B13140, Milestone Nuclear Power Station,Units 1,2 & 3 Semiannual Radioactive Effluents Release Rept,Jul-Dec 1988

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Milestone Nuclear Power Station,Units 1,2 & 3 Semiannual Radioactive Effluents Release Rept,Jul-Dec 1988
ML20235V824
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 12/31/1988
From: Mroczka E, Sears C
NORTHEAST NUCLEAR ENERGY CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B13140, NUDOCS 8903100351
Download: ML20235V824 (84)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

N UTILITIES o.nor.i orric.o . s.ioen stro t. seriin. Conn.ciicut ARTFORD. CONNECTICUT 06141-0270 k L IJ [ ",'", [ [ [y ",", (203) 665-5000 f February 28, 1989 Docket NoL _50-245 50-336 50-423 B13140 Re: 10CFR50.36a U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Millstone Nuclear Power Station Unit Nos. 1, 2, and 3 Semiannual Radioactive Effluents Release Report In accordance with the requirements of 10CFR50.36a, the Technical Specifica- 4 tions and the Radiological Effluents Monitoring Manual, a copy of the Semi-annual Radioactive Effluents Release Report is herewith submitted.

This report includes a summary of the quantities of solid radioactive waste and liquid and gaseous effluents for the period of July through December 1988.

An anndal Radioactive Effluents Dose Report (to be submitted in March 1989) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released during the calendar year (January through December 1988).

The report has been . prepared in accordance with the format of Regulatory Guide 1.21, and copies of the report are being forwarded in accordance with the provisions of 10CFR50.4(b)(1).

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY I

E . h . M w />y E. J. Mroczka k

Senior Vice President LodL-By: C. F. Sears Vice President l l cc: W. T. Russell, Region I Administrator l M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 8903100351 881231 h PDR ADOCK 05000245 d

_ __ ____? - _ . _ . - . _ _ - _ .b]_

NORTHEASTNUCLEAR ENERGY COMPANY i MILLSTONE NUCLEAR POWER STATION i

UNITS NO.1,2 & 3 .

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SEMIANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT JULY-DECEMBER 1988 P,

  • s- OPERATING LICENSE NO's. DPR-21, DPR-65, & NPF-49 DOCKET NO's. 50-245, 50-336. & 50-423 i

NORTHEAST UTQ.lTIES o.n r.i Ome.. . s.io.n sir i. s.riin. conn.ciicui l avs' nIsemc *"

P.O. BOX 270 I HARTFORD. CONNECTICUT 06141-0270 g k ' J CEDN.e5"ca,",, (203) 665-$000 February 28, 1989

  • Docket Nos. 50-245

!!0-336 50-423 B13140 Re: 10CFR50.36a U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Millstone Nuclear Power Statior.

Unit Nos. 1, 2, and 3 Semiannual Radioactive Effluents Release Report In accordance with the requirements of 10CFR50.36a, the Technical Specifica-tions and the Radiological Effluents Monitoring Manual, a copy of the Semi-annual Radioactive Effluents Release Report is herewith submitted.

This report includes a summary of the quantities of solid radioactive waste and liquid and gaseous effluents for the period of July through December 1988.

An annual Radioactive Effluents Dose Report (to be submitted in March 1989) will include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released during the calendar year (January through December 1988).

The report has been prepared in accordance with the format of Regulatory Guide 1.21, and copies of the report are being forwarded in accordance with the provisions of 10CFR50.4(b)(1).

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 1

Y b , b w%y Q E. J. Mroczka Senior Vice President N

By: C. F. Sears

f. Vice President N- cc: W. T. Russell, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3

_ __ _______ _ a

NORTHEASTNUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION (JNITS NO.1,2 & 3 SEMIANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT JULY-DECEMBER 1988 l

f' OPERATING LICENSE NO's. DPR-21, DPR-65, & NPF-49 DOCKET NO's. 50-245, 50-336. & 50-423 1

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TABLE OF CONTENTS it .

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I 1.0 . . . . . . . . . . . . . . . . . . . . . . . . .............. Introduction 2.0 . . . . . . . . . . . . . . . . . . . . . . . ............... Radioactive Effluent Releases .

