38 (Ta be Ic.3 9)}

4-20 1-9!0 cc/hr 0g38-7 2-4 7-2-0

-20 2A~5 719.7 O*5 74~g Revision 12 September 1998

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15.5 21 Sheet 1 of 5 ASSUMPTIONS-USEqD TO CALCULA.TE OFFSITE EXPOSURES FROM POST LOCA CIRCULATION LOOP LEAKAGE DIN THE AUXILIARY BUILDING H.Auiiar; Building Iodine

-Decontamination-Factors

1.

E-le ntar,'÷,l iodrine de'cont..'am*rinat'lio.n

a.

M ao, !bmn

.8-x-1!0 2*

3.22-x--!0O

b.

V v po, t lbm

!.60 O

x 0

-O6

-x -4O "

V liquid, fl/Ibm

c.

Partition coefficient,-7.2x!"

.7x-*

d.(g/1)-gas d.Partition factor, 6!

0s*

e.

Decontamination factor-,

-4 I.62-x1*4O 14 1-%2-x-1O*

(g) gas

2.

Organic iodine decontami 14=

14-14 14 natio feactr F

-P-tatecut, and Filter

-4.-Radiooia ecycei None None None None

2.

Plateout-Gai None None None None Revision 12 September 1998

DCPP UNITS 1 & 2FSAR UPDATE TABLE 1 5.5 24!

~h~+ 'Lr~f~ F~

ASSUMPTIONS USED TO CALCULATE OFFSITE EXPOSURES FROM POST LOCA r'IDtCI II ATlICNI I t'tDI EAI/A("*

Ilkl -rUE AI VIIl IAIDV DI III rFlINlf-Expected

~peGted D-BA Q*,LL'*

I *'I,]

DBA

.Auviliary Buidinglm Decay Removal (Contd)

3.

Auxillaryl bira lding

a.

Iodine filter effiGiency

(*I 1) 1 Elemental iodine i

(2) Organic, iodine,,

None None Ye&

0,0 0,0 0,0 99,0 85,%

99,0 0~0 0,0 0,0 9Q,0 7,0,0 90,0

1. Down wi-nd-radiological decay credi Nene None None None

2.

Atmospheric dilu-tion f.BrathngRter Table4! 5.5, Trable-!15.-4 Frable-l-,%-7 T-able-l-,&54W Tablel5.51 Ta~e45~54 Revision 12 September 1998

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1 5.5 26 EXPRESSED* AS PERCENTAGE OF TOTAL HOURLY OBSV*ERVATIONSQ WAITHIN EACH SEASON AT THE SITE (250 FOOT LEVEL)

W~ind Directin We*

Tr~a;+;e,,-I Offsheie~{b~

Galm-~~4 54%

62%

38%

40%

42%

34%

5%

4%

(a) Drj Season May through Septembei Wct Season November through March Transitional April and Octobci measu-red clccg:ise.

(d Calm wind directions aqre defined as.. wind wit h speeds Icss than one* 1 mph.

Revision 11 November 1996

DCPP UNITS 1 & 2FSAR UPDATE TABLE 1.5<

2 7 Sheetlof2 DIABiLO CmtANYONM POWAER DPLNT SITE PROBABL^*lITY OF PERSSL~TENCEiOFFSHOR W*IQ~mIND Dhll IIrECTION SECI::TORS*C (250 FOOT LEVEL)

Cense-NN*

ou04 Hours

_ANe D*

WV~a T 2

024 0407 0782-7 0-.7-8 3

0420 0,04 0030 0248 4

0,07-3 0,04 0,049 0448 6

0,6 0*045

0707 07030 4-0 4-2--

473 NE A

D AN 07044-0,047-0M44 07044-04)44 0708-070-040-073-0*47--

-07000 0;400 0744)4 0430 A

D AN E-A D

AN A

0 AN 0-400 0440480 49 0-423 0476 04#73 0,64 07090-0464 -

.0490 0467-80406 077 04B40 0*400044 04370 0444 0440738 04890

-440 0442 0490 040404 0040B 0467-0400 04330475 044 0-.........4 07066 04-00 07086 042 07046 0-.--.8 04000 0400 04408 0-46)0 073 0406 000 0440o0-300490 0444-A028 -

0,00 04004 04)00-04000 -

0407-0,044, 44 4,5 46 47-48 49

-20 Revision 11 November 1996

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15. 27 o

Sheet 2 of 2 D-IABlOt CiANYON*k DPOWAER DPLAT SITE" PROBIABILITY OFl PERIS:(ITENCEI¢I:

OFFSHORE/*DI WAINDi-DIRECTIONl SEC:TORS (250N FOOtT" LEVEL)'- "

Gue-v NeuFG NW A

D W

NN4W A

D W/

t A

0 W/

I A

D WA I

4 0,405 0,986 2

0,994 0,942 3

0,942 9,054 4

9,95~

9,058 6

~058 0,240 6

0,953 0,948 9,950 0,045 S

0,914 0,939 9

0,945 0,944 40 0,038 0,0.44 14 0,946 0,959 42 9,935 0,926 43 0,033 9,954 14 0,938 0,043 45 0,Q49 9,023 46 0,929 9,025 44 0,022 0,034 46 0,023 0,933 40 0,030 0,034 20 0,043 0,024 24

~003 0,005 22 0~093 0,906 23 0,004 0,006 24 0,042 0,042 25 0,042 0,049 26 0,912 0,020 22

~004 o,004 28 9,094 0,003 29 0,000 0,990 30 9,090 9,990 34 0,005 0,008 (zO A Anniia~

0-A42 0-,~4 90386 0,993 90*45 0,045 O0O93 Q,093 0 ---...---..

o0o9o o0,95 90498 9,059 90*44-o,045 9*26 9,044 0,945 9,o04 oo48 0o900 0-494 0-4-94 0,935 o,929 0*046

-,3 9,04 0,007-0,000 O,997 00999

~0900 0O0 04716 0O--3 0,944 949 09424 0,900 0,026 9,046 O9,99 0,000 9,99 9,93 0*494 O-.9-O4 O=O443 9,099 80949 O=,934

0,99 0,99 0,94 0A46 0,044 0,923 94223 9442 0A44 O9O7-9,043 9,00 O=,654 9452 0,4&3 0,948 0,434 9,944 O9,2-9 0,037 0,344 9466 O,026 9,999 9,239 984*0 9,040 0,934 9,944 Dry c~a~on (May thrc~gh-6eptembe~

Wct ~co~on (Nzvembe~~4ewgWMaro4i)

Tram~tAp~J-a~-QGtebe~

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TA LE,15.5 2-,8 Sheet 1lof 2 l~~'I if~Nr~lr-fN/\\K I-rr-lr-,i I r-r~ fNP~K IT A IN IT~ flrk 1T

. IITINIf~'

.~UIVIt I U1'J~ U~I~L' IL~ L.,".LUUL'X I ~ ~JJ flUtW U~JJ'4 I r~jLL~L' L.UI'~I irjPII~JtrJ I *~'~I~J I

~BA-Gose

a. Elcmc-tal

b. Organie

c.

Particulate

2.

Noble gases Otfhcr fision products~f

1. Radiolo"ical decay credit

b. Organic

c.

Pati~culate 25% of gap iodine inventor,'

21.95% of gap iodine invcntor,'

0.05% of gap iodine inventory 0% of gap iodine inventor,'

100% of gap inventor; None 25% 7o,f core*

iodine,*

inventor; 22.75% of core iodine inventor' "1.rlr0% oft crer,-- iodinen'tn Y-es Yes 0 -

0

b. Noble-gases A

r'-,,*n~~

I-*-.rN'NI None NoeF None None Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE

,.TABLE

!15.5-28 Sheet 2 of 2 ASSUMPTIONS USED TO C^LCrU! ATE-ONSHOEL CONTROLLED CON~TAINMENmT VENTINGr' Expcted ase BA-Gase C.CnanetAmshr

o m

2 6---10ebGfe 2.68-x1Oebe-fee

0. Purge Schedule 2.

T im f e O C u g n b e i s1 6

o r, C h 'c 6 6 7 h o r, C h p " 6 E. Purgc Flo'w-ate 10 efm, Chapter 6 25 cfm, Chapt--r-6 F. Filter EficiJenc-y

1. lodines

a. Elemental 8%9-

b. Organi..c-885%

7

c. -Pariult 9-%

0-%

1..Radoloi.a deca.. credit NeRo Noee

,Q Thbie4&530 Table46!5.530 Revision 11 November 1996

DCPP UNITS 1 & 2 ESAR UPDATE TABLE 15.5 29 ONSHORE CONTPOI I Ffl' m.CNTAINMFNT VENT!NG EXPO£!Rt RE DBA Whole body, exposure 0784 7-5 -4 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1 5.5-30 ATMOSHP-IERICl D*ISDPERIONI FACTORSD FO*R ONSHOq~RE*r CONkTROLL IED-CONIkTAI lIIENkT \\IENT! NO* (STAB!I LITV CATEG*-'ORY D)*

Distance7-kRm

/7seL

-172

%A4x4Q----

270 47-gg4-x-1-0*

Metc...."logi"al Input Parameters:

Height of releas 70 meter" Mixin-g,- dept-h -- 350r me,,ters Sima,,,,

phi+ - 30 degrees Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-23A LOSS OF COOLANT ACCIDENT Assumptions & Key Parameter Values Parameter Value Core Power Level 3580 MWt (105% of the rated power of 3411 MWth)

Fuel Activity Release Fractions Per Reg. Guide 1.183 (See Section 15.5.17.2.2.2)

Fuel Release Timing (gap)

Onset: 30 sec Duration: 0.5 hr Fuel Release Timing (Early-In-Vessel)

Onset: 0.5 hr Duration: 1.3 hr Core Activity Table 15.5-77 Chemical Form of Iodine released from fuel to 4.85% elemental containment atmosphere 95% particulate 0.15% organic Chemical Form of Iodine Released from RCS 97% elemental and sump water 3% organic Containment Vacuum/Pressure Relief Parameters Minimum Containment Free Volume:

2.550E+06 ft3 Primary Coolant Tech Spec Activity Table 15.5-78 Chemical Form of Iodine Released 97% elemental; 3% organic_

Maximum RCS flash fraction after LOCA Noble Gases 100%

Halogens 40%

Maximum containment pressure relief line air 218 actual cubic feet per second flow rate (acfs)

Maximum duration of release via containment 13 sec pressure relief line Release Point Plant Vent Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE Containment Leakaqe Parameters Containment Spray Coverage - Injection Spray 82.5% (sprayed fraction) and Recirculation Spray Modes:

Sprayed Volume 2.103E+06 ft3 Unsprayed Volume 4.470E+05 ft3 Minimum mixing flow rate from unsprayed to sprayed region:

Before actuation of CFCUs 2 unsprayed regions/hr After actuation of CFCUs 9.13 unsprayed regions/hr Minimum duration of mixing via CFCUs Start = 86 sec End = 30 days Containment spray in injection mode Initiation time 111 sec Termination time 3798 sec Maximum delay between end of injection 12 min (based on manual operator spray and initiation of recirculation spray action)

