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ENVIRO

/. mm:Pacific Gas & Electric CompanySan Francisco, California 94106F.'.'S'earls

DATa. OF Doc:

; 4-.6-'73 '-

"',Der" REC'D

4-.9»73.

bKiLO, RFf QTiKA

TOGordon K. Dicker,

'CZASS ij PROP Iii%0

..:,ORIG .'

signedZhVuT NO CYS REC'D

~ INTA C iDR'

BE. L LE

DOCK

50-275 50-323

DESCRIPZION:Zitr n'otaqized 4-6-73 trans the following

L

EiVCLOSURES:Supplemental Material Describing DiabloCanyon Blowdown Treatment System.'. ~

Supplementing Comment.No. 20 on',Draft EnviroStatement.....

pXj4g~i KQSS; Diablo Canyon Units ..I &2'hkMILEhE no NOT REINDUCE

(3 Orig & 47.conf'd cys rec'd)FOR ACTION Ll OZ:ATION fod

BUTZm(L)W/ CopiesCLArK(L)W/ CopiesGOLLER(L)W/ Copies

-~mrEL(z,)* 'W/1 Copies

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PA.CIFIC GA.S A.ND ELECTRIC 'OMPS.NTP (G7~MIE ~ 77 BEALE STREET ~ SAN FRANCISCO, CALIFORNIA 94106 ~ (415) 781-4211

P RE DE RICK T. S EARLSYICC TCCCIOCNT AND OCNCCAL COUNSEL

LIOAN C. MORRISSEYA'ICOCIATC OCNCSAL COVNSCL

WILLIAMD. IIV OCR

WILLIAMC, JOHNSMAI COLM H ~ PVRCSVSH

CHARLES T. VAN OLQVSCNMALCOLMA ~ MACIEILLOP

PHILIP A, CRANC, JR,ASSISTANT CIIQEAALCCUASIL

April 6, 1973O>~ P

P,PR9 <973 ~

TI1'.I I's'il71

U. S. Atomic Energy CommissionWashington, D. C. 20545

HOCL KELLYHC»1Y 4 LAOLANTEalc»kro* CLk1ACDISSECT L HA11ICCCOWASO J HCDANNCYJo»N 4, DISCO»4\EN» WC ~ T, JS,AST»US I HILL»AN Ja,C»ASLES W TNISSELL

~ CNIO ~ COUN~EL

aoscST Dl Lskc»~ ANYOSO H, 41ASOS~ TAIQLEY T ~ AINNCSDANIELC. DlscollDAN DSAYSON I.U~ SOCKJ, OAAOLEYOUNIQNQOEANASOJ DCLLAOANTAHOWASO V, DOLU~JACC O'ALLI»,41,DONALO L, TSCITASJANCS C I.OOSSONJO ~ ErN 4 CNOLCST,JSLONI~ C OC»O ~ IELOao ~ cST I ~ 01oo»DCN»l~ D, 4ULLIYk»KAT»YTocrk»1ao ~ EST L HA11IS

ATT4 1 N C T ~

Attention:

Re:

Mr. Gordon K. Dicker, ChiefEnvironmental Projects Branch 2Directorate of Licensing

t ~

Dockets 50-275, 50-32

Gentlemen:

Enclosed are 3 signed and 47 conformed copiesof supplemental material describing the Diablo Canyonblowdown treatment syst: em. Three copies of the en-closure are being sent to Mr. J. R. McWherter at OakRidge National Laboratory.

Kindly acknowledge receipt of the abovematerial on the enclosed copy of this letter and re-turn it to me in the enclosed addressed envelope.

Very truly yours,

EnclosuresCC: Mr. J. R. McWherter w/encs.

ll c

++@~4roRV

oleg~1~<moi<

'ij< 7')gILQ Lkk fIQQ

UNITED STATES OF AMERICATOMIC ENERGY COMMISS ION

In the Matter of

PACIFIC GAS AND ELECTRIC COMPANY

(Diablo Canyon Site — Units 1 and 2)

)) Docket No. 50-275)) Docket No. 50-323))

Pacific Gas and Electric Company (PGandE) hereby submits

material supplementing its Comment No. 20 on the Draft Environmental

Statement issued by the AEC Directorate of Licensing for Diablo Canyon,

Units 1 and 2. PGandE comments on the Draft Environmental Statement

were submitted to the Commission on March 1, 1973.

The supplementary material enclosed, which has been ab-

stracted from Chapter ll of the current draft of the Final Safety

Analysis Report, includes a description and drawing of the Blowdown

Treatment System and tables of assumptions and calculated activitylevels which may aid in the Regulatory Staff's evaluation of the

system.

Subscribed in San Francisco, California, this 6th day

of April, 1973.

Respectfully submitted,

PACIFIC GAS AND ELECTRIC COMPANY

FREDERICK T. SEARLSJOHN C. MORRISSEYPHILIP A. CRANE, JR.

PHILIP A. CRANE, JR.By

Philip A. Crane, Jr.