3.0 . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . Radioactive Solid Waste l

1 >

4.0 . . . . . . . . . . . . . . . . . . . . . . ... ....... .. Supplementallnformation 5.0 . . . . . . . . . . . . . . . . . . . . .. ... . Changes to the REMM/ODCM/PCP 6.0 . . . . . . . . . . . . . . . . . . . . . . . .. .. .. Effluent Monitor Inoperability

Appendix A - Updated Tables L

l I.

L 1

l ' e ~.

l.

1 1

~

l k'. - . _ __ ____._.____.______.______.________.O

4 ,

INTRODUCTION e.

, o: o 1'.0 This report is being submitted for Northeast Nuclear Energy Company'sT Millstone Power Station, Units No.1,2, and-3 in accordance with the requirements of 10CFR50.36a, and the Radiological Effluent Technical:

Specifications and in the format outlined by U. 5. NRC Regulatory Guide .

1.21.

During the period covered by this report, Unit No.1 operated with a unit capacity factor of 94% Unit No. 2 with a unit capacity factor of 98% and -

Unit 3 with a unit capacity factor of 85%.

Unit 3 was shutdown for main steam isolation valve repairs in October 1988.

A single report is being submitted for all units as the three units share a number of items related to this report. . However, effluent release data are presented separately for each' unit.

This report does not consider the dose consequences of the radioactive effluents tabulated here. However, the data in the report is comparable to prior experience and the results of dose calculations are anticipated to be well within regulatory limits. These will be published shortly in the Annual Radioactive Effluents Dose Report for 1988.

l 17 -

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<- ' RADIOACTIVE EFFLUENT RELEASES

~

2.0 ;The plants were operated in accordance with the Technical 5 specifications. The liquid .

W and airborne radioactive effluents are given in the attached tables as follows:

. Table 2.1-1 . . . . . Unit 1 Liquid Effluents - Summation Table 2.1-2 '. . . . . . Unit 1 Liquid Effluents- Batch Mode -

iable 2.1-3 . . . . . . Unit 1 Gaseous Effluents - Summation Ta ble 2.1-4 . . . . . . Unit 1 Gaseous Effluents - Elevated Continuous Ta ble 2.1-5 ' . . . . . . Unit 1 Gaseous Effiuents- Batch Mode Ta ble 2.2-1 . . . . . . Unit 2 Liquid Effluents- Summation Table 2.2 2 . . . . . Unit 2 Liquid Effluents - Continuous Mode (SGBD)

Table 2.2-3 . . . . . . Unit 2 Liquid Effluents- Batch Mode ' ,

Table 2.2-4 . . . . . . Unit 2 Gaseous Effluents Summation Table 2.2-5 . . . . . . Unit 2 Gaseous Effluents - Mixed Continuous Mode -

Unit 2 Ventilation and 5.G. Blowdown Tank Vent Table 2.2-6 . ... Unit 2 Gaseous Effluents- Mixed Batch Unit 2 Containment Purges J Table 2.2-7 . . . . Unit 2 Gaseous Effluents - Elevated Batch  ;

Unit 2 Waste Gas Tanks Table 2.3-1 . . . . . Unit 3 Liquid Effluents - Summation Table 2.3 2 . . . . . . Unit 3 Liquid Effluents- Continuous Mode (SGBD)

Table 2.3-3 . . . . . - Unit 3 Liquid Effluents - Batch mode (LWS)

Table 2.3-4 . . . . . . Unit 3 Liquid Effluents - Batch Mode (WNS)

Table 2.3-5 . . . . . . Unit 3 Gaseous Effluents - Summation Table 2.3-6 . . . . . . Unit 3 Gaseous Effluents - Mixed Continuous (Unit 3 Ventilation Vent) l Table 2.3-7 . . . . . . Unit 3 Gaseous Effluents - Mixed Continuous

% (ESF Building Vent)

Table 2.3-8 . . . . . . Unit 3 Gaseous Effluents - Mix Batch

    • .- (Containment Drawdown)

i s ' l' r.