Containment spray in recirculation mode Initiation time 4518 sec Termination time 22,518 sec Long-term Sump Water pH

> 7.5 Maximum allowable DF for fission product Elemental Iodine: 200 removal Others: not applicable Elemental iodine and particulate spray removal See Table 6.2-32 coefficients in sprayed region during both injection spray and recirculation spray modes Elemental iodine removal coefficients due to See Table 6.2-32 wall deposition Particulate removal coefficients in unsprayed See Table 6.2-32 region due to gravitational settling Containment Leak rate (0-24 hr) 0.1% weight fraction per day Containment Leak rate (1-30 day) 0.05% weight fraction per day Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE Containment Leakage Release Point From the worst case release point of (Unfiltered) the following:

Diffuse source via the containment wall Via Plant Vent Via Containment Pen Area GE Via Containment Pen Areas GW

& FW ESF System Environmental Leakage Parameters Minimum post-LOCA containment water 480,015 gal.

volume sources Minimum time after LOCA when recirculation is 829 sec initiated Duration of leakage 30 days Maximum ECCS fluid temperature after 259.9 0F initiation of recirculation Maximum ECCS leak rate (including safety Unfiltered via plant vent = 240 factor of 2) cc/min Unfiltered via Containment Penetration Areas GE or GW & FW

- 12 cc/mmn RHR pump seal failure Filtered01* via plant vent 50 gpm starting at t =24hrs for 30mrin Iodine Airborne Release Fraction 10%

Auxiliary Building ESF Ventilation System filter Elemental iodine: 88%

efficiency Organic iodine: 88%

Refueling Water Storage Tank (RWST) Back-Leakage Parameters Earliest initiation time of RWST back-leakage 829 sec Maximum ECCS / sump water back-leakage 2 gpm rate to RWST (includes safety factor of 2)

RWST back-leakage iodine release fractions See Table 15.5-23C RWST back-leakage noble gas, as iodine See Table 15.5-23C daughters, release rate from the RWST vent Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE Miscellaneous Equipment Drain Tank (MEDT) Leakagqe Parameters MEDT inflow rate (includes safety factor of 2) 1900 cc/min MEDT leakage Iodine release fractions See Table 15.5-23D MEDT leakage noble gas, as iodine daughters See Table 15.5-230 release rate from plant vent_________________

CR Emergency Ventilation: Initiation Sigqnal/Timingq Initiation time (signal)

SI signal generated: 6 sec Non-Affected Unit NOP Intake Isolated: 18 sec Affected Unit NOP Intake Isolated and CRVS Mode 4 in full Operation:

44.2 sec Bounding Control Room Atmospheric Table 15.5-23B Dispersion Factors for LOCA Note:

Releases from the RHR Pump Seal failure are filtered for CR dose evaluation and Site Boundary Dose Evaluation.

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE 1 5.5-23B LOSS OF COOLANT ACCIDENT Control Room Limiting Atmospheric Dispersion Factors (sec/in 3)

R°elese'Location /Receptor 0-2hr I 2-8 hr 8-24 hr I24-96hr hr Control Room Normal Intakes Plant Vent Release_____

- Affected Unit Intake 1.67E-03

- Non-Affected Unit Intake 9.10E-04 Containment Penetration Areas___________

- Affected Unit Intake 6.84E-03

- Non-Affected Unit Intake 2.24E-03 Control Room Infiltration Plant Vent 1.26E-03 8.96E-04 3.44E-04 3.44E-04 2.99E-04 Containment Penetration Areas 3.22E-03 1.85E-03 7.29E-04 7.15E-04 6.64E-04 RWST Vent 1.07E-03 5.80E-04 2.18E-04 2.19E-04 1.79E-04 Control Room Pressurization Intake Plant Vent 5.65E-05 3.70E-05 1.35E-05 1.37E-05 1.11E-05 Containment Penetration Areas 6.45E-05 4.05E-05I 1.65E-05 1.38E-05 1.1 2E-05 RWST Vent 5.25E-05 3.03E-05 1.15E-05 1.10E-05 8.83E-06 Note 1: Release from the Containment penetration areas (i.e., areas GE or GW & FW):

applicable to containment leakage and ESF system leakage that occurs in the Containment Penetration Area Note 2: Release from Plant Vent: applicable to ESF system leakage that occurs in the Auxiliary building, MEOT releases, RHR Pump Seal Failure Release and Containment Vacuum/Pressure Relief Line Release Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-23C LOSS OF COOLANT ACCIDENT RWST Iodine Releases Fraction and Gas Venting Rate to Atmosphere Average Interval Fro Tie o Tme Iodine Release Fraction Weighted Gas Space to Atmosphere Venting Rate to Atmosphere Sec Sec Fraction 'released/ 'entering Fraction Vrs / day 829 7200 9.451E-05 2.610E+00

7200 28,800 6.357E-05 7.291E-01 28,800 86,400 8.796 E-06 7.375 E-02 86,400 345,600 4.560E-07 9.955E-03 345,600 471,600 6.347E-07 1.311 E-02 471,600 1,011,600 8.231E-07 1.489E-02 1,011,600 2,048,400 1.114E-06 1.547E-02 2,048,400 2592000 1.483E-06 1.702E-02 Where:

Ireleased = Total Iodine mass released to atmosphere during specified time interval, gm lentering

= Total Iodine mass entering to the RWST during specified time interval, gm Frac. Vr~s = Rate of Fractional RWST gas volume vented during specified time interval Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-23D LOSS OF COOLANT ACCIDENT MEDT Iodine Release Fraction and Gaseous Venting Rate to Atmosphere Iodine Release Average Interval Weighted From Time To Time Fraction to Gas Space Venting Rate Atmosphere to Atmosphere Sec Sec Fraction 'releasedl /

Fraction VMEDT / day

'entering 829 7,200 4.521 E-07 5.024E+00 7,200 28,800 1.386E-08 3.024E-02 28,800 86,400 2.362E-07 3.324E-01 86,400 183,289 3.950E-07 6.497E+00 183,289 345,600 1.236E-02 (Note 2)

(Note 1) 345,600 752,400 2.028E-02 (Note 2)

(Note 1) 752,400 1,530,000 2.390E-02 (Note 2)

(Note 1) 1,530,000 2,592,000 2.166E-02 (Note 2)

(Note 1)

Where:

Ireleased = Total Iodine mass released to atmosphere-during specified time interval, gm lentering = Total Iodine mass entering to the MEDT during specified time interval, gm Frac VMEDT = Rate of Fractional MEDT gas volume vented during specified time interval Note 1: After the MEDT overflows at t =183,289 sec, the gas venting rates are 2640 cfm from the EDRT room, and 1760 cfm from the U1/U2 Pipe Tunnels (i.e.,. the exhaust ventilation rate from the respective rooms + 10%). To be consistent with the methodology used to determine the iodine release fractions after spillover, the noble gases generated by decay of iodines in the tank and spilled liquid after overflow occurs, should also be released instantaneously to the environment without hold-up.

Note 2: The room ventilation flows addressed in Note 1 (utilized as clean in-coming air) are incorporated into the determination of the iodine equilibrium concentration in the EDRT room and U1/U2 Pipe Tunnels air space, respectively. The bounding iodine release fractions presented above after spillover assume instantaneous release of iodines to the environment without hold-up in the room.

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-23E LOSS OF COOLANT ACCIDENT TSC Limiting Atmospheric Dispersion Factors (sec/in 3)96-720 Release Location / Receptor 0-2 hr 2-8 hr 8-24 hr 24-96 hr h

TSC Normal Intakes TSC Infiltration Plant Vent 5.43E-04 2.16E-04 9.97E-05 8.11E-05 6.58E-05 Containment Penetration 1.83E-03I 7.49E-04 3.16E-04 2.92E-04 2.41 E-04 Areas______

RWST Vent 3.72E-04 1.68 E-04 6.64E-05 6.17E-05 5.l0E-05 CR/TSC Pressurization Intake Plant Vent 3.70E-05 1.35E-05 1.37E-05 1.11E-05 Containment Penetration Areas 4.05E-05 1.65E-05 1.38E-05 1.12E-05 RWST Vent 3.03E-05 1.15E-05 1.10E-05 8.83E-06 Note 1 : Release from the Containment penetration areas (i.e., areas GE or GW & FWV):

applicable to containment leakage and ESF system leakage that occurs in the Containment Penetration Area Note 2: Release from Plant Vent: applicable to ESF system leakage that occurs in the Auxiliary building, MEDT releases, RHR Pump Seal Failure Release and Containment Vacuum/Pressure Relief Line Release Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE T ABLE 15.5 31:

CONTROL ROOM INFILTR~gTION ASSUMED FOR RADIOLOGICAL EXPOSURE CALCULAgTIONS Sheetl1of 2 B*-Deer-s I *"'Jlf*'jtl*

f'll I,"j'lIIq'*I"*l I ~

L~C1C~ I~tNI fllIt'%fl No Icakape. no windows.

070 and.controlroom.will.b........c.

pre.....

uriedsu.

e.

070

2. Pping(extrnalseal

3. ConduiJts and trays 070 detwihto coats of FLAMEMASTIC 72A, and control roo w^ill be positively*h pressurized-Nolaag:cndisae eld ihTiX RPCslcn 070 Revision 11 November 1996.

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-31 CONMTROL ROOM !IFILTRATIO*N ASSUED FORn RADIO~LOGICALr^

EXPOSU RE CALCUL AS TIONS Sheet 2of 2

Leka, D,,+h I p-,L--,.p Ir:,i, *÷;

- leakage,* untc.......

f.m*

..,,(

Ap-daperearea square.....

f tn

- lekageperun.tdampr.aea. pr.i....,,

of water~

Ap-presur difrec ar+sdmp i*n.

ofW.t

....... qO 2 ~O-000 frm/ft2 n. and Ap

..0i..G..

A--1*8-t, q - 0.001 cfm/ff2-in. and Ap -6.0 in. W.G*.

A-=6

,O-fq--Q0.001-cfm/ft*-in.

and Ap - 6.0 in. W.G%.

A-=- 1.78 t, q-=- 0.001-cfn/ft*-in. and Ap - 6.0 in. WA.G.

1. Mode damper..

3. Mode damper (a)

From manufacture' (b),

Ascum "e co n scrvat (c-,)

10 cfm i.,s,-

co rnser,,

40705 40705 40705

[r's-published-data7 ively lag a.ue cf 6..T. es" of water; dampers w-ill never-see a pre5,.ure-differential this large*.

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 32 ASSUMPTIONS USED TO CALCULA.TE Pfl£T A~mCfl.nENT CeNTRe! ROO.M RADIO! COGCAL EXPOSURES

.IIt121 I UI D-NA-Case A

Powcr I

L evelJ ased to Containment Atmosphere

1. Iodine, % of core iodine ncnto...

+'

b. Organic, % of core iodine inventor;

3. Othcr fis'ion product

a.

Elemental

c.

Par'ti{culate 1I. Time post LOC*A..pray starts

a. Iodines

b.

