ML20082K946

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Semiannual Radioactive Effluent Release Rept - 1st & 2nd Quarters of 1991
ML20082K946
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/30/1991
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20082K932 List:
References
NUDOCS 9109030124
Download: ML20082K946 (18)
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SIM1ANPUAL RADICALTIVE EFFWDIP IM FASE REIOld' lst ard 2rd Quarters of 1991 Facility: Shoreham Nuclear Power Station, Unit 1 Licensee: Ioryy Island Lighting Ccupany, Inc.

TABLE OF ColmWPS Section Page Intrcxluction 1 A. Suppleental Informtion .1 B. Gaseo.18 Effluenta 4 C. Liquid Effluents 8 D. Solid Waste 11 E. Radiological Iquet on Man (Not Regaired )

F. Meteorological Data (Not Required )

G. OD04 Fevisions, REMP Incation Changes 15 and tbjor Changes to Radioactive Waste Treatrrnt Systems H. Miscellaneous Special Reports 16 3 Section E ard Section F are not required by Technical Specification to be included in this report. These sections will appear in the next tvport, due 60 days after January 1,1992, and will encctnpass al.'. of Note: During the period covered by this Report, SNPS was operating under license NPF-82 through Annndmnt 6. Arrendmnt 7, which becano effective on July 20, 1991, changed Appendix A, 'Ibchnical Specification significantly, including the numbering of nany sections. In addition, the numbering of same sections of the O(D1 changed concurrently. All Technical Specification and OIDI section ntrrixirs used in this Pqnrt refer te NPF-82 through Amendnunt 6 and OD04 Revision 17.

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INI'itTRETICN

'1his Scmiannual Padioactive Effluent Polease PcInrt, suhttittai in accordance with Technical Specification 6.9.1.7, Offsite Dose Calculation Manual (OCG) 6.9.1.7 and 6.15.1, and Pmeess Control Progr<,m (PCP) 9.4, covers the period fran January 1,1991 through June 30, 1991. By contractual actreenent with New York State, the long Island Lighting Ccnpany (LIICO) will transfer the Shoreham nuclear Pcuer Station to the Tong Island Power Authority. LIICO cannot operate the plant in the interim. In order to ready the plant for deccanissioning and to protect plant systems, the fuel was transferred to the spent fuel pool in August 1989, and plant layup activities began. Prior to defueling, the plant was in a cold shutdown condition for altrast two years.

A. SUPPLD~DTI'AL I?FOIMTICN

1. Thx ulatory Limits Shoreham's effluent mgulatory lirtits are detincd in Facility Coorating License NPF-82, Shoreham Nuclear Pcxer Station, Ippendix A, Technical Specifications.

a) Limits for gr.neous etrluents and noble gases are covered b/

Technical Specification 6.8.4 and OCG Controls 3.11.2.1 and 3.11.2.2.

b&c) Iodines and particulates with half-lives greater Olan 8 days in gaceous erfluents are addressed in Technical Specification 6.8.4 and ODCM Control 3.11.2.3.

d) Liquid effluent limits are described in Technical Specification 6.8.4 and ODLM Controls 3.11.1.1 and 3.11.1.2.

e) In addition, with Shoreham's sampling and analysis prcxyram the rollcuing average mLnimum detectable activities (MDA's) wre achieved for the first and second quarters in l'391. These MDA's are less than the required lcwer limits of detection (12D's):

Liquid:

Ce-141 3.65 E-8 uCi/ml Co-58 2.87 E-8 uCi/ml Cc-137 3.60 E-S uCi/ml Mn-54 3.67 E-8 uCi/ml Mo-99 1.79 E-8 uCi/ml Zn-65 7.21. E-8 uCi/ml

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Caseous:

Cs-137 5.24 E-14 uCi/cc I-131 7.63 E-14 uCi/cc I-333 7.16 E-13 uC1/cc Mn-54 4.88 E-14 uC1/cc Xe-133 1.J4 E-08 uci/cc Zn-65 1.23 E-13 uCi/cc