RADIOACTIVE EFFLUENT RELEASES' Continued -

4L Ho Table 2.3 9. . . . . . Unit 3 Gaseous Effluents - Mixed Batch (Containment Purge)

Table 2.3-10 .... Unit 3 Gaseous Effluents - Mixed Continuous (Turbine Gland Sealing System Exhaust)

Table 2.3-11 ... Unit 3 Gaseous Effluents - Mixed Batch (Main Condenser Mechanical Vacuum Pump Exhaust

[-

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1-

o L, ' TABLE 2.1-1 MILLSTONE NUCLEAR POWER STATION L

UNIT #1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES o

QUARTERLY JULY AUGUST SEPTEMBER YEAR 1988 A. Fission and Activation Products

1. TOTAL ACTIVITY Ci RELEASED 3.38E-02 1.36E-02 9.78E-02 1.45F-Ol
2. AVERAGE DILUTED UCi/a1 ACTIVIIY DURING~ PERIOD 4.52E-10 1.83E-10 1 32E-09 6.54E-10 B. Tritium
1. TOTAL ACTIVITY Ci MEASE 3.91EM O 3.64E+00 4.25E+00 1.18E+01 1
2. AVERAGE DILUTED UCi/ml ACTIVITY DURING PERIOD 5 23E-08 4.89E-08 5 74E-08 5.32E-Ob C. Dissolved and Entrained Cases
1. TOTAL ACTIVITY 6.42E-05 1.75E-05 7.81E-05 1.60E-04 RELEASED
2. AVERAGE DILUTED UCi/ml ACTIVITY DURING PERIOD 8.58E-13 2.35E-13 1.06E-12 7 22E-13 D. Cross Alpha
1. TOTAL ACTIVITY Ci -------- -------- --------

RELEASED E. Volume

1. VOLUME OF WASTE LITERS RELEASD 1.54E+06 1.16EM6 1.16E+06 3.86E@ 6

""- 2. VOLUME OF DILUTION LITERS DRING REI. EASES 7.67E+09 .5.83E+09 6.40E+09 1.99E+10

    • 1
3. VOLUME OF DILUTION DURING TIME PERIOD 7.48E+10 7.44E+10 7.24E+10 2.22E+11

TABLE 2.1-1

)

MILLSTONE NUCLEAR POWER STATION i

UNIT #1  ;

LIQUID EFn,UENTS - SUMMATION OF ALL RELEASES j 1

o QUARTERLY NOV DEC TOTALS OCT YEAR 1980 A. Fission and Activation Products

1. TOTAL ACTIVITY Ci RELEASED 2.11 E-02 2.00 E-02 1.79 E-02 5.00 F 0?
2. AVERAGE DILUTED UCi/al ACTIVITY DURING PERIOD 2.82 E-10 3.29 E-10 2.63 E-10 2.89 E-10 B. Tritium
1. TOTAL ACTIVITY Ci RELEASED h.17 E+00 5.66 E+00 h.80 E+00 1.h7 F+01
2. AVERAGE DILUTED UCi/ml ACTIVITY DURING PERIOD 5 57 E-06 9.32 E-08 7.18 E-08 7 21 E-08 C. Dissolved and Entrained Gases
1. TOTAL ACTIVITY Ci RELEASED 3.76 E-Oh' 8.10 E-Oh 2 77 E-Oh 1.L6 E-03
2. AVERAGE DILUTED UCi/ml ACTIVITY DURING PERIOD ,5.02 E-12 1.33 E-11 4.07 E-12 7.16 E-12 D. Gross Alpha
1. TOTAL ACTIVITY Ci --- --~~ ------ ~~~~

RELEASED E. Volume

1. VOLUME OF WASTE LITERS RELEASED 1.12 E+0c, 1.52 E+06 1.13 E+06 1.27 E+06
2. VOLUME OF DILUTION ITERS DURING RELEASES 6.05 E+09 5 09 E+09 5 7h E+09 1.69 E+10

=. ~

3. VOLUME OF DILUTION '

DURING TIME PERIOD 7.49 E+10 6.07 E+10 6.81 E10 2.04 Ell

TABLE 2.1-2 MILLSTONE NUCLEAR POWER STATION - UNIT #1 i

LIQUID EFFLUENTS - BATCH MODE Year 1988 Nuclides Released Unit JULY AUGUST SEPTEMBER N""*"*(Y s

C1 1.88E-04 1.88E-04 Cr-51 Ci 1.28E-03 4.00E-04 5.48E-03 7.16E-03 Mn-54 I Tc-99M Ci Co-58 Ci co-60 Ci 2.99E-02 7.57E-03 1.90E-02 5.65E-02 1-131 Ci 9.92E-06 1.21E-05 2.20E-05 I-133 C1 1.95E-05 3.85E-05 5.80E-05 I-135 Ci Cs-134 C1 1.11E-05 5.60E-04 5.71E-04 Ci 1.94E-03 5.51E-03 2.53E-02 3.28E-02 Cs-137 Mo-99 ci Ce-141 ci Ce-144 Ci 4.05E-04 4.72E-05 1.67E-03' 2.12E-03 Zn-65 eg Fe-59 es __