Nole[l gae 1eo0 Ne~e Nene Revision 12 September 1998

DCPP UNITS 1 & 2 FSAR UPDATE TAR! E 15.5 32 Sgheet-! of-3 ASSUMPIIaETIONSM USIEDi" TO' CAl CULIIATE pOS*T ACC *Ii-DENI*T CONI*TROL)*

ROOM'h/ RDi'1"IOLOG*ICAL EXPOSURI IES D~A-Ga6e 6.Co.-nta ir nment Iea'kLrate,

a. First 21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months

b. Remaindcr of accident period 04%-per-day O70~%-p&-4ay D. Recirculation Loop Lcakagc

1. RHRlcakagcratc

2. Start of RHR leakage

3. Duration of RHR leakage

1. Charcoal filter efficiency for release of RHR leakage

a. Iodine filter efficiency (1) Elemental, %

(2) Organic, %

(3) Particulate, %

2A-hf S 740 p070 070

b. Noble gas filter efficiency E. Meteorology (atmospheric dilution factors from the containment to the eontrol room)

F. Control Room Ventilation Flowrates

1. Flowrate of contaminated air infiltrating into the control room

2. Flowrate of pressurization air into the control room

3. Flowrate of recirculated control room air through cleanup filters Tab4e45~-6 1-0-efm 24!00-ecfm 2!00-cfm Revision 12 September 1998

DCPP UNITS 1 &2 FSAR UPDATE TABLE 15. 32*"

ASSUMP*ATIONSM USIED tO* C'ALCULIIATE pOST ACCIDENIT CONMTROI ROOM RDAIOLOG*ICf**IAL EXPOSURES=

hect

! c 3

~BA-Gase G. Decay and Cleanup in Control Room

1.

Radio*lo-gca-l dcayr,* inc~ludcd

a. Io;inc (1) FElmcntal (3) Pa~icu~ate H. Control Roocm Compl!ex VIolumc (total for I.

Control Room Occupancy Factors

1. 0 2 ho'-rs

3. 96 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months Yes Ye~s 80%

-170,0O0,!?

1-I (a)

Although a su..bsequent safety evaluation sho-,ed that the Design Case coefficient of 31 hr4 -(fer-2600-inhrgn(ficant...cf.rcncc 39)

Revision 12 September 1998

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-33 ESTIMATED POST-AGGI=P44NT-LOCA EXPOSURE TO CONTROL ROOM PERSONNEL DURING INGRESS / EGRESS (HISTORICAL)

D8ALOCA Gamma Beta Thyroid

Exposure, Exposure,

Exposure, Radiation Source rem rem rem 1...R.di.tion..rom....bo..o.f...ion products See-See-See-Used 6

2. Not Usedirc radi.tin.to.th.contro 0-032z 0

0 fission proutsAr{ in the ontaninment

3. Not UsedDirect radiation to the control 002-2

0) 0

4. Radiation from airborne fission products 0.0066 0.0243 4.72 in the containment leakage plume to-control room personnel during room.p.r.onne during,'*' egress ingress

5. Direct radiation from fission products in 0.022 00 the containment structure to control room personnel during egress-ingress (53 5-minute trips)

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-34

SUMMARY

OF OFFSITE AND CONTROL ROOM DOSES MAIN STEAM LINE BREAK Dose (TEDE, rem)

Regqulatory Limit (TEDE, rem)

Maximum 2-hour Exclusion Area Boundary Dose Pre-incident iodine Spike Accident-Initiated Iodine Spike 30-day Integrated Low Population Zone Dose Pre-incident iodine Spike Accident-Initiated Iodine Spike 30-day Integrated Control Room Occupancy Dose Pre-incident iodine Spike

-Accident-Initiated Iodine Spike 0.1 0.7 25 2.5

<0.1 0.2 25 2.5 5

2.0 4.1 Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE Note:

1. The maximum 2-hour EAB dose occurs during the following time period :

- Pre-incident iodine Spike

- Accident-Initiated Iodine Spike 0 -2 hours 7.6 - 9.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-34A MAIN STEAM LINE BREAK Analysis Assumptions & Key Parameter Values Parameter Value Power Level 3580 MWt Reactor Coolant Mass 446,486 Ibm Leak rate to Faulted Steam Generator 0.75 gpm (conservative assumption) ;

leakage density 62.4 Ibm/ft3 Leak rate to Intact Steam Generators 0 gpm (all leakage assumed into faulted SG)

Failed/Melted Fuel Percentage 0%

RCS Tech Spec Iodine Conc.

Table 15.5-78 (1 pJCi/gm DE 1-131)

RCS Tech Spec Noble Gas Conc.

Table 15.5-78 (270 pCi/gm DE Xe-i133)

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 rate Rate Duration of Accident-Initiated lodine Spike 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Initial Secondary Coolant Iodine Table 15.5-78 Concentrations (0.1 pCi/gm DE 1-131)

Secondary System Release Parameters Iodine Species released to Environment 97% elemental; 3% organic Fraction 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)

SG Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-34A MAIN STEAM LINE BREAK Analysis Assumptions & Key Parameter Vaiues Parameter Value Liquid 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 seconds SG Time period when tubes not totally submerged Insignificant (intact SC)

Steam Releases from intact S~s 0-2 hrs: 384,000 Ibm 2-8 hrs: 893,000 Ibm 8-10.73 hrs: Same release rate as that for 2-8 hrs Iodine Partition Coefficient in Intact SC 100 (SGs fully covered)

Termination of release (0.75 gpm leak):

30 hrs when RCS reaches 212 0F Faulted SG Termination of release from Intact SC 10.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months Release Point: Faulted SC Outside containment, at the steam line break location Release Point: Intact SC MSSVs/10% ADVs CR Emerqency Ventilation : Initiation Si~qnallTiming Initiation (signal)

SIS Unaffected Unit CRVS inlet damper fully closed Within 12.6 seconds Affected Unit CRVS inlet dampers fully closed Within 38.8 seconds Control Room Atmospheric Dispersion Factors Table 15.5-34B Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-34B MAIN STEAM LINE BREAK Control Room Limiting Atmospheric Dispersion Factors (sec/mn 3)

Receptor-Release Point 0-2hr 2-8 hr 8-10.73 hr 10.73-301 hr CR NOP Intake - Faulted SG (Break Note 1 Location)

CR NOP Intake - Intact SG (MSSVs/10%

8.60E-04 ADVs) - Note 2 CR Inleakage - Faulted SG (Break 1.24E-02 7.35E-03 3.01E-03 3.01E-C 3 Location)______

CR Inleakage - Intact SG (MSSVs/10%

2.78E-03 1.63E-03 1.63E-03 ADVs)______

CR Emergency Intake & Bypass -

7.65E-05 4.78E-05 1.86E-05 1.86E-5 Faulted SG (Break Location)

CR Emergency Intake & Bypass - Intact 1.5E0 96E-6

.0E6 SG (MSSVs/10% ADVs)

Notes:

1. ARCON96 based x/Q s are not applicable for these cases given that the horizontal distance from the source to the receptor is 1.5 meters (which is much less than the 10 meters required by ARCON96 methodology)..

2. Due to the proximity of the release from the MSSVs/10% ADVs, to the normal operation CR intake of the affected unit, and due to the high vertical velocity of the steam discharge from the MSSVs/10% AIDVs, the resultant plume from the MSSVs/10% ADVs will not contaminate the normal operation CR intake of the affected unit. Thus the %/Q s presented reflect those applicable to the CR intake of the unaffected unit.

Revision 19 May 201.0

DCPP UNITS 1 & 2FSAR UPDATE T -ABLE 15.5 "10 (HA/

ISITOR*IC'AL)

LONG TERM,ACTI I/TY RELEA SE FRACTIONS

~Rle aso Fractions44-339.1x!-

44134 1.02-x4!0-K-r-83M 2.!6- !0-*

K-r-87 1.-51 4 -*,

X-e--33 1.68x*-1,*

Xe-433M 5.52x !0-4 Xe!35M,

3. 23-x4", n-X e --138 2.89-x !0 -

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-4!

Sheet 1 of 2 4431--

8.643E-!

14.783.=0

,L432 1.121-E4 2.505E-!

-1433 7.753E4 3.4725E0 44134 6.086E-2

4.0 67-E2

1--43-5 3.67-3E-I 140, 7-E-O 44!32ORG 070 070 44133ORG 07 7

44!350RG 070 070 44314-PAR 07 7

41-32-RAR 07 070 4-433P-AR 07007 44!34PAR 07 7

-tI-?,P-AR 07 7

K-r-83M 9.975E4 !

428! E-Kr-85 1.2282Et

!.6610E!

K-r-88M

.9366E04.69!E0 Kr8-32949E0 8.647-E-K--8

.004E0 A47E Xe4--3 2.7392E2 X~e4-33M 3.8638E0 5.1880 X-e4-3 2.0293E!-

2.2393E!

X43M3.026E4!

0 X-e-1-38 0.!-20E 0

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE

-I"/%1")1 I--

,d*

A4 A cTTX/JTY R.ELF\\*.SE

FOVVIOWP'W.nTI A T OCKFD R OTOR.,ACflD.NT 0-2-hF 44-32 14-133 14340RG

! -32ORG 4413!PAR 1433PAR KF-83M K-r-88 Xe-4.3, Xe--3.3M X~e138 1.~223E-3 8.'!5E-3 3.984E 3 070 070 0705E 20870 07027 5.2170E-2 1.40!E-!

2.8404E4 2.825E !

5.116E-3

!.564 E2 2-84h*

2.386E-3 3.87-5E-2 4*004-E-4 070 070 070 0.70n 09 70]

070 *L-2.3A4E-!

O42-O72-Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-42

SUMMARY

OF OFFSlTE DOS-ES-AND CONTROL ROOM DOSES F-R,-M-A-LOCKED ROTOR ACCIDENT Thyroid Exposures, rem Qua

~r%, inr 4 '~,ri, 0 hr., Ire 10 CFR P-art 100 Desig basis..

case 300 0~30 275-x-404 300 0T07-6 Whole Body Exposures, rem Q;~a E~n.,nrbrr.,

0 hr., Ire' 10 CFR Part 100 Design basis cs E*peete~-oae 2-5

!.*3-x!0 2 2-5 !.

x!n

f ~ llJ]

I 1 I*

. *1L;t-i ij T*J I I tI :

09*

t2 '

2 7... 8,-

x., 4 Dose (TEDE, rem)

Regulatory Limit (TEDE, rem)

Maximum 2-hour Exclusion Area Boundary Dose1 30-day Integrated Low Population Zone Dose 30-day Integrated Control Room Occupancy Dose 0.5 0.1 2.5 25 1.7 5

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE Note:

1. The maximum 2-hour EAB dose occurs between 8.73 - 10.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months .

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-42A LOCKED ROTOR ACCIDENT Analysis Assumptions & Key Parameter Values Parameter Value Power Level 3580 MWt Reactor Coolant Mass 446,486 Ibm Primary to Secondary SG tube leakage 0.75 gpm ( total for all 4 SGs); leakage density 62.4 lbm/ft3)

Melted Fuel Percentage 0%

Failed Fuel Percentage 10%

Equilibrium Core Activity Table 15.5-77 Radial Peaking Factor 1.65 Fraction of Core Inventory in FuelIGap 1-131: 8%

1-132: 23%

Kr-85: 35%

Other Noble Gases: 4%

Other Halogens: 5%

Alkali Metals: 46%

Isotopic Inventory in Fuel Gap Table 15.5-80 Iodine Chemical Form in Gap 4.85% elemental 95% particulate 0.15% organic Secondary Side Parameters Initial and Minimum SG Liquid Mass 92,301 Ibm/SG Iodine Species Released to Environment 97% elemental; 3% organic Time period when tubes not totally submerged insignificant Steam Releases 0-2 hrs: 651,000 Ibm 2-8 hrs: 1,023,000 Ibm 8-1 0.73 hrs: same release rate as that for Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-42A LOCKED ROTOR ACCIDENT Analysis Assumptions & Key Parameter Values Parameter Value 2-8 hrs Iodine Partition Coefficient in SGs 100 Particulate Carry-Over Fraction in SGs 0.0005 by weight Fraction of Noble Gas Released 1.0 (Released without holdup)

Termination of releases from SGs 10.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months Environmental Release Point MSSVs/10% ADVs CR emergency Ventilation : Initiation Signal/Timing Control Room is assumed to remain on normal ventilation (CRVS Mode 1) for duration of the accident.