2. Maximum Permissible Concentrations a-d) K1xinum permissible liquid effluent concentrations (MPC's) are those specitied in 10 CPR 20, Appendix B, Table II, Coltmn 2. If an isotope is listed with values for SOIABLE and INSCJUIU states, the more conservative value is utilized. For gaseous effluents, MPC's were not used. Direct calculations of dose were utilized to satisfy the dose rate limitations of Technical Spncification 6.8.4 and ODO4 Control 3.11.2.1.
3. Average Ener g No isotopes above minimum detectable activities were unasured in gaseous effluents. Therefore, there is no reportable average energy Ior this tine period.
4. Measurenents and Approxinntions of Total Radioactivity a-d) Sartples were collected in the nunner and with the frcquency prrmribed in Technical Specifications Surveillance Requirennnt 6.8.4 and ODCM Contruls 4.11.1.1.1 and 4.11.2.1.2. Samples were analyzed in accordance with ODCM Controls Tables 4.11.1.1.1-1 and 4.11.2.1.2-1 regarding both type of analysis and level of sensitivity. Most samples were analyzed by ganun spectroscopy with a Germanium detector. A liquid scintillation counter was used to analyze for 11-3 and Fe-55 while Sr-89, -90 analyses were done by proportional counter. Samples analyzed for iron and *
strontium underwent a chemical separation prior to counting.

Approved sample collection and analysis procedures were folicwx1 l Analytical results are examined to ensure that the minimum i sensitivity levels required by ODCM lower limits of detection (LID's) have becm met. Any identifiable peaks above backgrcxmd are quantitied.

l The netheds above were used for baten releases. The sane methods were used for continuous discharges, but were canbinnd with gross activity nuasurements on process streams and total ficw for these streams.

No estirrote of percent total error is provided in Table 1A and Table 2A because all values for gaseous and liquid effluents were determined to be less than required LLD's.

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5. Batch Paleases a) Liquid 1s10uarter 2nd Quarter
1. Ntminr of batches 31 20
2. Totn3. Tine (minutes) 4,387 3,176
3. Maximim Tinn (minutes) 198 270
4. Minimim Tinn (mirutes) 01 78
5. Average Tino (minutes) 142 159
6. 'Jbtal Voltme Dischartyxl (gal) 5.20 E+5 3.36 E+5
7. Total Dilution Water (gal) 3.77 E+7 1.74 E+8
8. Average Flcw (ggn) 8.71 E+3 5.49 E+4 (with dilution) b) Gaseous - tbne
6. Abnormal neleases a) Liquid - Ibne b) Gase<xis - tbne I

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9 e SIMINEAL IWLtuACTIVE DTILTNT IU11'ASE IUTOIC B - GASIWS DYIlffR15 1st and 2nd Quarters of 1991 All sanples of gasecus effluents were analyzed and detennined to be at or bolcw mininum detectable activities ROA's) for all radionuclides listed in Shoreham's OD01. 'Ihese MDA's were below the lcwer lunits of detection required in CYX24 Controls Table 4.11.2.1.2-1. In addition, no other radionuclides wre identified . Therefore, no entrien were rode in Tables 1A, la or 1C that folicw.

Ccxqx> site sanple results 1or the first and second quarters of this reporting pericd are all at or below 10A's.

.. y TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1991.

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quener Quaner Est Total .

I 2 E rror. %

4 A. fision & activation gases

' 1. Tota 1 release Cl . E . E . E

2. Averag~e release rate for penod pCi/sec . E . E-

.3. Percent of Technical specification tirnit  % . E .

E

<. B. lodines

1. Total iodine.131 Ci .

__ _ E . E . E

2. Aserage release rate for period pCi/sec . E . E
3. Percent of techrucal specification hrnit  % . E . E C. Particulates
1. Particulates with half. lives >8 days Ci . E . E , E
2. Average release rate for penod pCi/see . E . E
3. Percent of tecTtmeal specification hrrut  % . E . E
4. Gross alpha radioactivity .Ci . E . E

- D. Tritium r 1. Total release Ci . E . E . E

2. Average release rate for penod pCi/sce . E . E
3. Percent of technical specification limit  % .

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TABLE 1B 1991 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE 8 ATCH MODE UrWt Overter 2 Quarter 3 Queriet 2 Nucides Reisased Owener)

1. Fission gases 4'

Ci E E E E krypton 85 . . . .

k rypton.85m Ci . E . E . E T~'T Ci E E E E krypton.87 . . . .

E E E k rypton.88 _ Ci . E . .