ByJ. D. WORTHINGTON

J. D. WorthingtonSenior Vice President

Subscribed and sworn to before methis 6th day of April, 1973

THEODORA COOKE SEAL)Theodora Cooke, Notary Public inand for the City and County ofSan Francisco, State of CaliforniaMy Commission expires January 28, 1977

~ — - ~

SUPPLEMENTAL MATERIAL'ESCRIBINGDIABLO CANYON

BLOWDOWN TREATMENT SYSTEM

In the operation of any plant under normal and near normal conditions, a wide

variation of operating parameters occurs. Some of these parameters are:amounts of defective fuel cladding, amounts of primary system leakage to the

containment or steam system, boron feed-and-bleed rates, condenser leak

tightness, reactor power, degree of load following, etc. In order to carryout an activity analysis of the plant which covered different combinations ofthese basic operating parameters, two cases were selected: a Design Basis

Case and a 'case identified as "Anticipated Operational Occurrences." For the

case identified as "Anticipated Operational Occurrences," the plant was assumed

operated for a full year at full power with a fuel defect level of 0.2%.

Coincident with this condition, it was assumed that there existed primarysystem leakages of 20 gallons per day to the secondary system, 50 pounds perday to the containment, and 20 gallons per day to the auxiliary building.

Steam Generator Blowdown Treatment

The Steam Generator Blowdown Treatment System for each unit is composed of

'wo processing paths. During operation when the secondary system does not „

contain significant radioactivity, blowdown is directed to the blowdown tank.

During periods when the secondary system contains significant radioactivity,blowdown is diverted to the Blowdown Treatment System.

During plant operation, steam generator water collects suspended and

dissolved solids that are brought in by the feedwater. Water must be blown

down from the steam generators to maintain low solids concentration for effi-cient operation. A complete description of the system and components, includ-

ing sampling criteria, isolation criteria, design codes, inspection and

testing, is included in Section 10.4.6.

During operation with negligible primary to secondary leakage, blowdown flow

will be processed via the steam generator blowdown tank to the circulatingwater discharge structure. The amount of radioactive liquids released during

operation in this mode will be negligible.

During operation when significant radioactivity exists in the secondary sys-

tem, blowdown will be processed through a flash tank, heat exchanger, prefil-ter, and demineralizers. .Blowdown will be reduced in pressure and temperature

within the flash tank and heat exchanger. Three demineralizers with prefilterwill be used in series to reduce the activity and solids concentration in the

blowdown.

The prefilter will remove principally calcium phosphate and magnesium hydrox-

ide precipitation. Following the prefilter, a 60-cubic-foot cation deminer-

alizer will reduce the cationic activity and solids. The blowdown then enters

one of two 150-cubic-foot anion demineralizers where anionic activity (Mo-99,

Te-132 and iodines) and solids are removed.

The third demineralizer, 60 cubic feet cf anion resin, will principallyremove breakthrough anionic solids. The blowdown is then returned to the con-

densate pump suction for reuse (see Figure 11.2-5) .

11.2-6

'I

Vpon exhaustion, the 60-cubic-foot cation and anion demi'neralizers will be

regenerated with sulfuric acid and sodium hydroxide. Run lengths are esti-mated at 3.4 days with no significant main condenser leakage. Regeneration

wastes will be collected in a waste regenerant tank for neutralization and

further processing. After neutralization the wastes will be pumped to the

equipment drain receiver tank and eventually procesed in the waste

concentrator (see Section 11.2.2) .

The two 150-cubic-foot anion demineralizers have an estimated run length of

40 days each before I-131 saturation. These demineralizers will be run past

an anionic breakthough. The decontamination factor for iodine is expected to

be greater than 100 throughout the run. (1)

After one demineralizer has completed a 40 day run, the'econd demineralizer

will be placed into service. The exhausted demineralizer 'will be held for 40

days decay before regeneration. This decay period will allow approximately

97 percent (5 half lives) of the I-131 to decay.

Regenerant wastes will be neutralized, sampled, and analyzed before release

to the circulating water discharge structure.

For the analysis of activity releases for the anticipated operational occur-

rences case, it has been assumed that the main condenser will experience 36

leaks per year of 6 hours each'. During these periods, blowdown will be proc-

essed through the steam generator blowdown tank as in the design basis opera-

tion, since operation of the demineralizers with influent water of high solids

is not practicable. During regeneration of the 60 ft demineralizers, blow-3

down will also be processed via this route. The activity releases during

these periods are included in the overall releases listed for the blowdown

treatment system in Table 11 '-10-

Table 11.2-10 lists the volume and activity released during- anticipatedo'perational occurrences from the turbine building sump.-

11.2-7

BASIC ASSUMPTIONS FOR CORE AND COOLANT

INVENTORIES FOR ANTICIPATED OPERATIONAL'OCCURRENCES CASE

PRIMARY TO SECONDARY LEAK RATE (GPH) ~ 0 ~ 0138"PRIWAKYCMCAAY'.BAKACE'"fb'ONYAINHEViTCGA'N:— de0038PRIMARY COOLANT LEAKAGE TO AUXILLIARY BUILOING (GPH) 0 0138FRACf MA OF FUfL WITH OfFPCT IVE CLA6DING =0 002000VOLUME OF HATER IN PRIMARY SYSTEM (GALLONS) = 94000+