Ci -

Ci Ci Ci Ci Fe-55 -------- -------- 4.52E-02 4.52E-02 Ci 2.39E-04 -------- -------- 2.39E-04 Sr-89 eg 3.16E-05 1.74E-05 3.36E-04 3.85E-04 Sr-90 Ci 3.38E-02 1.36E-02 9.78E-02 1.45E-01 Total Activity Ci Ke-133 1.09E-05 1.09r-ns C1 6.42E-05 1.75E-05 6.72E-05 1.49E-04 Xe-135 Ci

  • b. Ke-135M eg Ci

Ci Ci

TABLE 2.1-2 MILLSTONE NUCLEAR POWER STATION - UNIT #1 LIQUID EFFLUENTS - BATCH MODE Tear _1988 _

, Quarterly I DEC 're ni Nuclides Released Unit OCT NOV d _

s_ sn v nt _

Cr-51 C1 1 .sh E-OL 6.73 E-Os 3.90 E ch P.ph 7 nt C1 1.05 E-03 0.33 E-OL 2.61 E-oh Mn-54 1 .TL F-oh Tc-99M Ci 2.33 E-05 8.75 E-05 6.95 E os C1 co-58 3.07 E-02 Ci 1.17 E-02 8.52 E-03 1.05 E-02 Co-60 1.0h E-03 Ci 6.76 E-Oh 2.38 E-Oh 1.29 E-Oh I-131 9.68 E-Oh Ci 3 39 E-Oh 3.09 E-Oh 3.20 E-Oh I-133 C1 I-135 1.78 E-OL Ci 1.62 E-Oh 1.63 E-05 Cs-134 1.87 E-02 Ci h.70 E-03 8.69 E-03 5.3h E-03 Cs-137 Mo-99 c, Ce-141 et 6.85 E-06 6.85 E-06 ce..1p Ci 3 13 E-03 7.88 E-OL 9.37 E-Oh Zn-65 Cf 1.h0 E-03 3.68 E-05 3.68 E-05 Ee-59 ci L.70 E-06 ci h.70 E-06 Eu-103 2.09 E-05 Ci 2.09 E-05 Y-93 Ci Ci Cf

9.61 E-Oh 9.61 E-Oh Te-55 __

Ci 2.h8 E-Oh 3.8h E-05 2.10 E-OL Sr-89 Ci ---- 1.81 E-05 Cf 1.81 E-05 Sr-90 5.90 E-02 2.11 E-02 2.00 E-02 1.79 E-02 __

Total Activity Cf 1.18 E-oh 8.99 E-oh 2.30 E-Oh 5.51 E-oh Xe-133 Ci 5.6L E-Oh 2.59 E-OL 1.59 E-OL Cg 1.h6 E-OL

.., y,_333 I Xe-135M Ci Ci

=,

ci

< Ci l l

TABLE 2.1-3 MILLSTONE NUCLEAR POWER STATION UNIT #1 CASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES TE M UNITS TOTALS JULY AUGUST SEPTEMBER YEAR 1988 A. Fission and Activation Cases I

1. TOTAL ACTIVITY Ci RELEASED 9.52E+01 1.91E+00 5.19E+01 1.49E+02
2. AVERAGE RELEASE RATE '!*'#

FOR THE PERIOD 3.93E@l 7.83E-01 1.71E+01 1.89E+01 B. Iodines

1. TOTAL I-131 ACTIVITY Ci 1.27E-04 2.11E-04 6.24E-04 RELEASED 2.86E-04
2. AVERAGE RELEASE RATE 1.18E-04 5.20E-05 6.96E-05 7.91E-05 UCi/sec FOR THE PERIOD C. Particulate
1. TOTAL PARTICULATE Ci ACTIVITY RELEASED 4.25E-04 3.43E-04 3.18E-04 1.09E-03
2. AVERAGE RELEASE RATE #