E-E xenon.133 Ci . E . E . .

Ci E E E . E xen6n.135 . . .

Ci E- E E .

E_

xenon.135m . . .

Ci E E E . E

, xenon.138 . .

Ci E E E E Others (specify) . . . .

E E I Ci . E . E .

E E __

Ci . E i . E . .

Ci E E E E unidentiGed . . .

Total for period Ci . E . E . E . E

2. lodines Ci E E E E iodinc.131 . . . .

Ci E E E E iodine 133 . . . .

Ci E E E E iodine 135 . . . .

Ci E E E E

' Total for period . . . .

3. Particulates Ci E E E E strontium.89 . . ,

4 Ci E E E E strontium.90 . . , .

Ci E E- E . E cesium 134 . , .

Ci E E E . E cesium 137 . . .

Ci E E E . E barium. lanthanum.140 . . .

Ci E E E E Chhersjsyecify) . . .

Ci . E . E . E , E

~~ " E Ci . E . E . E .

C E E E E-i unidentined . . . .

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. 1 TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1991 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE SATCH MODE Nuciides Releawd Unit Onnw y Qwner2 O d"*' l 0 "". ."_ 2

l. Fision pses krypton.85 Cl . E .

E_ . E . E Erypton.s3 m Ci . E . E . E . E

~~

krypton 47 0 . E . E . E . E krypton 48 Ci . 78 . E . E . E xenon.133 Ci . E . E . E . E xenon.135 Ci . E . E . E . E xenon.135m Ci . E . E E . E xe non.138 Ci . E . E . E . E Others (specify) O . E . E . E , E Ci . E- . E . E . E Ci ~ . E . E . E . E

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unidentined Ci . E . T . E . E Total for penod Cl . E . E . E ,

E1

2. Iodines iodine.131 Ci . E . E . E . E iodine.133 Ci . E . E . E . E iodine 135 Ci . E . E . E ,

__ _E Total for penod Ci . E . E . E . E

3. Particulates strontium 49 Ci . E . E . E . E st rontium.90 Ci . E . E . E . E cesium.134 Ci . E . E . E . E cesium.137 Ci . E . E . E , E barium lanthanym.140 Ci . E , E . E . E Others (specify) Ci . E . E . E , E Ci . E . E . E . E Ci . E , E . E . E unidentined Ci . E . E . E . E w-

'A lb SDtIANNUAL DADIGACTIVC IT1' IUD (P IWJEASE ItFJOfff C - LI7JID TITIITNIS 1st and 2nd Otnrters of 1991

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~ All samples of liquid effluents were analyzed and determined to be at or beim j minimum detectable activities R1DA's) for all radionuclides listed in the ODr}i. -

These im's were beim the LLD's mguired in CtXN Controls Table 4.11.1.1.1-1 In addition, no other radionuclides wre identifux1, 'Ihcrofore, no entries were a nude in Tables 2A and 2B that follw.

Cmposite smple result.s for the 1st and 2nd quarters or this reporting period are all at or beim MDA's.

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TABLE 2A

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- EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 199:

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Ouenot Quanet E st. Total 1 2 E rroe. s A. Finien and actintion producta

1. Total releau (not including tntium, gases, alpha) Ci . E . E . E
2. Average diluted concentration

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dunna period mci /ml . E . E

3. Percent of appbcable limit  % . E . E B. Tritium
1. Total release Ci . E . E . E l
2. Average diluted concentration during penod pCi/ml . E . E
3. Percent of appbcable limit  % . E . E
  • I C. Dissolwd and entrained sanes
1. Total release C . E . E . E l 2 Average dduted conczntration dunng period pCi/ml . E . *E _
3. Percent of applicable limit  % . E . E-D. Gross alphs radioactivity El

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l 1. Total release l Ci l .

E-l . . E l E. Volume of waste released (prior to dilution) liters . E . E _. E

F. Volume of dilution water used during period - liters . E . E . E 1

v p T ABLE 28 EFFLUENT AND WASTE DIGPOSAL SEMIANNUAL REPORT 199i LIQUID EFFLUENTS CONTINUOUS MODE S ATCH MODE suci.on sei..wo unit ow.,ie,i oven.' 2 u u' '1 0"'" 2 E E E strontiume9 Ci . E .

