ML20246P109

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Revised, Effluent & Waste Disposal Semiannual Rept for Second Half 1985
ML20246P109
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/31/1985
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20246K241 List:
References
NUDOCS 8909110044
Download: ML20246P109 (19)
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.fMLNDNENT to the PRAIRIE ISLAND Effluent and Waste Disposal Senfannual Report

'(for the 2nd half year of 1985)

This report is being resubmitted to include an abnormal

. release for; this period resulting from the release of a

. Liquid Waste' Tat,k prior to shift supervisor approval.

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PDR-ADOCK 05000292

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1985 Effluent S miannual Report REV. 1 L '

Retention: Lifetime

.Pega 1 of 9-l ' ','

1 EFFLUENT SEMIANNUAL REPORT 01-JUL-85 THROUGH 31-DEC-85 SUPPLEMENTAL INFORMATION l

Facility:

Prairic Island Nuclear Generating Plant Licensee:

Northern States Power Company License Numbers: DPR-42 & DPR-60 A.

Regulatory Limits 1.

Liquid Effluents:

a.

The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:

for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ 2.

Gaseous Effluents:

.a.

The dose rate due to radioactive materials released in gaseous efdluents from the site shall be limited to:

noble gases 4500 mrem / year total body 43000 mrem / year skin I-131, 3-3, LL?

41500 mrem / year to any organ b.

The dose due to radioactive gaseous effluents shall be limited to:

noble gases 410 mrad /auarter gamma 420 mrad / quarter beta 420 mrad / year gamma 440 mrad / year beta I-131, H-3, LLP 415 mrad / quarter 430 mrad / year

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1985' EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 2

!L%.

p.

B.

Maximum Permissible Concentration 1.

Fission and activation gases in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column /

2.

Iodine and particulate with halflives greater than 8 days in gaseous releases:

)

i 10 CFR 20, Appendix B, Table 2, Column 1 l

3.

Liquid effluents for radionuclides'other than dissolved or entrained gases:

10 CFR 20, Appendix B, Table 2, Column 2 l

4.

Liquid effluent dissolved and entrained gases:

1 2.0E-04 uCi/ml Total Activity C.

A.erage Energy Not applicable to Prairie Island regulatory limits.

D.

Measurements and approximations of total activity 1.

Fission and activation gases Total GeLi 25%

in gaseous releases:

Nuclide GeLi 2.

Iodines in gaseous releases:

Total GeLi i25%

Nuclide GeLi 3.

Particulate in gaseous releases:

Total GeLi 25%

Nuclide GeLi 4.

Liquid effluents Total GeLi 25%

Nuclide GeLi j

_____-____ ________-__ a

3 [.

1985 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 3 A

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?

- 1. 0.

BATCH RELEASES (LIQUID)

QTR: 03

.QTR: 04

'1.1 NUMBER OF BATCH RELEAStu 6.90E+01 4.80E+61 1.2 TOTAL T';1E PERIOD (HRS) 1.09E+02 7.95E+01

-1.3 MAXIMUM TIME PERIOD (HRS) 1.90E+00 2.37E+00 I

1.4 AVERAGE TIME PERIOD (HRS) 1.58E+00 1.66E+00 l

1.5 MINIMUM TIME PERIOD (HRS) 8.30E-01 1.00E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 2.44E+04 2.57E+04 l

2.0 BATCH RELEASES (GASEOUS)

QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 4.00E+00 6.00E+00 2.2 TOTAL TIME PERIOD (HRS),

1.44E+01 2.08E+01 2.3 MAXIMUM TIME PERIOD (HRS) 8.00E+00 9.60E+00 2.4 AVERAGE TIME PERIOD (HRS) 3.595+00 3.476+00 1

2.5 MINIMUM' TIME PERIOD (HRS) 1.47E-01 1.41E-01.

g 3.0 ABNORMAL RELEASES (LIQUID)

QTR: 03 QTR: 04 3.1 NUMBER OF BATCH RELEASES 1.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED **

(CI) 4.12E-01 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 4.12E-01 0.00E+00

)

SEE ATTACHMENT #1 i

l 4.0 ABNORMAL RELEASES (GASEOUS)

QTR: 03 QTE: 04 I

4,1 NUMBER OF BATCH RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 l9.