REACTOR CORE THERHAL POHER (HEGAHATTS)DURATION OF PERIOD { HDURSfCAPACITY FACTOR DURING PERIODNUH8 ER OF F IS S IONS P ER OMEGA HATT- S ECONOFRACTION OF FUEL HAVING CLADDING DEFECTS

3568 F 00008760'+850

0'31"5F 1'7

0 '02

TABLE ll.I"5

CORE ACTIVITY INVENTORIES FOR ANTICIPATED OPERATIONAL OCCURRENCES CASE

NUCLIDE PR(IDUCE 0 DECAYED LKGE TO COOLT INVENTORY CUR I ES/MEGAWATT

C R-51MN-54HN-56

0»C0 ~ 0n ~ I

0.0C ~ i)0 ~ u

CD-58 G.O" FE-"59 " '"3»'O'~ Q

0»C'O-60

O»C 0 ~ 0S R-89S R-9C

0 7136E'O9 "0 6334F 09

0 ~ 4388E 07 0 1503E 06SR-O'I " '" "0 1102E 12 0 ~ I ICOE 12SR-92 G»362CE 12 0 ~ 361SC 12Y -9('""'0.5764E '09 (.5722E n9Y -91Y -92IR-95NB-95Mo-99

C ~ 739CE C9C»3021E 120 ~ 728 2E C90 ~ 1225E 10C ~ 1670E 11

(»6738E ') 90 ~ 302OF, 12C ~ 631 6E 09C ~ 1159E I 00 1652E 11

TE='132 '" "O.f'025E 11"'O'I'012E11'S-134

CS-136C S-137

0 ~ 9118E C2r ~ 3546E 07C ~ 4845E C7

C 137BE )2C ~ l388F 07C» 171 9F C6

BA-14C CD 3784E IO C ~ 361SE 10LA-140 0 2788E 11 0.2782C 11CE-i44 3. 1%56E 0 I C.H925C ( 8PR-144 ) ~ 2094F 13 0 ~ 2G94E 13I -131

-1320 ~ 2780 E ICC ~ 32S4E 12

(' 2696E IGCD 3283F 12

KR-83MKR-85KR-85MKR-87KR-88

0 ~ 51-55E 11u ~ 4547E 060 '448E 110 '63OE 12G ~ 2 330 E 12

C ~ 5154E 110 ~ 4664E 05C ~ 5444E I 1

C ~ 3629E 120 ~ 2329E 12

XER. 33 3~ ~ 96SOf I'u» (»96 I IF 10XE-133M 0'»5679F 09 0 ~ 562 7C 9XE-135 C ~ 6314C 11XE 135M 0» 1277E 1 >

X E-138 0 ~ 4669E 13

C»63'l 7E' l('»1277E'13C ~ 4669E 13

I -1.33 0.5875E 11 0.5854E llI -134 0 ~ 1661E 13 C ~ 1661E 13I -I 35 ) 1698E 12 0»1696E 12

O.r,C ~ 0C»Cn,O0 ~ 00 ~ 00 ~ 8095E0 ~ 382 7E0. 1111E0 ~ IO15EG. 6079EC.164 7EO.ISGTEC ~ 103GC0 ~ 1012EC» 2334EC. Sr'89C0 ~ 335C E

G ~ 142SE0.54erEG. 11 54'F..". 1854FC ~ 1016E0» I ') I

bL'»

7029fC 1". 64E9» 1660E0 ~ 1942E0» 1535EG ~ 6474E') ~ 2964E) ~ 161SE0» 3113EC ~ 43 57F.G ~ 8243F.0 2098E0»3925E0 ~ 2241E0 ~ 734 7C

02'1

0303OC"n2O203C305G'4"

-010304030202"0205

06nbC6050406C6C606O5

G606

0 ~ 00 hO."..CD i0 ~ 00»G ~ 144OE 090 ~ 8178F. 07') ~ 1765E 09») 1610E 09O.'8134E 07n ~ 1781C 090»1792E Q90 ~ 1863E 090 ~ 1904E 090 ~ 1871E 09G.'I'315 E 09

'»

7736E 020 ~ 1822E 06O ~ 9C')7E 070 ~ 1914E C90.1926E ('9'0.1248L- 090 ~ 124SE 090» 8839E 080 ~ 1 31 5F. 090 ~ 2032E 09OS 2369E 09

iO»1874E 490 '580E 080 ~ 923 1E 060»3949E.OS0 '594C 080 1063E 09Oi2('32E 09) ~ 5164E 07"»9568C 08DE 546SE 080 ~ 1792E 09

O.C0.00 ~ C

CD 0G»G0 ~ 00 '036E 050 ~ 2292E ".4G ~ 4946E 05C ~ 4512C C50 '280E C40 '993E 050 5023E 050 '220E G50 ~ 5335E 05C ~ 5244E u50 ~ 3686E '05'