E E E strontium.90 Ci . E . . .

E E E E cesium.134 Ci . . . .

E E E iesium 137 Ci . E .

Ci E E , E . E iodine 131 .

Ci E E E . E cobalt.58,, .

-E E E E cobalt.60 Ci .

E E . E iron 59 Ci . E . .

Ci E . E _3 E iinc!65 .

E E E . E maganese.54 Ci . . .

Ca' E . E E . E cluomium 51 E E E E

, zirconium. niobium.95 Ci . .

Ci E E E . E rnolybdenum.99 . . .

Ci E E E . E technetium 99m .

Ci E E E . E barium.lant hanum.140 cen um.141 Ci . E . E , E .

E_

Ot her (specify) C . E , E . E ,

E_

Ci . E E . E . E Ci . E , E . E . E Ci . E- . E . E . E Ci . E - E . E . E Ci . E . E , E , E

_ _ unidentified Ci E E E E Total for period (above)

Ci E E E . E xenon.133 . , .

Ci E E E . E xenon.135 , .

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SIMINMJAL PADIQrCTTE EFFIDENT PJ2E16E RE ORT D - SOLID H GTE 1st and 2nd Quarte.rs of 1991 There was no shi} vent of solid waste of any kind oftsite during the first and the second cpuirters of 1991. All entries in Table 3 are therefore zeros.

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  • HSGUIA70RY GUIDE 1.21 M70TG' * * *
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EOLID WNm: E!!IPPID 01131'IT: IDH DIf40 SAL I

    • DURDIG PDtICO PIOt41/1/91 t.o 6/30/91*
  • I 1033: tm(17Et Posins, riltera, & D/aporator Ibttcm I i

1# S13 _ ASS ,CU111C Ml?D3tS CUldIM  % 13tIOR (CI)  !

A 0 0.0 ft/A I

    • !$7.IMND:S OF !%JOR fAC.IDPS IlY 1@SDs CLASS & TmtlW4 **  !

h%STE S'I107N: Desinn, Filters & INaporatcr tbttcm with .0t CtrIuy {

_ WASTE CI168 _gn.iDD AnUbiWE CUfu tS I

A Co-60 0% 0.0  !

Fe Os 0.0 -

Cr-51 0% 0.0 Co-50 Ot 0.0 Zn-65 0% 0.0 t t

Ag-110m 05 0.0 IM-241 0% 0.0

  • 11- 3 0% 0.0 i Mn-54 0% 0.0 t Fe-59 Os 0.0 Co-144 C.t 0.u Ni-63 01 0.0 i Cs-137 0%- 0.0  :

Nb-95 0% 0.0 Sb-124 0% 0.0 Co-57 Ot 0.0 Co-141 01, 0.0  :

Ni-59 0% 0.0  ;

Sr-90 0% 0.0 lb-94 0% 0.0  :

C 0% 0.u i On-242 '

0% 0.0 1-129 0% 0.0

'Ib-99 01, 0.0-r l

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- - i L 'm, . , - , . ,_....i,_...,-.A-, ,- - - , - , , . - ~ . . _ . , . . - - . . _ - . _ , . - . . . , - . . -

. . - , - - . , . . _ _ . - - , . . . . - - . . ..m,-..'----.,,-

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i TAluE .s (Cont'd)

      • Tunfl1/IORY rRhDE 1.21 RETOIrr * **
  • SOIJD h'MME SilIPPID OPPSITS TOR DISITN4
    • DURDKi PERICO l'IYYi 1/1/91 to 6/30/91**

h7CIE S'DU#1: DIY Active Wanto WASTE CIASS CUllIC MIM TS CURIp1  % ERIOH (CI)

A 0 0.0 N/A

    • BffrImTIT, OF WJOR !AKLIDES IW h7sIE CIASS 1. STRl741 **

h7CIE STPJ#1: Dry Active Wanto with .0% CtJIOIT h7&rE CIASS , IATCLIDE NENWK'E CURIES A Mn-54 Ot 0,0 Co-60 Ut 0.0 Fe-55 0% 0,0 Cr-51 Ot 0,0 Co-58 Ot 0.0 Zn-65 ut 0.0 Ag-110M 0% 0.0 re-59 Os 0,0 Ni-63 01 0.0