Control Room Atmospheric Dispersion Factors Table 15.5-42B Note 1: Due to the proximity of the release from the MSSVs/10% ADVs, to the normal operation CR intake of the affected unit, and due to the high vertical velocity of the steam discharge from the MSS Vs/1 0% ADVs, the resultant plume from the MSSVs/10% ADVs will not contaminate the normal operation CR intake of the affected unit.

Thus the x/Q s presented reflect those applicable to the CR intake of the unaffected unit.

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-42B LOOKED ROTOR ACCIDENT Control Room Limiting Atmospheric Dispersion Factors (sec/rn 3)

Release point and receptor 0-2hr 2-8 hr 8-1 0.73 hr MSSVs/10% ADVs to CR NOP Intake (Note 1) 8.60E-04 5.58E-04 5.58E-04 MSSVs/10% ADVs to CR In-leakage (CR 2.78E-03 1.63E-03 1.83E-03 Centerline)______

_____ I Note 1: Due to the proximity of the release from the MSSVs/1 0% ADVs, to the normal operation CR intake of the affected unit, and due to the high vertical velocity of the steam discharge from the MSSVs/10% ADVs, the resultant plume from the MSSVs/10% ADVs will not contaminate the normal operation CR intake of the affected unit.

Thus the x,/

s presented reflect those applicable to the CR intake of the unaffected unit.

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-44 COMPOSITE SOURCE TERM FOR FUEL HANDLING ACCIDENT IIM TUill 1l IEI UAKfIrlT ?NTVlt2-11 II! fINIfIC2-Source Tc-rm-Gil!assembiy-at shutdown) 5.057-E+05 Activty-at4!00 3.625E+05 Is1t7p PeeJ-AetMty-

{CI-atAOO-he) 57981-3E+04 FHB Activity Based on 0F200 for Jo~es 4-2 7.283E+05 3.042E+~05 5.0!-93E+04 2-0&865 H443 1.032E+0g 3.783E04 6.2420E+93 84-~24 14-5 9.611E+=05 2.69E+=01 4.43g9E+00 2

Kr-S3m

&1-96D+-

9.54E-08 1.57g4E- 084E0 K--Sm 90! E+05 3.179E-02 0.0060704 0.0806974

___353E+0-3 6.350E+03 25 K-r-8-7 3.828E+05 0

0 0

5.4!6E+05 1.350LE 05 2.2275E 06 2.2275E 06 r-9.55+5 00 0

Xe-4Thn 5.gg E+-03 5.4§9E+03 0027385 25 Xe43&m 3.4!87-E+04 1.306E+01 24A 9.93

~9E+05

@.91dE+05 144048 414048-X-e4-3-m 2.02! E+05 A, 264 E+OO 0-703*§

-X-e43 2.886E+=05 1.327E+0 24*

~

289 9.140E+05 0

0 0

Xe4-ag-7--+05 0

0 0

Where4:

, Zm*,

r, i

X

- A4 x 1.65 x 0.3 for Kr 85

,-HB,ct-+,it+,,at 100 ho..r...

(,A. 0o)"°-

/200 for iodinc

Revision 16 June 2005

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 15 gheet-e-2-d ASSUMP54TIONS FOR*E UEl HAINDrINGflt ACCID*ENT IN THJE FUEL IhANDl ING* AREA A*.

Prc accident Operation

1. Coe Po*wcr

580-MWt B*.

Highest Power Fuel*,Asscmbly Characteristics

3. Number oftuhan emK ie da5a d4-7.GSpeAntivt Fra Po}Dctontas ain atr

!.-led~ne 2040 8073 NoNoae§se Revision 17 November 2006

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15.5 45

$heet4-ef-2 A.SSUMIPTIO-NS FORD FEl HEIANDrL ING-ACCIDEN-T IN THlE FEl HE ANDIN*

G AREA

2. Radiological cleanup credit N~ene t~

Atmospheric Dispersion

1. Rad!ological decay credit 2~-%/Qs M7 Offsite Breathing Rates N~

Off slle-Pewe~

~Assumes the FHB ventilation operates contir stages of this event with or without offsite power.

Nene EAB (00m) to 24 hr 28to29*hr 96 to 720 hr 4.5El*sec/'m 3

" +he-early'

uously to maximize the FHB exhaust tc Revision 17 November 2006

DCPP UNITS 1 &2 FSAR UPDATE TABLE 15.5-47

SUMMARY

OF OFFSITE AND CONTROL ROOM DOSESDOSES FROM FUEL HANDLING ACCIDENT IN-T-HE FUEL HANDLING AARE-ACCIDENT IN THE FUEL HANDLING BUILDING OR CONTAI NMENT Dose (TEDE.....rem)

Reg~ulatory.

Limit (TEDE. rem)

Maximum 2-hour Exclusion Area Boundary Dose' FHA in Fuel Handling Building FHA in Containment 30-day Integrated Low Population Zone Dose

-FHA in Fuel Handling Building

-FHA in Containment 30-day Integrated Control Room Occupancy Dose

-FHA in Fuel Handling Building

-FHA in Containment 6.3 1.0 1.0 6.3 0.1 0.1 5

1.0 4.3 Note:

1. The maximum 2-hour EAB dose occurs between 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15,5-47A FUEL HANDLING ACCIDENT IN THE FUEL HANDLING BUILDING OR CONTAINMENT Analysis Assumptions & Key Parameter Values Parameter Value Power Level 3580 MWt Number of Damaged Fuel Assemblies 1

Total Number of Fuel Assemblies 264 Decay Time Prior to Fuel Movement 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Radial Peaking Factor 1.65 Fraction of Core Inventory in gap 1-131 (8%)

1-132 (23%)

Kr-85 (35%)

Other Noble Gases (4%)

Other Halides (5%)

Alkali Metals (46%)

Isotopic Inventory in Fuel Gap (Decayed 72 Table 15.5-47C hours),

Iodine form of gap release before scrubbing 99.85% elemental 0.15% Organic Iodine form of gap release after scrubbing 57% elemental 43% Organic Scrubbing Decontamination Factors Iodine (200, effective)

Noble Gas (1)

Particulates (co)

Rate of Release from Fuel Puff Environmental Release Rate All airborne activity released within a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period (or less if the ventilation system promotes a faster release rate)

Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-47A FUEL HANDLING ACCIDENT IN THE FUEL HANDLING BUILDING OR CONTAINMENT Analysis Assumptions & Key Parameter Values Environmental Release Points and Rates Accident in SFP in the FHB - Release flow

-Plant Vent - 46,000 cfm rates FHB Outleakage

-Ingress/Egress locations - 30 cfm

-Miscellaneous gaps/openings - 470 cfm Minimum free volume in FHB above SEP 317,000 ft3 Accident in Containment - Release flow rates

-Open Equipment Hatch - All airborne activity released in 2 hrs Minimum Free Volume in Containment above 2,013,000 ftJ Operating Floor CR Emer~qency Ventilation: Initiation Siq nal/Timin~g Signal(s) available to switch the Control Room Radiation signals from gamma sensitive Ventilation System (CRVS) from normal intake monitors that initiate closure of the operation (NOP) Ventilation (Mode 1) to CR normal intake dampers and switch the Pressurized Filtered Ventilation (Mode 4)

Control Room Ventilation System from following a FHA normal operation Ventilation Mode 1 to Pressurized Filtered Ventilation Mode 4.

Radiation Monitor Analytical Safety Limit 1 mR/hr Delay time for CRVS Mode 4 operation, 32 seconds (see below) including monitor response, signal processing, and damper closure time Radiation Monitor Response Time 20 seconds (conservative assumption) -

(Refer to Section 15.5.22.2.4)

Radiation monitor signal processing time 2 seconds NOP Ventilation Damper Closure Time 10 seconds Bounding Control Room Atmospheric Table 15.5-47B Dispersion Factors for FHA Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE TEDE Expo...res., rom*

+r Orcindr;.'n 0 _n Ir...

h-R--z-Qa Design basis case

~26~

CcteIreeB,,,,

Re~e4e~j-Li~4t Dcsign basis case Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE I

TABLE 15.5-47B FUEL HANDLING ACCIDENT IN THE FUEL HANDLING BUILDING OR CONTAINMENT Control Room Limiting Atmospheric Dispersion Factors (sec/rn 3)

Release Location / Receptor 0-22 s 22 sec -2 hr I2-8 hr 18-24 hr 1-4 d I4-30 d*

Control Room Normal Intakes Containment Hatch Release

- Affected Unit Intake 2.61E-02 L-

- Non-Affected Unit Intake 2.88E-03...