~ 2168E-0 I0 ~ 51CBE 020 ~ 2524L'4C ~ 5364E'05

„

C'5398E C50 ~ 3497F. 050 ~ 3497E C50 ~ 2477E 05CD 3686E 050 '696E 05CD 6641E 050 '253E 050»4427E 04G ~ 2587E 03C ~ 1107E 050 '128E C5C ~ 2980E 050.5605'E C'5

CD 1447E 04G ~ 2682E 050 ~ 1532C 05C ~ 5023E C5

TABLE 11. 1-10H

BASIC DATA FOR CORROSION PRODUCT ACTIVITIES

Core Wetted Areas, Effective (in )2

Zirconium

Stainless SteelInconel

Out of Core Wetted Area, Inconel (in )2

Coolant Velocity (ft/sec)Core

Steam Generator

Nominal Base Metal Release Rates (mg/dm -mo)2

Zirconium

Stainless SteelInconel

Coolant Crud Level (ppm)

Permanent Crud Film, Nominal (mg/dm )2

In-Core

Out-of-Core

Transient Crud Layer, Nominal (mg/dm )2

In-Core

Out-of-Core

9.42 x 106

6.C9 x 105

1.01 x 10 6

2.74 x 10

15.0

18.6

0.00.5

1.0

0.1

50

50

50

50

TABLE 11. 1-12

PRIMARY COOLANT ACTIVITIES FOR ANTICIPATED

OPERATIONAL OCCURRENCES

NUCL IDF. CONCENTRhT hCTI VITY(UC/CC I (CUR I ES)

CR-51HN'- 54MN-56CO-58FE-59CO- 60SR-89

C ~ 716CE-03'""589'OE-'03

Oe 2210E" 010 ~ 190GE-GlC ~ 7890E-030 ~ 5970E-030 '843E"03

SR=9'C' "~ i1832E-'04'R-91

SR-92V -9OY -91Y -92

0 '578E-03C ~ 1006E-030 ~ 2238E- 04n. 7489E .030 ~ 1263E-03

ZK-95 "''%8'99E= 03N 8-95 O. 4847E- 03M'0=99 '0

~ '1060E 00TE-132 0 ~ 3789E-OlCS'=134 ' "1420E 00C S-136 0 1088E- 02CS'='13'7 " 0'.44".6E=01BA- I.40 0 ~ 5344E-03

0 ~ 2548E0.2096E0 ~ 7864E0 ~ 676 1E0 '808E0 ~ 2124E

00

01010000

0 '665E 00G ~ 4494E-010. 1743E 000 ~ 1725EC ~ 3772E0 ~ 1348E0 '853ECD 3970E0. 1568E0 1902E

GC020202000200

G ~ 136 7E GO0 ~ 6 5 1 BE-0'2'

~ 9173E-01Go 358CE-C 1

CD 7964E-02

LA-14CC E-144

0 "1801f -030 4858E-04

0.6410E-010 ~ 1729E-0 1

PR-'144 '0'858E-"04I "131 0 ~ 3521E 00

C ~ 172 fE-'010 ~ 1253E 03

I '-'1'F2 ~. 1'Z9TF. Otl "'0~ 4'594E '02

KR-85 0. 1208E OlK%=85~

" ..2~61E FOKR-87 0 1712E 00KR- 88.XE-133

CD 5003E C'0

0 '668E 02Xt-133M O.4264C CGXE-135 0 ~ 1688E 01KE'=1Y5M 0. ZSW5F. —C1XE-138 0 775 1E-01

I "133 0 ~ 5 7'30E CG

I -194 ' 0.7240F.'-61I -135 0 ~ 3005F. COKR'-83K "0;50'95E= C 1

0 '028E'0 '576E0 ~ 1069E

03+203

0 '09GEC ~ 178GEQ ~ 1305EO.151'TE0 '006E0" 9'410t0 2 T58E

0203 '.

C503C3

0. 18l3E 020 ~ 4297 E 030.i0566 53

TABLE 11. 1-14

DEHINERALIZER DECONTAMINATION FACTORS

NUCLIDE- PR I MARY PRIMARYMXD RFA CA T l()N

LF TDOWNMXD BED

LF TDOWN LE TDOWNCATION ANION

M~3CR-51IN-54.

MN-56CO-58~E-59CO-60SR-89SR-90S R-91SR-92y pnY -91Y -92ZR-95N 8-95MO 99TE-132CS-134CS-136CS-13784-140LA-140CE-144PR-144I -131I -132

-133I -134I -135KR-83MKR-85KR-85MKR-87KR-88XE-133X E-133MX E-135

'XE='i35TIXE-138

1 ~ COC1 v ~ GC."