!!-3 0% 0,0 Sb-124 0% 0,0 Co-57 0% 0.0 Zr*95 0% 0.0 Cs-137 0% 0,0 Ni-59 On 0.0 Cc-141 0% 0.0 C-14 0% 0,0 Am-241 Os 0.0 Sr-90 0% 0.0 '

th-94 0% 0,0 Cc-144 0% 0.0 o Cin-242 0% 0,0 Pu-241 0% 0,0 I-129 0% 0.0

'IC-99 Ot 0.0

i Tail 1I 3 (Cctit'd) I f

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  • JUIRf!WM0/ GUIDE 1.2* IU'PollT ** *
  • f 001JD h%S'It UllIPITD OFPSI'IE 1011 DISKliAL [

" 1ATRI1XI PI3tICO ITKli 1/1/91 to 6/30/91**

WAmt m1UW4: Irradiatal Ctqomnto i WAR'IE CfN;S CimtC Mm13ts ytf13 1. rJUOlt (CIL A 0 0.0 N/A j f

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    • IETIMATIN OF MAJOR 1AX'!JDES 13Y WAmt CINIS & STitrW4 ** j NAS'IE M1TR4 Irradiatol Ccqr>nent a with .0% CmO!1 .

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_ WASTC CIAMS !AICfJDE .Allt NI W X T.

CtmtiB A FE-55 Ot 0.0 Co40 0% 0.0  !

N1.-63 Dt 0.0 i Mn-54 us 0.0 (

Ni-59 Ot 0.0  ;

C 0% 0.0 '

Ni>-94 0% 0.0 N-241 ut 0.0  ;

N239/40 0% 0.0 ,

N-238 0% 0.0  :

Te-99 0% 0.0 f

!Jp-237 0% 0.0 i Cm-242 0% 0. 0 - -l Im-241~ 0t 0.0- i Cr-51 0% 0.0  ;

On243/44 ~ Ot 0.0 i N-242 0% 0.0

/vn-243 0% 0.0 l Co-137 0% 0.0 ,

I-129 0% 0.0 [

Sr-90 0%- 0.0 i 11- 3 Ot 0.0 j

    • DOLID WASTE DISPOSITION StM1ARY** f

' fvTMBER OP S!!IIM2TI'S MODE OP 'ITtANSIORTATION DIETINATION O N/A Tiarnwell  !

O N/A Richiarx1 1 0 N/A lbat.ty i 0 N/A Other t  !

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SIMINUJAL PADitVCPIVE ITrHWT ,

IU3J%SE JU'P0fft G - Mai F1VISIG1S, RlW Il1%TIQ1 QWKIDD NO 14MOR OWJCPS '1D HADIOTCTIVE h7&rn TIUWIWNr SYST!M9 A. Changes to the 004:

According to Technical Specification 6.14.c and OD04 Control 6.9.1.7, changes to the Offsite Dono Calculation 14anual (CD04) Imde during the reporting pericd shall be nulxnittext with ex, Semiannual ibdioactive Effluent releano Pciert in Ole form of a cr.stplete copy of the entire CtO4, with changes identificd irf rerkirga in the rurgin of On pages that contain t1xn.

There was a single revision to the dui, ihn.17, that was rnvie during this t rerorting pericd.

In this 2wision, c!wnes were made to the 0004 to reficiet the inotopic inventory and the radiolcgical offluent rmnitoring rcquirtents apprrprinto to the plant's non qwrating, defueled condition with fuel stored in the spent fuel pool.

Revision 17 to the COQ 4 was apptwod by the Devirv of Operations Ccmnittre on May 30, 1991 and became offective on June 24, 1991. A copy of this revision ic attached to this S(ni 'nnaal Eifluent Ibicarc ReIrit. >

13 JU74P Iocation Changes:

Action Stat <rrents c of 0034 Control 3.12.1 and a and b of Gm Control 3.12.2 rtquire IU2tP location changes to be reported in the S(miannual ibdioactive Effluent Helease Pnport.

- There were no such PJI4P location charges during this reportirn pericA.

C. Major Owiges to Radicactive Waste Treatnent Systemst Dolid Waste process Control Program (PCP) 9.3.1 and 9.4.4 state that the S(niannual IMdioactive Effluent Polense Report shall include major changes to radioactive waste treat 2 rent syntams.