FOR THE PERIOD 1.76E-04 1.41E-04 1.05E-04 1.38E-04

3. TOTAL GROSS ALPHA Ci __------

ACTIVITY RELEASED ________ ________

D. Tritium

  • o *
1. TOTAL ACTIVITY Ci RELEASED 1.12E+01 2.32E+00 1.38E+00 1.49t+01

~

2. AVERAGE RELEASE RATE #

FOR THE PERIOD 4.63E@0 9.51E-01 4.55E-01 1.89E+00

TABLE 2.1-3 i

MILLSTONE NUCLEAR POWER STATION UNIT #1 CASEOUS EFTLUENTS - SUMMATION OF ALL RELEASES UNITS TOTALS OCT NOV. DEC YEAR 1988 A. Tission and Activation Cases

1. TOTAL ACTIVITY Ci RELEASED 1.21 E+00 3 27 E+00 6.h7 I+00 1.10 E+01
2. AVERAGE RELEASE RATE FOR THE PERIOD 5 01 E-01 1.09 E+00 2.27 E+00 1.h0 E+00 B. Iodines
1. TOTAL I-131 ACTIVIIT Ci h.67 E-OL 2.66 E-Ok 1.32 E-Oh S.65 E-Oh-
2. AVERAGE RELEASE RATE UCi/sec FOR THE PERIOD 1.93 E-Oh 8.8h E-05 5.hh E-05 1.10 E-Oh C. Particulate
1. TOTAL PARTICULATE Ci ACTIVITY RELEASED 3.1h E-Oh 7.63 E-Oh 5.8h E-Oh 1.66 E-03
2. AVERAGE RELEASE RATE f**

FOR THE PERIOD 1.30 E-Oh 2.53 E-Oh 2.h1 E-Oh 2.12 E-04 I 3. TOTAL GROSS ALPHA Ci ACTIVITY RELEASED 2.09 E-07 2.61 E-07 2 62 E-07 7.32 E-07 l

.. D. Tritium l

1. TOTAL ACTIVITY Ci RELEASED 3.61 E-01 5.08 E+00 6.23 E+00 1.17 E+01
2. AVERAGE RELEASE RATE I!***

FOR THE PERIOD 1.h9 E-01 1.69 E+00 2.57 E+00 1.h9 E+00

TABLE 2.1-4 MILLSTONE NUCLEAR POWER STATION - UNIT #1 CASEOUS EFFLUENTS - ELEVATED RELEASE - CONTINUOUS MODE

(_fLielidesReleased l Unit l JULY AUGUST SEPTEMBER j u l r

1. Fission gases 4.69E+01 2.31E+01 7.00E+01 Xe-133 _Ci 1.06E+01 5.85E+00 1.65E+01 y_ __

C1 Ci 2.51E+00 2.51E+00 Er-88 /

C1 2.73E@0 2.09E+00 4.82E+00 tr-85e Cl 1.54E+01 7.95E+00 2.34E%1 Xe-135 Ci 8.49E@0 1. 91 FMO 4.RRE+00 1.53E+01 Xe-13)

C1 Kr-89 Cl

._ .. Ke-137 s . s ?r-mn 1.AAr+nt Ze-335m C1 1.11r+nt Ci Er-85 Re-133m Ci Ie-131m Ci Kr-85 __ Ci Ar-37 Ci 9.52E+01 1.91E+00 5.19E+01 1.49E+02 Total Fer Period Cf

2. lodines 5.4RF-na C1 2.61E-04 I 1.27E-04 2.10E-04 iodine-131 1.22E-03 3.74E-03 C1 1.62E-03 8.97E-04 iodine-133
3. Particulate C1 3.47E-05 1.50E-04 6.25E-05 2.47F-06 cr-51 ._

2.62E-06 C1 2.62E-06 1 &-54 Fe-59 C1 7.96E-07 7.96E-07 Co-58 Cg 3.09E-05 2.77E-05 3.86E-05 9.72E-05 Co-60 C1 1.01E-04 4.65E-05 1.97E-04 c, 4.98E-05 Zn-65 1.16E-06 2.59E-05 2.47E-05 I-131 C1 Cs-134 C1 2'.00E-05 2.11E-05 5.7Ar-ns Cs-137 C1 1.67E-U5 1.61E-04 1.97E-05 8.91E-05 2.70E-04 Ba-140 Cl Ce-141 Cl Ce-144 C1 Cf La-140 Ci

  • Ci 2.32E-05 5.58E-05 1. 86 t_-06 Sr-89 C1 1.07E-04 1.84E-a7 9.46E-07 1.717 nA Ci 5.81E-07