10 ~ OGC1O ~ "001) ~ CCC10 ~ c Crln,nCn10 oOOC10.0001O.CCC10 'OC

1 oCO"I.OGCloCOC

IC.CrO'G

nC'0

10.CCC10.".".O

2 'hO2

AMOCO

'"2'50~10'o DOC~

10 oO<n10 ~ CCO'!O''.CCh"10 ~ COO1VoDI.C10oCOO10.5OC1 0 ~ Cnn

1 oCCC1 0301'.cÃ] n inn1 onOn1.00r.1 ~ COCI ~ OCC'! '"SCZ1 oOCC

1 ~ OOC1CO OOOO

100 OOOO

1GC OOOO

lCC ~ 0"C1".0.0001JC ~ COO100.0IGC.O'OO1Ch ~ OGOICC.OOO

10.0hC1CoOO')10 'nO

1 ~ COC1GO.COO10OoGOC100. CGC10'CO100.COG100oCOG10C ~ GOC100oOOO100» COO100o COC

1 o'30Gl.nOn1 ~ COC

loOCC100 F 0001OC F 00010G OCO10n ~ 0001GG ~ CCO1OO ~ OOCICQ ~ CCO100.000100'OOO1CO

AMOCO

10 ~ OCC10.0001O.COO

1 ~ 0001 ~ 0001 ~ 0001 ~ OOGlo0001 F 3001 F 0001 ~ 0001 OOOO

lo000lo0001 ~ OCG1 oOOO1 ~ 300

I Oh' On+ '1 CC'. C Oi' "' 100. GOO""" '!

~ OCO1OG.nCO

1 ~ CCO1 oOCG

10G.CCG100o GGO100 ~ iOO

1OO F 000loOGn1 ~ COO

1 o0001CC OOOO

1-3C.OCC1C ~ OGO 2 '.OC'0.000" OOOO1C ~ 036 2,COC 10 '"0 1 F 00015.0i.'0 " "2.C'OG " "TO;ODD' ' i.".Odh

100 ~ COO 100 ~ CGG 100o000 1 o0001CCo OOG 100oI'00 "iCO.ChO'" " '

1.0do10n nOn1DO"'Ci 3

100 ~ OGO1CO ~ COO"1OO.CGO

' '00.0Dn" loOOO!.OOn

1 ~ OCO 100 ~ COO 1 ~ 000 100 ~ 000i:.OCO i%%;COd

' 'T.OIiC '"iOO'.05C1 ~ 0001ohh0

100 ~ 000ioc.ccrc

loOCCloCOC

100 F 000100 F 000

1 OOO!.OCO

'O ~ COO1. D'OD

1 ~ COO, 130oOGO

1 oI~CC'" '1:OCO

1 ~ OOO 1 ~ COC lo000 1 ~ )001 ~ aCO loOOC i oOOC

1.000 1

AMOCO

1 F 000 1 F 0001.."CG

" * 1.000 '1.OOOI.nCO 1.CCn l.eoe1.'nGO "

1; GOY ""'.'DOG1 ~ OCO1 oOOO'1.000

1 ~ 0".0 1 ~ CCC 1 ~ OOC 1.000"'1 "3T'M ''.CFC 'Z ~6IT '" ' J" ODC

loOCO 1.COO '1.000 1 ~ 000

TABLE ll.1-22

STEAM SYSTEM OPERATING CONDITIONS ASSUMED FOR ACI'IVITY

ANALYSIS IN ANTICIPATED OPERATIONAL OCCURRENCES CASES

PARAMETER VALUE

Sl EAM FLOW RATE TO CCNDENSFR FP()M S.G, (LBS/HR)FEEDWATER FLOW kATE TO S.G. (L<S/HR)RLOHDOwlv FLOg RATE Fkow S.G. (Lr)S/HR)STEAM VLNT ING FLOW RATE FR()M S.G. (LBS/HR)TOTAL WC I GHT OF STEAM V EN TE)) FRO)', S.G. DUR ING PER IUD-LBHEIGHT OF HATER IN S.G. (LBSlVOLUME DF WATER IN S.G. (FT3) "

DENS ITY OF WATER IN S.G. (LBS/FT3lFRACTION OF PRIMARY TO SECON(rARY LEAKAGE TO THIS S.G.LEAKAGE FLOW RATE TO THIS S.G. (COMPUTED) (GAL/."IN)TOTAL GALLONS OF PRIM COOL ~ LEAKED INTO S.G. IN PER'IOO

STEAM GEN. I

3804300 ~ 03C3818495 ~ OOSC

13710.0 ~ 09 ~ 0

,81500icouL

1683.48 ~ 4ncr

0 ~ 25030 ~ 0034

1813.

STEAM GEN ~ 2

380430". e DOC 03818495oCCCO

13710'oo

815cneoccc35 8'3.

48.4CCCCD 25CCCD 0034

18 13 ~

STEAM GEN o 3

39'34300 ~ OCOO3818495+OOOO

13710.0 ~ C

0 ~ 081500+OCOC

1683 ~

48 4COCG ~ 2500CD CO34

18 13

STEAM GEM ~

38G4333 ~ 00033818495 F 0000

13710+'~ 0

0 ~ 0SLSOV COOO

1683 ~

48.40000+25000+0034

1813

'OTAL

STCAM FLOW RATE TO CONDENSER (LBS/HR)TOTAL CONDENSATE FLOW RATE FROM CONDENSER (LBS/HR)

15217200+ COOC CC

15276482 ''30CCC

HEIGHT OF WATER IN CONDENSER (LBS)VOLUMC OF WATER IN CONDENSER (FT3)DENSITY OF WATER IN CON()ENSER (LBS/F T3)