There were no rm3cr changes to radioactive waste treatnnnt systens during this reporting period.

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81141Nitant,1%DINCTIVD ITlH!rNT JUM1J E !! 10 7 0lff 11 - M!rclini1XX1S SPDCIAo PLUlflU 1st aid 2rd Quarters of 1991 A. LtO4 Pavisionn: .

l Dttring the first. two quartern of 1991, OLc4 wan revinal once, frun Pov.16 to

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ikw. 17 An ikwinion 17 to G04 lxcann effective on June ?4,1991, Shoreham'c 1mP, an rycified in the governirn 001, was concurrently mluoed in acqc, '

reflecting the non-creratify ard defuelat statun of the plant,

s. Sanpliry frequencien for mrtain ef fluent patJuayn were nvlucui and analynin rcrptinsinnta for inotqvs no longer available for reloano were deleted.

Enviroratental sanpling nquitutents for rid 1h nid grnuxi water were deletal ninco the Fit 1 ways do not currently exist. 7ho outer rirm of direct radiation rionitority stationn van clintinated ninco potent.lal exposure trou tuttire bhorrham reintui radioactivity is innignificant and all done raten are evaluatni to be at natural luchgrottnd icvel at thenc 1ccatmas. Environnental nanplo analynin raluinstnnts were reducx4 pimilar to the ef fluent analynin nquiratonts. In addition, 004 control md curveillanco nquinwnt a for the Ventilation Ikhaunt Treatment Syntan, Contairtinnt Pttnjirvj nrd Venting arvi tho l Ganeoun JW1wanto Treatunnt Syntan were eliminatNI.

131wmkly in-neanon Oby-octoler) milk nanplirn and quarterly potable water mmplire ere last collectcd on 6/14/91 and 6/6/91, recp etively. Puture colltction of thene two tyren of 1024P sanples will coaco frun thin point on.

The TID's i.t tic full 36 innot / outer ntation ara the 5 extra nchool/ park relatal locations were last collected for the 1991 ?nd quarter on 7/11/91. Startiry with the 3ni quarter, only la direct radiation nnnitorn at the 16 inner plus 2 control locationn will le collectal. 'Iho rm,ining 23 will le p'twinently discontinurd.

The foal product narapiirn, prinarily of bmad loaf vtsetation gnun locally, ir no longer noroly a culmtituto for unavailable milk aanples. Becaune or the

  • shif t of critical exposure path frun milk to grutnd deponition after the charecover fmn full puer geration nrdo to the 6 fueled cuvittion, nanpling of vcgetation 2n ncw ochalulod to be a rtgular activity, with inquency dqraling on the timing of harvest.

Conduct of analysin of all IMP nanplen colheted before the new PJW neoro date of 6/24/91 has len ongoing in the old fonmt, consistant with the intent of the 4

sanplity. Irginning in August 1991, all analyses will le in the new fonut, ard all lodine-131 radioanalynis rcquimrnnts in the weekly ahicrne particulate sanplen and the food product aanples that were collect.ed after 6/24/91 will le deleted.

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  • II . Sanple Flcw Pailurn in Ibich Liquid Dischattje 91D-046:

On May 17, 1991, raiortly af ter starting a batch dinchanjo finn the Discharge h' acto Sanple Tank, the ample pimp on the Radraste Dischanje Sattple !bnitor unit (1D11-1WL-013) tritptd. 'this trip wcmt unroticcxl due to the coincidental failure of the on-skid ca'iple f1cw twitch which nontally wcults rhut of f the dischanie valve upon a no f1tw signal, resultiivj in the batch dincharge tot imity; sanplcx1 contirnninly, licuever, this batch was analyzul prior to startlig its releace in acconlanm with plant pixnxlures and detenninod to le less than L!D'n for all nuclides of consequence. '!he batch dose totain ac Tms t he waterlorne exposure patlway are all zems fran the carputerized calculations by the DFS Licptid Iwtwante Pnyyram, An Ihyineerirxj Charyje ikquent, 10118 1498, van issund to troke a nottvare enharnmvit to detect and prevent t'.!o cot 11tior' . n the future. Arid it was deterntincd (through RTS Itetort of .0antan; dcn".itions FAC 491-04) to le a non-reportable event por 10GT150.72 riry! 50.??,

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