- Sr-90 _

Ci Ci 4.25E-04 3.43E-04 3 18E-04 _ 1.09E-Q.l__

TOTAL

TABLE 2.1-4 ,

MILLSTONE NUCLEAR P0k'ER STATION - UNIT #1 CASEOUS EFFLUENTS - ELEVATED RELEASE - CONTINUOUS MODE

., 0""'IIf f Aclides Released Unit lOUT l NOV DEC Total -[

1. Tission gases C1 Xe-138 C1

- k-t?-

tr-ss C1 C1 Er-85_= _._

C1 1.21 E+00- 8.39 E-01 9 37 E-01 2.99 E+00 Ze-135 2.43 E+00 5 53 E+00 T.96 2+0V fe.ly) C1 Kr-89 C1 C1

_ ]e-131 Ke-13sm Ci tr-s3m Ci Ke-133m Ci Te-131m C1 Kr-F5 _ Cf Ar-37 Ci 1.21 E+00 3.27 E+00 6.h7 E+00 1.10 E+01 fotal Fer Period C1

2. Iodines _nb p.66 v oh ,1c y nb J R.LA todine-131 C1 3.69 v-oh .

Ci 2.Th E-03 1.35 E-03 5.59 E-Oh Qh.65 E-03 todine-133

3. Particulate 3.32 E-Oh 4.87 E-05 1.h2 E-Oh 1.L1 E-Oh Cr-51 C1 l

Ci L . bh r oli b.bh r_oA

{ &-s t.

Fe-59 C1 Co-58 9.82 E-06 7.88 E-06 1.27 E-05 Ci 2.41 E-Oh, 1.09 E-04 B.61 E-05 . 56 E-05 Co-60 C1 1.30 E-Oh h.91 E-Oh 3.h5 E-OL 9.66 E-Oh 2n-65 c5 I-131 .Ci b . 9? E-0/5 _.26 E-05 1 69 E-05_=

Cs-134 C1 .

Cs-137 Cf Ba-140 C1

' no v os 1.nn r Os Ce-141 C1 Ce-144 C1 Ci

~* La-140 C1 C1

,,73 p_oq 3,3o p_oq n,qq p_nq 7,gg r_nz Sr-89 Ci C1 3.30 E-07 1.8h E-PT ' Ib E-07. 7.28 E-07 Sr-90 C1 5.8h E-Oh 1.66 E-03 TOTAL Cl Lib E-Oh 7_.,63 E-Oh

Teble 2.1-5 MILLSTONI NUCLEAR POWER STATION - UNIT f 1 CAEEOUS IFFLUENTS . RATfM MQDE Tear 88 h

[ belfdes Released l hit l_ July l August l September l 8

' NONE 1_._ Finsten gases - _

Xe-138 gg

_ f j

Er.at

_Cf N98 -

CI . _

,,,, C, _

ie-133 Cf_

C1 - :

____Kr-99 Ee-117 _

Cf _

- C1

_ _Ie-131s ~

tr-JD ~Cf =

Is-13Je C4 Ze-131m Cf Kr-85 _ Cf 21 AP-E ti fotel Far Perted

f. M (nes i Wfne-131 Ci C1 (oftne-133
3. Partfealstas '