1985 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 4 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 03 OTR: 04 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 1.94E+01 9.36E+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.46E+00 1.19E+00 5.3 GAMMA DOSE (MRAD) 8.29E-03 5.56E-03 5.4 BETA DOSE (MRAD) 2.77E-02 1.57E-02 5.5 PERCENT OF GAMMA TECH SPEC (%)

8.29E-02 5.56F 02 5.6 PERCENT OF BETA TECH SPEC (%)

1.39E-01 7.85E-02 6.0 IODINES 6.1 TOTAL I-131 (CI) 3.46E-03 4.30E-04 6.2 AVERAGE RELEASE RATE (UCI/SEC) 4.40E-04 5.47E-05 7.0 PARTICULATE 7.1 TOTAL RELEASE (CI) 1.17E-05 8.89E-07 7.2 AVERAGE RELEASE RATE (UCI/SEC) 1.49E-06 1.13E-07 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 2.19E+01 2.46E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 2.79E+00 3.13E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 2.79E+00 3.13E+00 10.0 DOSE (MREM) 2.43E-01 6.67E-02 11.0 PERCENT OF TECH SPEC (%)

1.62E+00 4.45E-01 12.0 GROSS ALPHA (CI) 5.80E-07 7.93E-08

~

'1985 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 5

. TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI 5.78E-01 5.42E-01 XE-131M CI 1.27E-02 8.54E-03 l

XE-133 CI 1.80E+01 8.41E+00 3.51E-01 3.90E-01 XE-133M CI 1.01E-04 3.70E-03 XE-135 CI 3.60E-01 2.08E-02 3.39E-04 TOTAL CI 1.84E+01 8.41E+00 9.63E-01 9.45E-01 14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 I-131 CI 3.46E-03 4.30E-04 1.34E-07 I-133 CI 1.24E-04 1.17E-05 TOTAL CI 3.58E-03 4.42E-04 1.34E-07 15.0 PARTICULATE CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 CO-58 CI 1.11E-05 1.60E-07 CO-60 CI 5.95E-07 7.20E-07 CS-137 CI 9.23E-09 TOTAL CI 1.17E-05 8.80E-07 0.00E+00 9.23E-09

- - - - - - - - - - = - - - - - - - - - --

- - = - - - -

l414

'y-li985? EFFLUENT,SEh! ANNUAL REPORT-REV.- 1 PAGE-6:

i kIh CTABLEj2A f

f--f JLIQUID~ EFFLUENTS - SUMMATION.0F ALL RELEASES-QTR: 03 QTRi 04.

E

=16i0 ; VOLUME'OF WASTE PRIOR-TO. DILUTION'(LITERS)-

3.63E+07

.4.35E+07 1

'm' 117.0- VOLUME OF DILUTION WATER (LITERS) 2.26E+11-

.1.65E+11'

' 18'.0 FISSION.AND ACTIVATI,0N PRODUCTS-3-

18.1 TOTAL RELEASE;W/O H-3, RADGAS, ALPHA (CI) 1.23E-02 4.73E-03 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML)-

5.44E-11 2.87E -

11 9. 0 ' TRITIUM 19.1 iTOTAL RELEASE (CI) 2.41E+02-1.28E+02 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.07E-06 7.76E 9-20.O~ DISSOLVED'AND ENTRAINED GASES 20.1,TOTALJRELEASE'(CI) 2.24E-02 1.93E-02

~

20.2 AVERAGE DILUTED-CONCENTRATION'(UCI/ML) 9 -. 91 E-11 :

1.

7E-10 21 ~. 0-GROSS ALPHA (CI) 0.00E+00-0.00E+00-2210 TOTALTTRITIUM,-FISSION l.ND ACTIVATION

-PRODUCTS.(UCI/ML) 1.07E-06 7.76E-07u 123.0 TOTAL BODY DOSE (MREM) 5.32E-04 4-.74E-04' 34.0 CRITICAL ORGAN

-24.1 DOSE (MREM) 5.62E-04 5.46E-04 24.2 ORGAN GI-LLI LIVER y

25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)

1.77E-02 1.58E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)

5.62E-03 5.46E-03

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1985 EFFLUENT' SEMIANNUAL REPORT REV. 1 PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 03 QTR: 04 QTR: 03 QTR: 04 AG-110M CI l1.59E-04 2.40E-04 CS-134 CI 1.47E-05 CS-136 CI 1.24E-05 CS-137 CI 2.82E-05 5.93E-06 CS-138 CI 1.03E-05 7.278-06 I-131 CI 2.33E-05 5.19E-04 I-133 CI 3.18E-06 CO-58 CI 4.49E-04 3.26E-04 CO-60 CI 7.50E-06 1.80E-04 3.43E-05 FE-59 CI 5.25E-05 4.05E-05 FE-55 CI 7.24E-03 NA-24 CI' 5.48E-06 1.95E-06 NB-97 CI 3.62E-06 6.99E-06 SB-122 CI 1.84E-04 SB-124 CI 2.34E-03 2.94E-03 SB-125 CI 9.71E-04 8.61E-04 SC-47 CI 8.31E-05

,1.24E-04 SN-113 CI 3.52E-06 4.61E-05 SR-85 CI 8.09E-06 SR-92 CI 2.19E-05 1.02E-05 TC-99M CI 7.70E-06 TE-132 CI 3.08E-06 ZR-97 CI 9.00E-06 l

TOTAL CI 0.00E+00 7.37E-05 1.23E-02 4.66E-03 I

n-_.