Plant Vent Release___________

-Affected Unit Intake 1.67E-03

- Non-Affected Unit Intake 9.10E-04 FHB Out-leakage points

- Affected Unit Intake 6.98E-03

- Non-Affected Unit Intake 2.93E-03

.L7-Control Room Infiltration Containment Hatch Release 5.51 E-03 5.51 E-03 Plant Vent 1.26E-03 1.26E-03 FHB Out-leakage points 3.78E-03 3.78E-03 Control Room Pressurization Intake Note 1" Release from the Containment Hatch: applicable to FHA in Containment Note 2: Release from Plant Vent / FHB Out-leakage: applicable to FHA in FHB Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-470 ISOTOPIC GAP ACTIVITY - FUEL HANDLING ACCIDENT Single Fuel Assembly (Decayed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

Activity Gap Fraction Gap Activity per Per Assembly Assembly (w/o Peaking Nuclide (Ci)

Factor) 1-129 2.07E-02 0.05 1.04E-03 I-130 3.29E+0~2 0.05 1.65E+01 1-131 4.09E+05 0.08 3.27E+04 1-132 3.99E+05 0.23 9.18E+04 1-133 9.73E+04 0.05 4.87E+03 1-135 5.01E+02 0.05 2.51E+01 KR-83M 2.51 E-04 0.04 1.00 E-05 KR-85 5.75 E+03 0.35 2.01 E+03 KR-85M 1.77E+00 0.04 7.08E-02 KR-88 7.73 E-03 0.04 3.09 E-04 XE-127 9.64E-02 0.04 3.86E-03 XE-129M 5.28 E+01 0.04 2.11E+00 XE-131 M 6.96E+03 0.04 2.78 E+02 XE-133 8.31E+05 0.04 3.32E+04 XE-133M 1.88E+04 0.04 7.52E+02 XE-135 1.07E+04 0.04 4.28 E+02 XE-135M 8.18E+01 0.04 3.27E+00 CS-132 2.16E+01 0.46 9.94E+00 CS-134 1.25E+05 0.46 5.75 E+04 CS-134M 1.04E-03 0.46 4.78E-04 CS-135 3.01 E-01 0.46 1.38E-01 CS-136 3.10E+04 0.46 1.43 E+04 CS-137

'7.10E+04 0.46 3.27E+04 RB-86 1.16E+03 0.46 5.34E+02 RB-87 1.37E-05 0.46 6.30E-06 RB-88 8.63E-03 0.46 3.97E-03 Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE DE*iGN_*

INPUDI TS ANDl ASSUMPh*TIONS~l FORD FEliL HA, NDLINGI-*

A 1 CCIDEN~TS INSIDEn, CONTAINIMENkT fParameter a~

Containmc....t Frcc Voum (f,

t*

.5E0 Purge Line Flo'wrate to Envrnmn (CM SQ Depth of Watc*

Abo, D... m d Fue (..ft) 3 Iodine Dcnt...m+in;ation Factors:

IOrganic (Eemntl Onergallnffcte 2'..

+*00 Duration of

" Release (c'"")

Time of Accident, aft*.er, Shudow

h. )

1,*-00 Nulmber of Familed* R*"od24 Gap ^"+i;"L,' Released from, Dam-a.ged Rods (0%:

,odie Gap Inventor; (o%):

Reactor Poe

(...

%R/

TP) 1-05 Reactor Powe..r (M4*t)\\

3580

-Rad~a! ekng Facto; 145

-444E+0

-I-1434 1.07-E+03

-F48*3.13E+04 Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15. 18A

~heet-1-ef 2 DESIGN INPU, TS ^ANDASSUMPDTIONS FOR FUE H', ANDLINGM ACCID*ENTS INSlerE CONTAINIMENIT Paramete*

Value Control Room (CR) Inu D.. ta:..

Control Room..

Vo.u...

(U! +U2) (cubic fcct)

F~eI:nwfe of retire~ CR nir f.hri, f!hfera-240 CR pressurization air filter:

CR Ocua nc, Facors

A (P* N,,r 24RGhee 4-04 Atopher-ic

p Control Room P; -8-hours 8

21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months 21 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months

cri, i*,,-actors (scc/m)9 ressur~ati9n:

7.05E 05 2.27-E-05 Connro~l Room~r Iniltrtion -

8 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months 21 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 96 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 1.96E-0"4 1.0BE-04 5.29E 04 Exc~usion Area Boundary (EAB), 800 met.r..

Lo0 P opurainZns(P)000 ees 2A-ho-rs Control Room Breathing Rate (m*/se4.

1 3 0-da...

2~0~-Q5

~7-~-0g 1~4E-0g 3A7E 01 3.47E -04 1.75E 04 2.3E-04 Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE ACTI\\IITY RELE IASES FROM FUEVL HANDLIN ACCIDr',ENT,I*NSID CONI*TA INMENII*T (CUIEIS):

0--.2 1-434 0

44.-O72-22 KFS~m0.00607-04 Kr-88 2.2275SE-05 Xe-4-31

-e33144084-e45248.955 Xe13-7:

0 X-e--38 0

Revision 15 September 2003

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 50

SUMMARY

OF OFFSITE DOSES FROM FUEL HANDLING ACCIDENT INSl ID'E CON'

iTAtINMl #ENfT Thyroid Exposurcs, rom 10 CFR Part 100 caee~bss 10 CFR Part 1 00 Conro(Rom 3GDas 2*I,g'P4 O

Whoe7odx4 mcrio 0g43 I 700 Population Dos....m.. remn Design basis cs E-xpected-cese

_73_

Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 51 CI-..-~~-A ~1 ~-d 0 APTI\\/ITV DI=I r-AQEQ IZAI LOWING A RDn EJECrTION ACCIDNmT (CrlES)~q

~.'ucIide 343 P1-134

-I 132 ORG I 133 ORG

!-!350RG

-t 131P-AR I-1324P-AR Kr--8M Xe-I-35M Xe43='SM

0. 9765' E 0 0.1578E 02 0.7304-!.E02 0.1872E 02 0-0 0-0 0-0 0,0 0-0 0-0 0-0 0-0 0.7646E 0!

0.1066E 01 0.3500E 00 0.2570E 00 0.7005E 00 0.!1!23E 02 0.18 57 E 00 0.2577E 01 0.7-913E 0-0 0-0 0,0 0-0 0.-69 0 0.,90 0

0-646E--00 O,.57-8E--0*

0.12583E 00 0.2070E 03 8-24-hf 0.0 0,0 0-0 0-0 0,0 0.7-0 0

0.8!,0 E0 0.377 0 0.4580 0

0.3679E-!0 24-95-hf 0,0 O-0 0.908E0 0.!!0 0

0.!!.0 E0 0.-02 0 0.290 0

0.-!70 EO 0.!,0 0

0-01 r A 0.39508E-32 0-0 0-0 0-0

0. 70 E0 0--,0-8=0 0-0 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 51 Sheet-1-ef-AC"TI\\/I"F RELEIASES FOt"lLOING*'Mik A RD'*'

EJECI=*TIONlx ACCIDEN~lkT (CURES)i-*'

N4=uc1idte hr 2--

8-2-4-ht 24-96-hF 4*n..

4--.

4646E-O-2 0,0 0,0 0*

0M0 P-20.2675E 03 0,

0, 0,0 0,0 P20.!2'I,7E 2

0,0 0*

0, P434-0.2963E 03 0,0 0,0 0,

0.6529E 0,0 0,

080 0,0

!-!340RG 0,0 Q,0 0*-

0, b135ORG 0,0 0,0 0,

0, P43-1-PAR 0,0 0,0 0,

0, 0,0 P4!33PAR 0,

0,0 Q,0 9,0 9,0 P-4-4P-AR 0,

0, 9,0 0,0 0,0 Kr-B3M 0.3823E-0!4.08E0 0.3684E-020.7E05.!3E!

r-0.53209-E O

.1599ED0

.20 0

50 1

0.8242E-02 Kr88

.150 0

.28E 0

.68E 00.7387E

-02 0.87-75E K-r8 0.!205E O0 0.6227E-04 0.2430E-02 0.1922E-06 0.145!5-23 Kr-8 0.503E00 0.4!92E 00 0.!80E00 0.!097E-02 0.!45 0 Xe-I33M 0,9,285E-01 0n2650n0 nn n6462E-0O 0,82365-0 nn n

9o-0nn X0.1-62E 00

~

0-.4E-04-.!2E0 0.3887-5-00 0,4724E-02 Xe M0.1289E-04 0.8268E-04 0.7!07E54 0!O.070E-29 0,0 Xe-1-32 04,8875--

0.035E 03 0.!840E- !!

8-478=-32 40, Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-52

SUMMARY

OF OFFSITE DOSES AND CONTROL ROOM DOSESFRM MA-CONTROL ROD EJECTION ACCIDENT Dose (TEDE. rem)

Regulator,/

Limit (TEDE, rem)

Maximum 2-hour Exclusion Area Boundary Dose 1 Containment Release Secondary Side Release 30-day Integrated Low Population Zone Dose

-Containment Release

-Secondary Side Release 30-day Integrated Control Room Occupancy Dose

-Containment Release

-Secondary Side Release 6.3 0.7 0.7 6.3 0.3 0.2 5

3.4 0.5 Thyroid*"'"

E-p urorem 10* CFR PartH 100I E-xpeeted-ease 300

3. x !04 1-4 xx10 4 1.4 x-!0-Who!e Body Exposures, rem

'2 fa Dn.,r.rl..,r~,

0 U,, 1 Ire I

7 z P r,**

2-5 10 CFR Part 100 25 Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE Nopeted-a:00

1. The maximum 2-hour EAB dose occurs between 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Revision 11 November 1996

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15.5-52A CONTROL ROD EJECTION ACCIDENT Analysis Assumptions & Key Parameter Values Parameters Value Containment Leakaqe Pathway Power Level 3580 MWt Free Volume 2.550E+06 ft3 Containment leak rate (0 -24 hr) 0.1 % vol. fraction per day Containment leak rate(I-30 day) 0.05% vol. fraction per day Failed 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% elemental 95% particulate 0.15% organic Radial Peaking Factor 1.65 Core Activity Release Timing Puff Form of Failed Iodine in the Containment 97% elemental Atmosphere 3% organic Equilibrium Core Activity Table 15.5-77 Termination of Containment Release 30 days Environmental Release Point Same as LOCA Containment Leakage pathway Secondary Side Pathway Reactor Coolant Mass

[446,486 Ibm Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1 5.5-52A CONTROL ROD EJECTION ACCIDENT Analysis Assumptions & Key Parameter Values Parameters Value Primary-to-Secondary Leak rate 0.75 gpm ( total for all 4 SGs); leakage density 62.4 Ibm/ft3 Failed Fuel Percentage Same as containment leakage pathway Percentage of Core Inventory in Fuel Gap Same as containment leakage pathway Minimum Post-Accident SG Liquid Mass 92,301 Ibm I SG Iodine Species released to Environment 97% elemental 3% organic Time period when tubes not totally submerged Insignificant Steam Releases 0-2 hrs: 651,000 Ibm 2-8 hrs: 1,023,000 Ibm 8-1 0.73 hrs: same release rate as that for 2-8 hrs.

Iodine Partition Coefficient in SGs 100 Fraction of Noble Gas Released 1.0 (Released without holdup)

Termination of Release from SGs 10.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months Environmental Release Point MSSVs/10% ADVs CR emer~qency Ventilation: Initiation SiqnalfTiminqi Initiation time (signal)

_300 sec (SIS Generated) 312 sec (Non-Affected Unit NOP Intake fully Closed) 338.2 sec (Affected Unit NOP Intake fully Closed with full Mode 4 Emergency Ventilation Operation).