Ci Cr-51 -

Mn-se -

Ci _

~

Te-59 ff _

co-58 Cl

~

co-60 C4 _-

20-65 . M_ -

1 1-131 Ct_

C1

_ Cs-134 _

~

Cs-13t Cf Ba-140 ' Cf Ce-141 Cf Ce-144 C1 __

y -- ct gg

_ C1

~

Ci Sr-89

- CC fr-90 -

C1_ --

Cf , __

TOTAL 1

._-___- _ __ i

Table 2.1-5 Mill 5 TONE NUCLEAR POWER ATATION - UNIT $1 CAEEOUS EFM. VENTS - RAT (5t MODE

- Year 88

[helfdesRefessed Unit l _o_ctober November December Finsten gases NONE 1._ _

Xe-138 Cf _ _ _ _

M EI __ _

tv-es Ci -

tr-ess _

Cf __ __

~

ze-135 Ci ie-111 C4 __

k-ee Ci _

16-17P _

C1 _ _ _ _

re-itse _

Ci _

p.33 Cf _

2s-113e

__ C f re-131m __ Cf

_R-f f C(

~

Ar-11 _

Cf _ _

fotti For k riod ti

t. Iodines lodine.131 Ci

~ (oft ne-133 ___ , _

Cf _

3. Particu1 stas --

( Cr-51 Cf L

Ci z-m-u te-59 t$ -

co-se _Ci _ _

Co-60 Ci___ __

Zn-65 ~- e4 _ _ _

I-131 31 Cs-134 _Ci Cs-131 Ct Ba-140 Cf Ce-141 Cf Ce-144 Ci_ _ _

    • _ _ . c1 _

~

_ Ct _

~

Ci Sr-89 jf _

Sr-90 . _Cl _ --

C1_- __

ma _

_s< _

t, TABLE 2.2-1 MILLSTONE NUCLEAR POWER STATION UNIT 2 LIQUID EFFLUENT - SUM 4ATION OF ALL RELEASES l l l l l QUARTERLY l YEAR 1988 l UNITS l JULY l AUGUST lSEPTEHBER I TOTALS l A. Fission and Activation Products l l 1 l l l l 1. TOTAL ACTIVITY RELEASED 1 Ci l 1.88-02l 9.39-021 1.28-01 l 2.41-01 l l l l l l 2. AVERAGE DILUTED ACTIVITY l- l l DURING PERIOD l UC1/ml i 1.94-10l 9.70-101 1.34-09 l 8.34-10 t B. Tri tium I I I I i i I

'l 1. TOTAL ACTIVITY RELEASED l Ci l 3.44+00 l 1.38+01l 2.51+01 l 4.23+01 l l l l l [

l 2. AVERAGE DILUTED ACTIVITY l l DURING PERIOD l UC1/ml l 3 56-08 l 1.43-07 l 2.63-07 l 1.46-07 l C. Dissolved and Entrained Gases l l l l l l l

l 1. TOTAL ACTIVITY RELEASED l C1 l 1.54-021 3.55-021 1.85-02 l 6.94-02 l l l l l l l 2. AVERAGE DILUTED ACTIVITY l l DURING PERIOD l UCi/ml l 1. 59 - 10 l 3.67-101 1.94-10 1 2.40-10 1 D. Gross Alpha i l I i i 1 l C1 l N/D l N/D l N/D l N/D l l 1. TOTAL ACTIVITY RELEASED l }

E. Volume I l l 1 l i I l 1. VOLUME OF WASTE RELEASED l LITERS l 1.52+07l 1.89+07l 2.27+07 l5.68+07 l i l l [ l l 2. VOLUME OF DILUTION DURINGl i RELEASES i LITERS l 1.29+101 1.57+101 1.10+10 1 3. 9 6+ 10 l l l l l l l 3. VOLUME OF DILUTION DURINGl l TIME PERIOD 1 LITERS I 9.67+10I o.68+10l 4.4t+1n t? R9+11 l a o,

' TABLE 2.2-1 NILLSTONE NUCLEAR POWER STATION l

UNIT 2

., LIQUID EFFLUENT - Sul44ATION OF ALL RELEASE $

l j l l IQUARTERLYl

' YEAR 1988 l UNIT 5 I OCTOBERI NOVEMBERI DECI9tBERI TOTALS I A. Fission and Activation Products

]

I I I I I l I I l 1. TOTAL ACTIVITY RELEASED l Ci 1 5.97-01-l 4.04 011 2.44-01 I- 1.25M01  !

1 l l I 2. AVERAGE DILUTED ACTIVITY l lI 7.17-09 ll 4.32-091 2.52-09 l 4.56-09_l l_ DURING PERIOD l UCi/m1 .

5. Tritium _

l l l l l I l 1 1. TOTAL ACTIVITY RELEASED l C1 1 4.01+01 1 3.73+01 1 2.25401 1 9.99+01 l l l l 2. AVERAGE DILUTED ACTIVITY l DURING PERIOD I UC1/m1 l4.81-07 g lg 3.99-07 .ll2.33-07 3.65-07 ll g {

l l C. Dissolved and Entrained Gases-i l l l l l I

l 1. TOTAL ACTIVITY RELEASED l C1 12.58-01 15.43-01-l 2.19-02 1 8.21-01 l =

l 2. AVERAGE DILUTED ACTIVITY ]

1 UCi/m1 l1 3.10-09 gl5.80-09 lg 2.26-10 lg 3.00-09 ll lL i DURING PERIOD D. Gross Alphs _

i l l l I i i Ci ILLD i LLD ILLD l tin _t l 1. TOTAL ACTIVITY RELEASED _l E. Volume l l l 1 l l l

l l 1. VOLUME OF WASTE RELEASED l LITER $ l 1.76+07 11.2B+07 l1.17+07 I 4.21+07__l l l I l