1985 EFFLUENT' SEMIANNUAL REPORT REV.-1 PAGE 8 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 28.0 DISSOLVED AND ENTRAINED GA5ES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI 1.87E-03 XE-131M CI 4.67E-04 4.65E-04 XE-133 CI 3.42E-05 2.00E-02 1.88E-02 XE-133M CI 3.12E-05 XE-135 CI 2.79E-05 4.83E-05 TOTAL CI 3.42E-05 0.00E+00 2.21E-02 1.93E-02 lu____-____

j

+:

1985 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 9 f

i ATTACHMENT #1 ABNORMAL LIQUID RELEASE - SUMMATION OF ALL ACTIVITY

)

CONTINUOUS MODE BATCH MODE NUCLIDE UNITS-QTR: 03 QTR: 04 QTR: 03 QTR: 04 AG-110M CI 2.52E-06 CO-60 CI 3.59E-06 SB-125 CI 3.30E-06 XE-133 CI 3.86E-06 TRITIUM CI 4.12E-01 TOTAL CI 0.00E+00 0.00E+00 4.12E-01 0.00E+00

s PINGP 753, Rev. 1 Q4-Retention:

Lifetime W

Page 1.of 5 PRAIRIEISLANDNUCLEAkGENERATINGPLANT Period: 7/1/85 to 1/1/86 License No. DPR-42 NORTHERN STATES POWER SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPOR"1 Table 1:

Solid Waste and' Irradiated Fuel Shipments A.

Solid Waste Total Volumes and Measured Curie Quantities:

~.

1.

Type of Waste:

Container Units Total Volumes I

A.

Resin Ft 3 340 170 Ci 3.008 B.

Dry Compacted Ft 3 0

i Ci 0

g.

Ig7 y~

C.

Non-Compacted Ft 3 0

Ci 0

D.

Wst. Concentrates Ft 3 0

C1 0

S.

Spent Fuel Ft 3 0

Ci 0

9 O

PlNGP 753, Rev. 1 Re.tention:

Lifetime Page 2 of 5

&o.s.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7/1/85 to 1/1/86 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPOP.T Table I:

Solid Waste and Irradiated Fuel Shipments (Continued) 2.

Measured Major Nuclide Composition by. Type of Waste:

TYPE (From Page 1)

Nuclide Percent H3 27.8 A

CS137 20.8 _

FESS 14.7 C058 13.2 CS134 10.6 CO60 5.0

_ SB125 3.3 SB124 1.3 N163 1.2 l

. f..,

4

  • = Inferred - Not heasured on site S

PINGP 753, Rev. 1.

~

Retention:

Lifetime TPage 3 of 5

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7/1/85 to 1/1/26 NORTHERN STATES POWER License No. DPh-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:

Solid Waste and Irradiated Fuel Shipments (Continued) 2.

Measured Major Nuclide Composition by Type of Waste (Continuation):

TYPE -(From Page 1)

Nuclide Percent

~.

~

,.~

  • = Inferred - Not Measured on Site

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l lJ iPINGP 753,.Rev. I.

.. j

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.. Retention:-

Lifetime l

Page 4;of'.5; PRAIRIE ISLAND N11 CLEAR GENERATING PLANT.

Period: 7/1/85:to-1/1/86-

~

. NORTHERN-STATES POWER License Nc,... DPR-42 J

-l 1

SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT'

~ Table I:

Solid Waste and Irradiated Fuel Shipments'(Continued)-

, 3.-

Solid-Waste Disposition 4

Number of' Shipments.

Mode Destination-ei Richland. WA 2

Truck i

. B.-

Irradiated Fuel Shipments:

r, N Number of. Shipments Mode Destination 0

d a

8 epr e

m

.~_m.__._.,mm_.__,__

l u r.

)*

t-

,-/*

PINGP 753, Rev. 1 Retention:

Lifetime Page 5 of 5

.0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-/-8 f 6 /-/~ & -

NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:

Solid Waste and Irradiated Fuel Shipments (Continued)

C.