Control Room Atmospheric Dispersion Factors Table 15.5-52B Revision 11 November 1996

DCPP UNITS 1 & 2 ESAR UPDATE TABLE 15.5-52B CONTROL ROD EJECTION ACCIDENT Control Room Limiting Atmospheric Dispersion Factors (sec/in3)

Rees oainI 0-2hr 2-8hr 8-10.73hr 107-24-96hr 96-721Jhr Receptor 24hr CR Normal Intakes Containment leakage

- Affected Unit Intake 6.84E-03

- Non-Affected Unit Intake 2.24E-03 MSSVs/10% ADVs

______[

-Affected Unit Intake Note 3

- Non-Affected Unit Intake 8.60E-04

....I CR Infiltration Containment leakage j3.22E-03 1.85E-03 7.29E-04 7.29E-04 7.15E-04 6.64E-04 MSSVs/1 0% ADVs j2.78E-03 1.63E-03 1.63E-03 CR Pressurization Intake Containment leakage 6.45E-05 4.05E-05 1.65E-05 1.65E-05 1.38E-05 1.12E-05 MSS Vs/i10% ADVs 1.57E-05 9.60E-06 9.60E-06 Note 1: Containment leakage: Used for Containment release scenario; based on Containment penetration 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 normal operation CR intake of the affected unit, and due to the high vertical velocity of the steam discharge from the MSS Vs/i10% ADVs, the resultant plume from the MSSVs/10% ADVs will not contaminate the normal operation CR intake of the affected unit.

Revision 11 November 1996

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15. 63 POST LOCA DOSES WITH,MARGIN RECIRCULATION LOOP LEAKAGE rt'flMT~f-I Dfl0lU flDr-DATflD rnflQpp (DCIU\\

-Gamma Containment leakage RHR pump seal leakage Recircu...lation loop leakage:*,

n 0.8 gpm with.

÷* no filtration Plume radiation (egress ingress)

Ot'lher dretlrnl radiatonlr pathway,*se

&6,9 4&42 4-,Q 0,034 0,0

0.000 0,0003 8480 0,0 0,004 Notes 23 3

10 CF RPART 50 APPENDIX A, GDC 19 LIMI.TS S

30 SITE BOUNDARY Pathway Gamma 1/2 N~es Containment leakage RHR pump..

sea leakage Recirculatlion loop* leakage:

1.8 gpm, with charcoal filtration, or 0.189 gpm, wilth no filtration TOTAL SITE BOUNDARY DOSES Pathway RHR pump seal leakage

-Expected rci~rculation loop,

,.aka'wb Recirculatien loop, leakage:"

1.11 gpm, w-ith no filtratlon 9,0

&-2-2 8,34 0,0 2-

-Gamma 1/2-y*

Whl-e 00,9 2 -........

2*

8-24,39 0,0@

0,44 2-TOTAL LPZ DOSES In* 0CD CAnT Iflf I-flf-l--

I I41ATC 2-5

1.

RHR pump seal leaag of. 50 gpm for 30*, mm,-

Tables 15.5 21! and 15.5 33.

_.*.. L:__

l--I A L WOO, 0011 ring Li nouiu ~aw [110 OUJIL Ul 1110 ou~:x, ouu at the start of the LOCA and continuing for 30 days.

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 61 PARA~METE RS USED [N EV~ALUATING Sheet-4-ef -

B. Tota-l ste-am generI4ato ubeaae C. Reactor,. coo-,-lant activit.

1~o

1. Accident initiated spike

2. Pro accidont spike

3. Noble gas activity The initial DRC iodine activities based, on in Table 15.5 65. The iodine Table !5.5-6~

on 60 ptCi/gram of D.E. 1 131 are pre.ente in,4; Table* 1 5.5 65 The, initial*, R,,OD noble gas activities based presentedl in Table 15. 65R 2.27-x !n8 A 3 7v 1t"-

D. Secondary system initial activity E. Reactor coolant mass, grams F. lnitial steam goncrator mass (each),

G. Offsite power H. Primary to secondary leakage durati for intact SG, hrs I. Species of iodine en-Lost at time of reactor trip S

100 percent elemental Revision 19 May 2010

DCPP UNITS 1 & 2FSAR UPDATE P^AP~M'TE~

1. Rupture flow

2. Flashed rupture flow

3. Iodine scrubbing efficiency

1. Total steam release, lbs.

5. Iodine partition coefficient non flashed flashed B. Intact steam generators

1. Total primar; to secondar,' leakage, gprn

2. Total steam release, lbs See Figure..

15.4.3 6b and

Table45SA-14 400 470 See Figure 15.1.3 10 and ra~e45444 1-00

3. Iodine partition coefficient C. Condenser

1. Iodine partition coefficient D. Atmospheric dispersion factors 1-00 See Table 15.5 68 TABLE 15.5-64

SUMMARY

OF OFFSITE AND CONTROL ROOM DOSES STEAM GENERATOR TUBE RUPTURE Dose (TEDE. rem).

Re culatorv Limit

.(TEDE, rem)

Revision 19 May 2010

flCPP JNIT~ 1 ~ 2 F~AR IJPDATF TABLE 1 5.5-61 Sheet--2-of--2 PAPR,[METERS USED iN EVALUATING PRDIOLOGICAL CONSEQUENCES FOR SGTR ANALYSIS Maximum 2-hour Exclusion Area Boundary Dose1

-Pre-incident iodine Spike

-Accident-Initiated Iodine Spike 1.3 0.7 25 2.5 30-day Integrated Low Population Zone Dose Pre-incident iodine Spike Accident-Initiated Iodine Spike 0.1

<0.1 25 2.5 30-day Integrated Control Room Occupancy Dose Pre-incident iodine Spike Accident-Initiated Iodine Spike 5

0.6 0.3 Note:

1. The maximum 2-hour EAB dose occurs during the O-2hr time period :

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1 5.5-61 DADANAfrIEDcO i iCE i~tt*

I Al~

I IAT!Irt" Sheet-2-ef-a DAr'*lt'*l C'tf*_IPAI Pt'*klQCCI IEI*IPI:::*

Et"*D Q(-*_TD AklAI VQI*

TABLE 15.5-64A STEAM GENERATOR TUBE RUPTURE Analysis Assumptions & Key Parameter Values Parameter Value Power Level 3580 MWt Reactor Coolant Mass 446,486 Ibm Time of Reactor Trip 179.0 sec Time of isolation of stuck-open 10% ADV on 2653 sec the Ruptured SG Termination of Break Flow from Ruptured SG 3402 sec that flashes Termination of Break Flow from Ruptured SG 5872 sec Time of manual depressurization of the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Ruptured SG Break Flow to Ruptured Steam Generator that Table 15.5-64C, Column "A" flashes Break Flow to Ruptured Steam Generator that Table 15.5-64C, Column "B" does not flash Tube Leakage rate to Intact Steam Generators 0.75 gpm (total for all 4 SGs; conservatively assumed for 3 intact SGs); leakage density 62.4 Ibm/ft3 Failed/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 IpCi/gm DE Xe-133 (Table 15,5-78)

RCS Equilibrium Iodine Appearance Rates Table 15.5-79 Revision 19 May 2010

flCDD I INITQ 4

9)

IQAID I IDEfATE TABLE 1 5.5-61

~hee4-2-ef-2 RADIOLOGICAL CONSEQUENCES FOR SGTR ANALYSIS TABLE 15.5-64A STEAM GENERATOR TUBE RUPTURE Analysis Assumptions & Key Parameter Values Parameter Value (1 IJ~i/gm DE 1-131)

Pre-Accident Iodine Spike Concentration 60 p Cl/gm DE 1-131 (Table 15.5-79)

Accident-Initiated Iodine Spike Appearance 335 times TS equilibrium appearance Rate rate Duration of Accident-Initiated Iodine Spike 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Initial Secondary Coolant Iodine 0.1 IpCi/gm DE 1-131 (Table 15.5-78)

Concentrations Secondary System Release Parameters Initial SG liquid mass 89,707 Ibm / SG Iodine Species released to Environment 97% elemental; 3% organic Steam flow rate to condenser from Ruptured 63,000 Ibm/mmn SG before trip Steam flow rate to condenser from intact SGs 189,000 Ibm/mmi before trip Partition 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 Ibm Ruptured SG Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE D*AD:)Ar.

ri*,E

-'-Dc)

I icil'--l IMl E\\/AI I rATIMc*-

2 RADIOLOGICAL CONSeqUENCES FOR SGTR ANALYSIS TABLE 15,5-64A STEAM GENERATOR TUBE RUPTURE Analysis Assumptions & Key Parameter Values Parameter Value Post-accident minimum SG liquid mass for 89,707 lbm per SG intact SGs Time 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 100 Termination of Release from intact SG 10.73 hrs Environmental Release Points

_.Plant Vent : 0 - 179 sec MSSVs/10°0LADVs:179 sec - 10.73 hr_

CR emer~qency Ventilation : Initiation Signal~fiminq Initiation time (signal)

SIS: 219 sec Unaffected Unit inlet damper closed:

231 sec Affected Unit inlet damper closed:

257.2 sec Control Room Atmospheric Dispersion Factors Table 15.5-64B Revision 19 May 2010

I*IDI INIITQ "1.9. ') C(AD I IDIlATE pAR^*METES USED,-

IM N_.\\

EAU ATiNG":

PAfrlirl. fl(.C.AJ.r.C.NFO fJFT.J.F:.Q Ffl)R g*T.P AN.Al Y.*!*

Revision 19 May 2010

r'*rDD I INIIT

'14 Q "0 ~cAD I IDI*ATEz TAI'IBLE 41::.56_

8h6e4-2-ef-2 PADR*METEDS USIED INI EVALUlIIATING'*

DAflICU-X

('crCAI

¢(*'v*NI.lC'r""I Iclrz",rC ECD C'rTD ANAlAI VC'IC' TABLE 15.5-64B STEAM GENERATOR TUBE RUPTURE Control Room Limiting Atmospheric Dispersion Factors (sec/rn 3)

Release Location / Receptor 0-179 s 179-257.2 s 257.2 s-2 h 2-8 hr 8-1 0.73 [r CR Normal Intakes

- Plant Vent 1.29E-03______________

-MSSVs/1 0% ADVs (Note 1) 8.60E-04 CR Infiltration

- Plant Vent

[1.26E-03

___]___

- MSSVs/1 0% ADVs 2.78E-03 j2.78E-03 1.49E-03~ 1.49E-0:

CR Pressurization Intake

- MSS Vs/i10% ADVs 1.57E-05 7.65E-06 7.65E-0(

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 65 IODIN*E SPECIFICACTIVITIESr IN THlE PRIMARY AND-SECOND-ARY COOLAMT*) _ SGTR ANALYSIS Nueliade 4&34 143-2 0-_7-94

~-_14-3 0-4-39 4-2-24 6677-8 0707-94 070204 0*-5A43

(~) Baczd on 1, 60 rind 0.1 1iCi/gm of Do~c Equivalent 1131 Spccificationc (Refcrence 22).

con ~~~tent '~'ith the DCP P Tcchnical Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 66 IODINE SPIKE,APPEARAHNCE RATES*

SGTR AN.ALYSIS (CI U R I1: ES/SlECOND 2-A6 1*

4-_442-340-

~~The accident initiatcd spikc ~ppe~ran equilibrium appearance into is c~lcuk is comprised of 120 gpm with pe~ect Gte int* o ms 33 U;mes thc equilibrium,ppea'nn

...++ Tho d bascd onI a total ledwn@I iflow of 113 gpm. Tis totll Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLEI "15. 6*7 NHOBLE GAS SPECIFIC ACTIVITIES IN THE RECO O'_A T B.ASED ON 1% FUEL DEFECTS -SGTR ANALYSIS Xe--1-Thm Xe-I-ga 2T -2a 8*64g 2-_441 6-.2OO

'B--ed on a 2 year fuJe[ c..l. at cor po....e.. of 3580 MVV/t. a 75 nom reactor coolant sy;stem letdow:n flow:

Revision 16 June 2005

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5 68 ATMOSPHERIC DISPERSION FACTORS AND BREATHING RATES SGTR ANALYSIS O*ESQITE-EXPOSURE~l 0-2 2*4

o. 2-x49

&47-x-1-0 4 2-8 272-v 1-O 3A7 v x r-14 CONTROL ROOM EXPOSURE 0-8 7-7n5-x-4 1-96.--

4 34t_7_xI-4Q 8-2-4 5.38-x-10 4 1.~49-x-1-4.