20COOoooooCOG3205 ~

62.39

TOTAL PRIMARY TO SCCONOARY LEAK RATE (GALLONS/MINUTE.)HATER LEAKAGE RATE FROM SECONDARY SYSTEM (GAL/MIN)STEAM LEAKAGE E RATE FROM SECONDARY SYSTEM (LBS/HR)FLOW RATE OF HATER TO BLOWO()WN CLEANUP SYSTEM (LBS/HR)CAPACITY FACTOR 07 KQQI)OQN CCEANJP SVSTEH

CD G1380C5 ~ COGGGO

1940 '8394m

b'95'REE

VOLUME (JF VAPOR SPACE IN CONDENSER (CUBIC FEET)TRUE VOLUME VENT RATE,OF GASES FROM VAPOR SPACE (CFM)

IOOOCC OOOO275eoooo

TABLE ll.1-23

SECONDARY SYSTEM PARTITION PACTORS ASSUMED

POR ANTICIPATED OPERATIONAL OCCURRENCES CASE

NUCl. ICE ST ~ GEN o 1 ST eGEN ~ 2 ST ~ GEN ~ 3 ST ~ GEN ~

CR-51HNW4H~6CO-58FE 59COMOSR-89SR~90SR=91SR .92Y -90Y -91Y =92ZR-95N8-95HO-99TE-132CS-134CY-i36CS-137hE=i4OLA-140CE-144PR-144I -131I- -132I -133I -134I -135KR-83HKR-85KR-85HKR-87KR-88XE-133XE-133HXE-135XE-135HXE-138

Ooo0+0

~ I I0 ~ C C ~ 0e.e 0 0

0 ~ 0CanO.c"

0 ~ 0 CD 0 C AC

0 ~ 0 0 ~ 0 GeOG ~ C 0 ~ 0 0 ~ 0C ~ '3 G ~ 0 GooCeo 0 ~ 0 GooO.C '=

O.O 6. 00 ~ C 0 ~ 0 CooCoO 0+G 0 ~ 0CD 0 C ~ 0 0 ~ 0

v+00 ~ 000 ~ 0C ~ C0.00 ~ 0O;00 ~ 0

"0+6 0 ~ 0 OoC '""Ooo'GAG 0 ~ 0 0 ~ C

0 ~ 0 G.' 0 ~ 0 0 ~ C

C ~ 0 0.0 0 ~ 0 Oeo

o." c.n o.o0+0 0 ~ 0 CeoCC GC OOO.ieoc O.iOGn - C.IGCO0 '0CC 0 1OCG 0 100

C ~ 0Geo0 ~ 0G 10GCOelOCC

0 ~ 1 CC OelGOC Oolooo OelOCOC 1CCC 0 1000 0 10CC 0 1CCG0 'CCG CD 1000 C.looo1 OOCC 1 OCOC 1 0000loGCCC li0000 leODGC1 ~ CCCG 1 ~ OCOO 1 ~ OOGG

O. 1COG1 ~ CCOO1 F 0000I ~ OGCQ

1 ~ GCGC 1 F 0000 1 ~ COOC 1 F 0000loOGOG 1 ~ OCOG I ~ GOCC1 OGCG 1 0000 1 .,GCOC

1 CCOC 1 000" 1 COCOleCCCC 1 F 0000 1 ~ OCOCloonGC 1 F 0000 loOGOC1, OGGC 1.0GOO 1 OCGO

leCOGC1~00001 ~ COCGI~GCOO1 OGGG1 ~ OCGO

Ooo Ceo" " 'Oeo bio

0 ~ 0 0.0 0 ~ 0 Goo*'0 0 O

C'"0

G 0 C 0 0.0 0 ~ 0~.7l O.O

TABLE 11.1«25

EQUILIBRIUM ACTIVITIES AND CONCENTRATIONS IN EAGI STEAM GENERATOR

FOR ANTICIPATED OPERATIONAL OCCuRRENCES CASE

NUCLIOE ACT IVITY(CuRIES)

CONC ENTRAT IONt UC/CC)

HN-54HN-56,CO-58F E-59CO-60S R-89SR-90SR-91SR-92

=Y -90Y -91Y -92ZR-95NB-95HO-99TE-132CS-134CS-136CS-1378A-140LA-140CE-,144P R-144I -131I -132

-133I -134I -135

0 '309E-050 ~ 2737E-050 o 395 3E-040 ~ 881 4E 040 a 365 5E 05Oo2776E-050.1781E-050 '518E-C70 '426F-060 1855E-06Oe9721E 070.3423E-050 ~ 2741E-060 ~ 2272E-050 ~ 2243E-0 5Oo4648E-030'o 1673E 030 '594E-03Oo4986E 050 ~ 20 47E-0 30 ~ 245 2E-050 ~ 7591E-060 a 2257E 060 ~ 1495E 070 o 1534E 02Oe 2097E 030 ~ 2117 E-02Oo5538E-040 '243E-03