Shipping Container and Solidification Method:

No.

Volume Activity Type of Container Solidify (Ft3)

(Ci)

Waste Code Code 85-40 170 0.61A

.i T.

85-41 17n a non a

+

fb a

CONTAINER CODES:

L = LSA A = Type A B = Type B Q = Large Quantity SOLIDIFICATION CODES:

C = Cement TYPES OF WASTE:

A = Resins B = Dry Compacted C = Non-Compacted-D = Wst. Conc.

S = Spent Fuel

'f ?_ w.

'f:

6 f ;.g

' Le-lx.s J

4 a

I Page. Revisions to Effluent and~ Waste Disposal Semi-Annual' Report:

-for Julv 1, 1985 throuch December 31, 1985 The Semi-Annual Effluent and Waste Report for July l',1985 through December.

31, 1985 has been revised to incorporate Sr-89, Sr-90.and Fe-55, analysis-

' results that arrived;from our! contractor too late to be incorporated in the report submitted on; March 3, 1986

_Results for analyses of Sr-89 and Sr-90.

'were below detection limits ^and did not effect the result of the report.

-Please replace pages 5, 6 and 8 of the-subject report-with the attached re':ised pages.

9 1.

4,<

I PI.NGP 158. Re r, 6-

' Page 5 of 8 j

,Y TABLE 1C EFFLUENT SEMIANNUAL REPORT GASEOUS EFTLUENTS GROUND LEVEL RELEASES CONTINUOUS NODE BATCH MODE l-1 1

1 I

I l

J NUCLIDE l UNIT i

QTR ii3 I

QTR f/4 l

QTR "3 l

QTR 414

]

-l I

I I

I l

l 13.0 INDIVIDUAL FISSION AND ACTIVATION GASES l Kr85 i Ci

-l I

5.78E-01 1

5.42E-01 l

l Kr85m i Ci i

i I

i l

l Kr87 i Ci i

i i

I l

l Kr88 I Ci 1

1 i

l l

l Xe133-l Ci i

1.80E+01 1

8.41E+00 l

3.51E-01 I

3.90E-01 l

l Xe135 I Ci 1

3.o0E-01 1

I 2.08E-02 1

3.39E-OL l

-l Xe135m i Ci i

i i

I l

l Xe138 i Ci l

l I

I l

l Xe131m i Ci l

I i

1.27E-02 I

8.54E-03 l.

l Arel l Ci i

i f

I l

l Xe133m i Ci i

l i

1.01E-OL i

3.70E-03' i

l I

i l

l I

l l

l 1

I I

I l

l-1 I

I I

I l

l Total I Ci i

1.84E+01 I

8.41Et00 1

9.63E-01 l

9.45E-01 j

14'.0 IODINES (Ci) l-1131 l Ci 3.46E-03 1

4.30E-04 1

1.34E-07 I

l l I133 l Ci l

1.24E-04 l

1.17E-05 i

I l

j I135 i Ci l

I I

1

-l l Total I Ci I

3.5BE-03 i

L.42E-04 1

1.3aE-07 1

0.00E-00 l

CONTINUOUS MODE BATCR MODE 1

I i

l 1

1 1

l l NUC'.IDE l UNIT l

Q3 413 l

QTR ii4 l

QTR ii3 l

QT3 ii4 1

l 1

1 I

I I

l-15.0 ?ARTIC"I.ATES (Ci) l SrS9 I Ci

'I t

t i

I l Sr90 i Ci i

I 6

I I

a l Cs13a

! Ci i

i I

I l

9 221-09 I

l l Cs137 I Ci 1

i I

1 I

l Ea-Esla0 t Ci I

+

l l ;c55 i Ci t

1. '.1E-05 4

1.00E-07 i

I h

5.95E-07 i

7.00E-07 i

i Oce0 l

I i Totsi 2i

'...7E-05 d.SCE-07 L.30E-0C 9 23E-09

-I i

1

,y,.

..n (

r O

{ PUGF.:.'158,.R2v. 6 ;.

[p Pagt.4 ei 8

^

$2 3 i

TABLE 2A pvk EFFLUENT SEMIANNUAL REPORT.

LIQUID EFFL1 TENTS - SU21ATION OF ALL RELEASES 1

I I

t j

TOTAL l ERROR *4 ;

l UNIT l-QTR 43 1

QTR #4

.)

l g.