3.4,7 x4!0.

2-4-96 3.9!-x !4-!

.~8-x-!O 4

3.47-x !04

~g2.2-7--x40*

&290--*4O4&4-x-0 Note 1 :

Due to the proximity of the release from the MSSVs/10% ADVs, to the normal operation CR intake of the affected unit, and due to the high vertical velocity of the steam discharge from the MSSVs/IO% ADVs, the resultant plume from the MSSVs/IO% ADVs will not contaminate the normal operation CR intake of the affected unit.

Thus the 7J s presented reflect those applicable to the CR intake of the unaffected unit.

Revision 16 June 2005

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-64C STEAM GENERATOR TUBE RUPTURE Break Flows and Steam Releases Break Flow and Steam Release within each Time Interval.

_A 8

_C

_D Time Flashed Un-flashed Ruptured SG Intact SGs from Break

.Break Flow Break Flow SemSteam Releases Releases

___c_

(Ibm)

(bm) flbm) 0___1678____

8422 187822 563100 179___2217 30003 10527 42565 8321190754 113657 118 2653___

1355 15906

___0 146 2953 779 2317 0

85467 3402 05260 97164 4324 016870 0

9237 4739 023892 0

29103 5872 00 0

103300 7200 0_________0 270000 1,342,400 38628 0

________0 0

0 Note: Data in row for T=0 is applicable to time interval between T=0 sec to T=1 79 sec (typ)

Revision 16 June, 2005

DCPP UNITS 1 & 2 ESAR UPDATE T:ABLE 155 6 THYRDl D DOS CONVERSZON F^ACTORS S GTR ArealYviS N~Glide

'434 4432 44~3 4434

'435 1.07 -106eeemTG;4e) 8.29 x I 0 mI*u*

SInt....ato""'

Commission on" Radiological Prctecti,,n Publication 30, 1979.

Revision 18 October 2008

DCPP UNITS 1 & 2 FSAR UPDATE

,AVERP.,GE GAMMA, AND BETA ENERGY FOR NOBLE GASES*

SGTR ANA*LYSIS

4433, O76 042 Xe4-33m~

0702:

024-Xe433 070304 Xe-435 0725 0732 Xe-4-8

-12 0766 046 07254 K-r-88 272 72 (a)-- ENDF 223, Octobe 197 (Rfrnc6 Revision 16 June 2005

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15.5 71 OFFSITE PRDIATION DOSES FROM SGTR ACCIDENT

\\

a,-4hd AVoalue Guiefernce37 Thyroid ODE Thyroid ODE l~

27 14

2.

Pre Accident Iodine Spike Thyro~id ODE Lo..

opulation Zo+;..

,ne (0 8 hr.)

Thyroid ODEc Whole Body Gamma DDEc LowPopulatin r,"

Zoner.-n (0 8 hr.

W^hole, Body4, G.mma DDE

4.

PreAccident Initiated Iodine Spike WAIn,-I IR,-,x' m',*'rnmn, l'

n 2~5 Exclusionm Area' Bounda4r,' (0- 2 hr.)

Low Population Zone (0O 8 hr.1 Whole Body Gamma DDE 0702 SNotc:

A dooe limit of 30.5 rem hoc been approvcd by the NRC bo~ed on OSGo. Rcfer to Section 15.5.20.2.1(5) for fudher discueeion.

Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-72 rn*NsFn' JF.Nf'.F FCR S*TR.AN.ALYSIS Control,--, Room Volume,-,

'17-O-N-O 4--"t Control Room Unfiltered In Leakage 44Q-efm Control Room Unfiltered Inflow Control Room Filtered Inflow*

Normal Mode

-fi Revision 16 June 2005

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.571T COMTROL. ROOM RDIAlTiON DOSES* F~ROM AIRBORNE AC'TI\\ITY IN SGTR ACCIDENT Accident Initiated

~e-AGei4e~4 GDG49 Guideline, rem Bet Ski SDE*-

~02 Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE TABLE15.5 It *75 SUMMIRY**D OF POST ILOCA DOSES FDROM \\LARIOUSI PQATHWAYSV (DF-OF !00}

THYRIDI3I DS-*ES. rerm 10 CFR Part 100 RHR Pump Seal (50 "gpm) 300 40740*

0 300 0709 Tet~al

'A'HOLE BODY DOSES, rem LP~Z 30dc 10 CFR Part 100 Pre-existing leak (191 0 cc/'hr) 25 3724 25 07203 070 07003 07295 Revision 19 May 2010

DCPP UNITS 1 & 2 FSAR UPDATE

,TABLE 15.5 76 WHOLE BODY DOSE CONVERS!ON FACTORSe)

DOSE EQUIVALENT XE 133 7.48E4-!5(Sv m*Iqs K-r8--

4!2 14 (Svm~ilB-s)

-Xe-433, 1.3E v-(vm*,Llq-s Xe4-352.4 14 (Svma/Be-s}

X~e-1-48 5.77E !4 (Sv m

<a}-Table 111.1 of Federal G'-idance Report 12, ERA, 1I02 R 93 081, 1093.

Soe* t,,,

he AOR used.......c÷'"ti walues,,,th respect to' the abov,.*

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-77 DCPP EQUILIRIUM CORE INVENTORY (Power Level: 3580 MWth)

Dose Significant Isotopes including the Parent, Grandparent and 2nd Parent Isotopes ACTIVITY ACTIVITY ACTIVITY ISTP*

(CURIES)

ISTP*

(CURIES)

IO PE(CURIES)

AG-ji0 2.67E+07 IN-i25 8.46E+05 SB-125 9.63E+05 AG-110M 6.92E+05 IN-127 1.86E+06 SB-127 9.14E+06 AG-I11 7.09E+06 IN-129 3.55E+06 SB-129 3.25E+07 AG-111M 7.09E+06 IN-131 1.09E+06 SB-130 1.08E+07 AG-1 12 3.16E+06 IN-132 2.85E+05 SB-1301M 4.38 E+07 AG-115 6.21E+05 KR-83M 1.14E+07 SB-131 7.67E+07 AG-115M 2.60E+05 KR-85 1.11E+06 SB-132 4.70E+07 AM-239 4.90E-01 KR-85M 2.33E+07 SB-I132M 4.37E+07 AM*-241 i.32E+04 KR-87 4.65E+07 SB-133 6.32E+07 AM-242 9.40E+06 KR-88 6.43E+07 SB-134 1.14E+-07 AM-242M 8.54E+02 KR-89 7.94E+07 SB-i135 5.46E+06 AM-243 5.28E+03 KR-90 8.48E+07 SB-i136 8.63E+05 AM-244 3.79E+07 KR-91 5.83E+07 SE-83 5.38E+-06 AM-245 1.12E-03 KR-92 3.12E+07 SE-83M 5.65E+06 AS -76 3.05 E+03 KR-93 1.07 E+07 S E-84 2.04 E+07 AS-83 7.02E+06 KR-94 5.O0E+06 SE-85 9.54E+06 BA-137M 1.30E+07 LA-140 1.85E+08 SE-87 1.32E+07 BA-i39 1.76E+08 LA-141 1.61E+08 SE-68 7.15E+06 BA-140 1.78E+08 LA-142 1.57E+08 SE-89 2.49E+06 BA-141 1.59E+08 LA-143 1.48E+08 SM-153 6.04E+07 BA-142 1.51E+08 LA-144 1.31E+08 SM-155 4.30E+06 BA-143 1.29E+08 MO-99 1.84E+08 SM-156 2.66E+06 BA-144 9.93E+07 MO-10I 1.69E+08 SM-157 1.70E+06 BR-82 4.44E+05 MO-103 h.62E+08 SN-121 8.43E+05 BR-82M 3.88E+05 MO-104 1.33E+08 SN-123 6.43E+04 BR-83 1.13E+07 MO-105 9.97E+07 SN-125 5.25E+05 BR-84 2.10E+07 MO-l06 5.86E+07 SN-125M 1.58E+06 BR-85 2.31E+07 NB-101 1.59E+08 SN-i 27 3.69E+06 BR-87 3.67E+07 NB-104 5.10E+07 SN-127M 4.95E+06 BR-88 3.52E+07 NB-95 1.66E+08 SN-129 1.28E+07 BR-89 2.45E+07 NB-95M 1.89E+06 SN-129M 1.17E+07 BR-go 1.35E+07 NB-97 1.59E+08 SN-130 3.28E+07 CD-115 9.17E+05 NB-97M 1.50E+08 SN-131 2.83E+07

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-77 DCPP EQUILIRIUM CORE INVENTORY (Power Level: 3580 MWth)

Dose Significant Isotopes including the Parent, Grandparent and 2nd Parent Isotopes ACTIVITY ACTIVITY ACTIVITY ISOTOPE*

(CURIES)

ISOTOPE*

(CURIES)

ISOTOPE*

(CURIES)

CD-115Mi 4.43 E+04 NB-99 1.07E+08 SN-132 2.28E+07 CD-121 7.67E+05 NB-99M 7.35E+07 SN-133 6.21E+06 CE-141 1.63E+08 ND-147 6.59E+07 SN-134 1.07E+06 CE-143 1.50E+08 ND-149 3.90E+07 SR-89 9.05E+07 I

CE-144 1.26E+08 ND-151 2.08E+07 SR-90 9.67E+06 i

CE-147 6.18E+07 NP-238 6.20E+07 SR-91 1.13E+08 CF-249 2.46E-02 NP-239 2.16E+09 SR-92 1.22E+08 I

CM-241 3.54E+00 NP-240 6.23E+06 SR-93 1.39E+08 I

CM-242 5.88E+06 PD-109 4.73E+07 SR-94 1.39E+08 CM-244 1.31 E+06 PD-109M 3.12E+05 SR-95 1.25E+-08 CM-245 1.26E+02 PD-111 7.09E+06 SR-97 4.68E+07 CO-58"*