0 '940E-070 ~ 5741E-070 e 8291E 06Oo 18 tBE 050 e 7665E 070 ~ 5821E" 070 o 3735E-070 ~ 1786E-080 ~ 1767E-070 ~ 3889E-OBG ~ 2039E-OB0 ~ 71 79E 070 e 5749E 080 a t765E 070 ~ 4704E-070 ~ 9747E-050 '509E-05Oo 1383E-040 e 1046E 060 o 42 92E 050 ~ 5143E-070 ~ 1592E-070 ~ 4734E-080 ~ 3136E-090 ~ 3218E-04Oe t398E 050 ~ 4440E-040 ~ 1161E-050 ~ 1729E-04

o

TABLE 11. 1-27

EQUILIBRIUH ACTIVITIES AND CONCENTRATIONS IN THE CONDENSER

IOR ANTICIPATED 01'ERATIONAL DACES- CASE

4UCL IDE ACT IVITY CONC ENTRAT ION"IVOR tfS) " 'Iuc/CC)

CR-51 0oC Q ~ Q

RN-54 0 C ~ Q

HN-56 0 o0 Oo Q

CO-58"

Oo0= 'ob =

F E-59C 0-60S R-89

CoG 0 '0 ' 0 ~ 00 0 Oo0

SR 9b C ~ 0"

OoOSR91 G ~ 0 OoQSR92" „00 '

Q

Y -9Q 0.0 OoQY 91 ';.0 '

Q ~ 0Y -92 QoG Oob?R95 "

QiG'

O+0N8 95%0 99I'-132CS-134CS 136CS-137"8A-140

GoO 0 ~ Q

0 ~ Q 0 ~ Q

Go0 OoQ"'i.O " "' * 0.0

CD 0 Co0A A

0 o0 VoV0oO Oo0

LA-140 0 ~ C . 0 ~ UCE-144 0 oO 0 '

~ ~ ~ - ~

PR 144 OoC QoOI -131I -132I -133I -134I -135

0 ~ 375QE-G3 Oo 4131E-05G ~ 5IC6E-C4 Go5626E-060 ~ 5172E-C3 Co5699E-05C ~ 1340E-04 1476E-060 ~ 2012E-C3 Co2217E-05

CONDENSER VAPOR SPACE

NUCLIDE INVENTORY CONCENTRATIONICURIESI IUC/CC)

KR-83 HKR-85XR"85HKR-87KR-88XE-133XE 133HXE-135XE-135HXE 138

0 '97GE-C30 '963E-Gl0 '876E-020 '547E-030 '775E-020 '639E CO0 '473E-020 '205E-010 '928E-04Oo7738E-04

Go1049E-060 '934E-050 ~ 1016E-05CD 2665E-060 '333E-05Oo2345E-03Go2639E-050 '785E-05Ool034E-07Gi2733E-07

I ~

~ ~

TABLE 11.2-10

ESTIMATED ANNUAL ACTIVITY RELEASE

POR ANTICIPATED OPERATIONAL OCCURRENCE CASE

UNITS, 1 AND 2 (SEE PICUK 11.2-3 AND 11.2-5)

Isotope

RadiateSystem A»

(ucurie/yr)

Blovdown TankEffluent(uCurie/yr)+

BloMdoun SystemRegenerationMastes (uCurie/yr)*

TurbineBuildin8 Sump(uCur les/yr)*

Too Unit

Totalize

(Curies/yr)

SR»89SR-90SR-91SR 92Y-90Y-91Y-92IR 9SNR-9580-99

ZE-132CS-135CS" 137BA 140LA 140CE-144PR-144

1 1311-1321-1331 1341-13S

CS-134CR-51HN 54RN-56Co-59FE-59Co-6C

Total

'l ~ 627E 92314F. n 1

0 ~ 218E 000,239 E-3Sne43?F 0>1 ~ 239F. 'l4ne 1'59E-nlOe809F 9?0 e823F 'l2'le567E 140 '245 049 ~ 996E 03-ne877E 059 ~ 752E 92Oe644E 'lrOe 8?7E 01n ~ 829E 91ne?16E 150 ~ 733E 04-0 ~ 'S14E 959 e 6 46F.-1 3n.228E 930 '79E 060 284E 020 ~ 256E 92-n.685F.-14oe801E 030 ~ 325E 029 261E 92

'5'52E 030 ~ 264E 92Oe?63E 03Oes85E 0?0 ~ 301E 02Oe 106E 040 '66E 92oe704E 03Oe695E 030 '44E 060 ~ 519E OS0 '54E 04Oe633E OSOe757F, 030 ~ 236E 93Oe700E Or9e476E nlOe441E 96ne604F'soe613E 96Oe.1608.05Oe238E 060 ~ 204E 060 ~ 102E 040 ~ 847F0 ~ 12'SE OS0 ~ 273E 05Oe 113E 'l4Oe857E 03

n.oOeoo.o'l~ 9Oeooeon.OOe1OeoOe 150E 02Oe215E 02n.o1 ~ 901 eo0 ~ nn.o0 720E 0"9 90 ~ 614E-98Oeo0 ~ 500FrBR0 ~ 9O.nO.o

O.nn.n1 ~ 0

O.O0

Oeooeo0 ~ 0n.O0 nOeooeo0 0Oeo0 ~ 0Oeo0 00 ~ 00 ~ 0neo0 ~ 497E0 '54FO'61E0 ~ 145Ene 218EOenOeoOe 'ln.oneoOeoo.n

1514'l5

05

'le117F-n?SSM-94

O.S?7e-n~'l l7F

0 ltD< 0 lh 4cl C 1?