16.0 VOLLME OF WASTE

'(Prior to Dilution).

l Liters I

3.63E-07 1

e.35E-07 12.50E+01.1 17.0 VOLUME OF DILUTION Vater.(lite:5) l Liters i

2.26E-11 1

1.e5Et11 12.50E-01 l 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 Total Release V/O H-3, (Ci)

{

i l

l Rad Gas, Alpha i

1.23E-02 l

1.29E-02 12.50E+01 1 18.2 Average Diluted (pCi/ml) l l

l

' Concentration l

5.44E-11 l

7 82E-11 l

19.0 TRITIUM 19.1. Total Release (Ci) 1 2 41E-02 1

1.28Ewo2 2.50E-01 i 19.2 Average Diluted (pCi/ml) l l

i Concentration l

1.07E-06 1

7.76E-07 l

20.0 DISSOLVED ~AND ENTP.AINED GASES 20.1 Total Release (Ci)

I 2.2eE-02 1

1.93E-02 12.50E-01 20.2 Average Diluted (pCi/ml) l i

i Concentration

[

9.91E-11 1

1.17I-10 l

21.0 GROSS ALFEA 21.1 Total Release (Ci) 1 0.00E-00 1

0.00E-00 12.50E-01 20.O TOTAL ~RITILt. FISSION AND ACTIVATICS FRCDUCTS (pCi/ml) l 1.0!E-Oc r

7 7eE-07

2 50E-0 l

...,. ]qwym---

_.-----:------y-es a; e

? -t::

l h..l" h 1@

~NC PINGP T 155,7 Rav. ej Mg Para 8'of 8f k,c.v.., n,

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k $[ N,

p@,

Ee

~ TABLE 2A ev EFFLUENT SEMIANNUAL RPEORT

. m.,. -;;;.

.t 5

LIQUID EFFLUENTS - SUtt'!ATION OF ALL RELEASES'

~

m....

CONTINUOUS MODE' BATCH MODE

.I l

l 1

l

'[ M l'[

NUCLIDE~

l ; UNIT.

'I

.QTR #3 l

QTR via 1

QTR #3 l

QTR #4 l

^

1

-l

'l I-l' I

i l

ti a

hj27.0iTNDIVIDUALLIQUIDEFFLUENT4 l'5r89 c l' Ci i

I-l 1

l fl Sr90-

. I Ci i

i 1

l-l

-l Cs134-I Ci<

i i

1.47E-05 1

I l

r

?

  • l Cs137 1 Ci-1 I

2.S2E-05 4

5.93E-06 I l

l.1131-1 Ci.

I l-2.33E-05 i

5.19E-04 I l

ij-Co58

. I Ci '

I i

4.49E-06 6

3.26E-04 l

l: Coo 0-

..I - Ci i

I 7.50E-06 1

1.80E-04 1 3.43E-05 l

l:Fe59 I Ci-1 i-l 5.25E-05 i

L.05E-05 l~

c".. 9.'

j:Ino5

-I Ci-1 I

I I

l I

.l Mn54, I Ci i

. I I

1 l'

l Cr51 I Ci 1-1 1-t l-J.) 2r-Nb95' 1 Ci

-1 I

I i

l TJ Mo99 1 Ci-1 I

I I

l l Ba-La140 1 - Ci -

1 l-1 i

l 9

l'Fe 1 Ci I

t 7. 2:.E-03 1

a m _n,

.:l

.w=

-I l-1 I

3.80E-03 1 4.26E-03 l

LJ Total-1 Ci l-0.00E-00 1

7.37E-05 1

1.23E-02 1

1 49E-02 l

.x SUM OF,NUCLIDE ACTIVITIES FROM ATTACEENT #1 CONTINUOUS MODE 3ATCH MODE l

-l 1

1 i

i I

.l NUCLIDE~

'l. UNIT l

-QTR #3 l

QTR #4 1,QTR #3 1

QTR #4 1

]

I l-1 I

I l

j28.0 DISSOLVED AND ENTRAINED GASES i

' 00E-02 1

1.SSE-02 l

Tl Xe133-I Ci 3.42E-05 i

..l Xe133m 1 Ci i

l i

1 3.12E-05 l

1-Xe131m I Ci i

i 1

e.o7E-Oe 1

4.65E-OL l

(j Xe135 i Ci i

i i

2.79E-05 i

e.83E-05 l

l KrS$m i Ci t

i f

i I

,j Kre5

Ci i

i t

1.57E-03 I

l fl Krs8 t Ci i

i i

I l

i i

l.

4 i

I

j-

..;I-95 G.gCE-00 2.;-E-0;

. 93E-02 TJ ot -

i t

.. _ _ _ _... _ -. _ _ _ _ _ _. _ _

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