0.00E+00 PD-112 3.14E+06 TB-160 1.87E+05 CO-6O"*

0.00E+00 PD-11.5 7.84E+05 TC-99M 1,63E+08 CS-132 5,75E+03 PM-147 1,68E+07 TC-IOI l,69E+08 I

CS-134 2.41E+07 PM-148 1.88E+07 TC-103 1,65E+08 CS-1 34M 5.63E+06 PM-148M 2.83E+06TC0410+8 CS-136_____7.____E+

PMV-149 6.43E+07 TC-l05 1.18E+08 CS-137 1.37E+07 PM-151 2.10E+07 TC-106 8.80E+07 CS-138 1.85E+08___

PM-153 9.77E+06 TE-127 9.03E+06 CS-139 1.72E+08 PR-142 9.47E+06 TE-127M 1.52E+06 CS-148 1.54E+08 PR-143 1.47E+08 TE-129 3.10E+07 CS-141 1.17E+08 PR-144 1.27E+08 TE-129M 6.30E+06 CS-142 6.80E+07 PR-144M 1.76E+06T-3182+0 CS-143 3.41E+07 PR-147 6.52E+07 TE-131Mt/

2.04E+07 DY-166 4.91 E+02 PR-149 3.57E+07 TE-132 1.41 E+08 EU-154 9.00E+05 PR-151 1.23E+07 TE-133 1.09E+08 EU-155 3.83E+05 PU-238 5.22E+05 TE-1331' 8.93E+07 EU-156 3.90E+07 PU-239 3.06E+04 TE-134 1.75E+08 I

EU-1 57 4.12E+06 PU-240 4.87E+04 TE-135 9.68E+07 EU-158 1.01E+06 PU-241 1.36E+07 TE-136 4.29E+i07 EU-159 5.15E+05 PU-242 3.34E+02 TE-137 1.45E+07 GA-72 1.71E+03 PU-243 7.36E+07 TE-138 3.65E+06 GA-77 1.66 E+ 05 RA-224 5.16 E-01 T H-228 5.14 E-01 GD)-159 "8.91 E+05 RB-86 2.50E+05 U-239 2.17E+09 GE-77 6.48E+04 RB-86M 2.07E+04 XE-1311M 1.42E+06

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-77 DCPP EQUILIRIUM CORE INVENTORY (Power Level: 3580 MWth)

Dose Significant Isotopes including the Parent, Grandparent and 2nd Parent Isotopes ACTIVITY ACTIVITY ACTIVITY ISTP*

(CURIES)

ISTP*

(CURIES)

STOE(CURIES)

GE-77M 1.70E+05 RB-88 6.60E+07 XE-133 2.01E+08i GE-83 1.24E+06 RB-89 8.57E+07 XE-133M 6.42E+06 H-3 6.10E+04 RB-90 7.86E+07 XE-135 4.92E+07 HO-I166 2.58E+i04 RB-90M*

2.53E+07 XE-i135M 4.30E+07 1-129 4.00E+00 RB-91 1.05E+08 XE-137 1.84E+08 1-130 3.58E+06 RB-92 9.35E+07 XE-138 1.70E+08 1-130M 1.92E+i06 RB-93 7.89E+07 XE-139 1.25E+08 1-131 9.90E+-07 RB-94 4.13E+i07 XE-140 8.66E+07 1-132 1.44E+08 RBI-95 2.01E+07 XE-142 1.33E+07 1-133 2.01E+08 RH-103M 1.66E+08 Y-90 1.02E+07 1 -134 2.22E+08 RH-lO5 1.08E+08 Y-90M 7.71E+02 I-134M 2.07E+07 RH-105M 3.43E+07 Y-9i 1.19E+08 1-135 1.92E+08 RH-106 7.53E+07 Y-911VlI 6.57E+07 1-136 8.73E+07 RH-109 3.65E+07 Y-92 1.23E+08 1-137 9.40E+07 RN-220 5.16E-01 Y-93 9.41 E+07 1-138 4.80E+07 RU-103 1.66E+08 Y-94 1.50E+08 1-139 2.22E+07 RU-105 1.21 E+08 Y-95 1.57E+08 1-140 6.06E+06 RU-106 6.68E+07 Y-97 1.26E+08 IN-11SM 9.17E+05 RU-109 3.16E+07 ZN-72 1.71E+03 IN-121 7.55E+04 SB-122 1.57E+05 ZR-101 9.55E+07 IN-121M 7.82E+05 SB-122M 1.57E+04 ZR-95 1.65E+08 lN-123 6.87E+05 SB-124 1.21E+05 ZR-97 1.58E+08 SB-124M 2.34E+03 ZR-99 1.66E+08 Note:

Isotopes in Bold Font are dose-significant for inhalation, submersion and direct shine. The parent, grandparent and 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 the Site Boundary is typically a subset of the isotopes listed above in bold font, and represent a small group of reasonably long half-life isotopes with significant inhalation dose conversion factors which dominate the TEDE dose.

To determine the total effective dose equivalent (TEDE) resulting from inhalation and submersion following a LOCA, the DCPP LOCA dose consequence analysis uses the default group of 60 isotopes provided with computer code 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 I Co-60 are activation products that are developed external to the core and typically do not appear in the equilibrium core inventory

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-78 PRIMARY AND SECONDARY COOLANT Technical Specification Activity Concentrations Nulie Primary Coolant Secondary Coolant Ncie(uCi/Qm)

(uCi/,qm)

Kr-83M 1.87E-01 Kr-85M 6.60E-01 Kr-85 5.60E+00 Kr-87 4.41 E-01 Kr-88 1.22E+00 Xe-131M 1.88E+00 Xe-133M 1.92 E+00 Xe-133 1.29E+02 Xe-i135M 4.07E-01 Xe-i135 3.76E+00 1-131 7.87E-01 8.06E-02 1-132 3.00E-01 1.94E-02 1-133 1.16E+00 1.08E-01 I-134 1.67E-01 4.78E-03 1-135 6.68E-01 5.09E-02

DCPP UNITS 1 & 2 FSAR UPDATE TABLE!15.5-79 PRIMARY COOLANT Pre-Accident Iodine Spike Concentrations & Equilibrium Iodine Appearance Rates

Pre-Accident Spike Equilibrium Iodine Activity RCS Concentrations Appearance Rates into RCS (60 IpCi/gm DE 1-131)

(IpCi/sec)

Nuclide (pJCi/gm) 1-131 47.2 7.18E+03 I-t132 17.9 7.78 E+03 I-133 69.5 1.25 E+04 1-134 10.0 8.91E+03 I135 40.1 9.91 E+03

DCPP UNITS 1 & 2 FSAR UPDATE TABLE 15.5-80 ISOTOPIC GAP ACTIVITY LOCKED ROTOR ACCIDENT / CONTROL ROD EJECTION ACCIDENT Fraction of Core Gap Fraction of Core Gap Core Activity Core Activity Core Activity in wlo Peaking Activity in w/o Peaking Activity Gap Factor Gap Factor Nuclide (Ci)

LRA (Ci)

CREA (Ci)

LRA CREA KR-85 1.11E+06 0.35 3.89E+05 0.10 1.I1E+05 KR-85M 2.33E+07 0.04 9.32E+05 0.10 2.33E+06 KR-87 4.65 E+07 0.04 1.86E+06 0.10 4.65E+06 KR-88 6.43E+07 0.04 2.57E+06 0.10 6.43E+06 Xe-131M 1.42E+06 0.04 5.68E+04 0.10 1.42E+05 Xe-133M 6,42E+06 0.04 2.57E+05 0.10 6.42E+05 XE-133 2.01 E+08 0.04 8.04E+06 0.10 2.01E+07 XE-135 4.92E+07 0.04 1.97 E+06 0.10 4.92E+06 Xe-138 1.70E+'08 0.04 6.80 E+06 0.10 1.70 E+07 1-130 3.58E+06 0.05 1.79E+05 0.10 3.58E+05 1-131 9.90E+07 0.08 7.92E+06 0.10 9.90E+06 1-132 1.44E+08 0.23 3.31 E+07 0.10 1.44E+07 I-133 2.01 E+08 0.05 1.01 E+07 0.10 2.01E+07 1-134 2.22E+08 0.05 1.11E+07 0.10 2.22 E+07 1-135 1.92E+08 0.05 9.60E+06 0.10 1,92E+07 BR-82 4.44E+05 0.05 2.22E+04 0.10 4.44 E.+04 BR-84 2.10E+07 0.05 1.05E+06 0.10 2.10E+06 CS-134 2.41 E+07 0.46 1.11E+07-CS-136 7,01IE+06 0.46 3.22 E+06 CS-137 1.37E+07 0.46 6.30E+06-CS-138 1.85E+08 0.46 8.51E+07-RB-86 2.50E+05 0.46 1.15E+05-Rb-88 6.60E+07 0.46 3.04E+07-Rb-89 8.57E+07 0.46 3.94E+07-Note-Values reported reflect the core isotopic gap activity assumed for the LIRA and CREA. These values have to be adjusted for a) the failed fuel percentage (10%) and b) peaking factor (1.65), prior to assessing the associated dose consequences.

For the isotopic gap activity associated with the FHA refer to Table 15.5-47C.

DCPP UNITS 1 & 2FSAR UPDATE TABLE 15.5-81 CONTROL ROOM Analysis Assumptions & Key Parameter Values Parameter Value Free Volume 170,000 ft3 Unfiltered Normal Operation Intake Total 4200 cfm + 10%

Unit 1: 2100 cfmn + 10%

Unit 2: 2100 cfm _+/- 10%

Emergency Pressurization Flow Rate 650 - 900 cfm Maximum Unfiltered Backdraft Damper 100 cfm Leakage during CR Pressurization Operation Carbon / HEPA Filter Flow during CR 1800 -2200 cfm Pressurization Operation Emergency Filtered Recirculation Rate 1-250 cfm (minimum)

(Normal and Pressurization Mode)

Includes 10 cfm ingress I egress Occupancy 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 UPDATE TABLE 15.5-82 TECHNICAL SUPPORT CENTER Analysis Assumptions & Key Parameter Values Parameter Value Free Volume 51,250 ft3 Filtered Rate (HEPA only) Normal Operation Intake 500 cfm Flow Normal Intake HEPA Filter Efficiency(includes filter 98% (particulates) bypass)

Filtered (Carbon / HEPA) Pressurization Flow Rate 500 cfm Flow through Carbon / HEPA Filter during 1000 cfm Pressurization mode Filtered Recirculation flow rate during Pressurization 500 cfm (minimum) mode Pressurization Intake and Recirculation Carbon /

93% (iodine)

HEPA Filter Efficiency (includes filter bypass) 98% (particulates)

Unfiltered Inleakage 60 cfm (maximum)

Includes 10 cfm ingress/egress Occupancy 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)

v t e Letter Sequence Response to RAI
TAC:MF6399, (Open) TAC:MF6400, (Open)
Initiation Request Acceptance, Acceptance, Acceptance Supplement Administration Questions 22 September 2015 23 September 2015 1 October 2015 7 October 2015 20 October 2015 2 December 2015 11 January 2016 17 February 2016 Answers 17 December 2015 10 February 2016 21 April 2016 11 December 2015 17 December 2015 17 December 2015 17 December 2015 17 December 2015 Results Approval... Other:
MONTHYEAR2015-08-31 [Table View]

DCL-15-152, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - Updated Final Safety Analysis Report Markup, Revision 1. Part 3 of 3

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