173+-'l3ne 1 a9F 17n ~ 147 F-nr0 ?94F 19nel n64 00net nAF Or-'l ?l 4F 09n.lA9e-nrO.si~F-own lese-03

17Ao-94

l 1%4+ on1.134'l344+-11Sloe hn

0 ARRF 01n.?nsc-n7h 17?F hr0 rS')F-nln.SS4e-OCn er Xne-gr'l 174 F-'lr0.'E<i

* Por One Unit~o Units

TABLE 11.3-3

GASEOUS WASTE SYSTEMS RELEASE: ANTICIPATED OPERATIONAL OCCURRENCES

(CURIES)

NUCLIDE CAS DECAY

VBiTILATIQN VENTILATION OFF-GAS

CONTAIRIENT AUXILIARYBUILDING CONDENSER

VENTING LEAKAGE

BLQWDQWN TANK MISC STEAM MISC SECONDARY

WATER LEAKAGE

TOTAL

RELEASE

KR-83MKR-85KR-85MKR-87KR-88X E-133X E-133MXE-135X E-135MX E-138

0 ~ 00 ~ 284E 040+0e.eC ~ 0c o4e6E 030 '37E-02Qoe0 ~ C

Coe

OoOQi429E 020 ~ 0O~COoO0 '84E 020 ~ 203E-100 ~ 0OoOOoO

0 ~ 140E Ol0+284E 020 ~ 812E 010+470E 010 ~ 137E 020 ~ 991E 030 116E 020 '63E 020 '26E 000 '13E Ol

0 '29E 000 '84E 020 ~ 416E Ol0 '09E 01Qe546E 010 '59E 03'''IOBE 02Qi318E 02

'

~ 423E-010 ~ 112E 00

0+00 'OoOOoOOoO0 ~ 0OoOOeO0 'Oio

0 & 178E-030 '62E-020 ~ 104E-QZOi599E-0300 175E-02Or 126E 00Oel48E-CZOi59CE-020%926E-04Oa 27IE-03

0 ~ 00 ~ 0OoO0 AC

0 ~ 00 AC

OeCOwe0+00 '

0 ~ 183E0 '94E0 ~ 123E0 ~ 579E00192E0 '36E0 '24EOo 781EOo769E

.0 '24E

010402Ol0204 ~QZ0001

I -131I -132I -133

-135

0+00 'Qoe000Oo0

0 ~ 57CE-08O'0'

~ 0

0+0

0 o 6 33F.-030 ~ 731E-O3CD 163F-03r. 1998-040.825E-04

0 ~ 24~ c Oln~ o Qnf'70 ~ 337'-Ql0 nOIE-Oa0 ~ l>2F-0 I

C ~ Be~i-CI Q..~l lr 01n. 7,0r"-.-n 7 no 4 > '4 F ~ l70 'elr-Al C 4~OF-Al

C ~ I 07~ 000 ISQr.-QIC 147F 00

n.4QQF-O~555K;-06

C ~ 5'54L-C5l F >8-CZ 0 ~ I l 5i-07 0 ~ 14 7F-06 0 39cF QZ

n.~>~F-rl 0.169E-nl 0.217F-C5 0 ~77F-01

~, ~

VENT TO ATMOSPHERE

STEAMGENERATORBLOWDOWN

TANK

TURBINE-GENERATOR

BUILDING SUMPTO CIRCULATING WATERDISCHARGE STRUCTURE L EGEND

PROCESS FLOW PATH

SECONDARY FLOTI PATH

RADIATIONMONITOR

RE

TO CIRCULATING WATER

DISCHARGE STRUCTURE

VESSEL DRAIN TO EQUIPMENTDRAIN RECEIVER TANK

VENT TO MAIN CONDENSER

PREFILTER

WASTEREGENERANT

TANK

TO CIRCULATING WATERDISCHARGE STRUCTURE

TO EQUIPMENT DRAINRECE IVER TANK

TO CONDENSATE PUMPSUCTION

FROM STEAMGENERATORS

FLASHTANK

HEATEXCHANGER

60 FT

CATIONDEMIN,

l50 FT(2)

ANI0 NDEMIN.

60 FT3

ANIONDEMIN,

RESIN TRAP

I. SEE TABLE I I.2 -l7 FOR ANNUALFLOWS AND ACTIVITY~

2, STEAM K IS EQUIVALENT TO Sl'REAM60A AND 60B ON FIGURE I I.2- 3.

UNITS I AND 2DIABLO CANYON SITE

FIGURE )$ .2-5STEAM GENERATOR BLOWDOWN

TREATMENT SYSTEM FLOW DIAGRAMICIPATED OPERATIONAL OCCURRENCES

4 0' ~