~

l 2. YOLUME OF O!LUTION DUR!!4Gl l l RELEASES 1 LITERS I9.02+09 11.19+10 11.4M10 1 3.58+10 l l l l l 1 3. YOLUME OF DILUTION DURINGl l l TIME PERIOD I LITERS I8.33+10 19.36+10 19 . 6 7_+10 12.7411 i I

TABLE 2.2-2 MILLSTONE NUCLEAR POWER STATION i

UNIT 2 '

a LIQUID EFFLUENTS - CONTINUOUS - S/G l

L '- Year 1988 1

l l l l l IQUARTERLYi l NUCt.1 DES RELEASED l UNIT l JULY I AUGUST ISEPTEMBERI TOTAL l l Cr-51 l C1 1 I I i l l Mn-54 i C1 1 l l l l l l C1 I l l l l' l Co-58 i C1 1 I I l l l Co-60 1 C1 l l 1 l l l I-131 l C1 l l l l l l I-133 i Ci l i I l l l I-135 i C1 l l l l l l Cs-134 i C1 l l 1 l l l Cs-137 i C1 l l l l l l l Ci l I i l l l Co-141 l C1 l l l l l l Ce-144 i C1 l l l 1 l l Zn-65 i 'C1 l l l l l l Fe-59 l C1 l l l I l l SR 89 i C1 l l 1 l l l SR 90 i C1 i l l l l l Total Act (F/A) l C1 l l l I l l H-3 i Ci i 1.35-01 1 2.06-01 13.00-01 16.41-01 l l Gross a l C1 l l l l l i l l 1 I I I _,,_ l l l i l l I l l l C1 1 I I I l l l C1 1 I I l l l l Ci l 1 I l l l Xe-133 l Ci i I I I l l Xe-131 l C1 l l l l l l Xe-135 1 C1 1 I I l l l Xe-135M l C1 1 I I I l l l C1 l l l l l l C1 I l l_ l l 1 l Total Dis Gas I C1 l l l l l

  • e i

i

TABLE 2.2-2

.o i MILLSTONE NUCLEAR POWER STATION

- UNIT 3 LIQUID EFFLUENTS - CONTINUOUS - 8/G Year 1988 i I. l l l lQUARTERLYl-NUCLIDE$ RELEASED l UNIT l OCTOBER - 1 NOVEMBER l DECDCBERI TOT _AL 1 l

l Cr-51 l Ci l 1 i 1 l Nn-54 1 Ci i l i i _l l

l l An-110M Ci i 1.62-02 1 1 1 1.62-02 l l Co-58 il C1 1 8.78-04 1 1 1 8.78-04 l l Co-60 1 C' I 3.46-04 I I l 3. 46-04__ l l__ I-131 1 CC I 1.25-02 i 1 i 1.25-02 l l I-133 i C1 1 7.35-03 1 1 1 7.33-03 l l l _Rn 106 i C1 1 1.01-02 I I i 1.01-02-l 1 l Cs-154 i C1 1 1.95-02 1 5.14-04 1 1 2.00-02 l l Cs-137 i C1 1 2.30-of I I I 2.30-02 l l I-132 i Ci 1 0.07-.04 i i 1 0.07-04_l l Sr 92 l C1 1 E.70-02 1 I i 5.79-03 l Co-144 1- Ci i i l l l l

j Nb-97 1 C1 1 2.27-02 l i I 2.27 n2 l Fe-59 i C1 1 I I I l l

SR 89 i Ci I l- 1 I l l ~ ~

1 _st 90 1 Ci i i i l l l l Total Act (F/A) l C1 1 1.10-01 1 4.14-oa 1 1 1.in n1 l l H-3 1 CT l A.1A-01 1 1.4A-01 1 1.La-01 1 7.10 n1 l

-Gross e l C1 1 1 1 l l l

l 1 1- 1 i l l c 1 1 l l _. l

[ ] l l l l l

l l _I i 1 1 I l 1 l l _. l l 3 j

l Xe-138 i Ci i 2.26-03 1 1 2.26-03 1 j xe-131 ~ l C1 i i i_ i __l l Xe-135 i C1 1 1.31-03 1 I i 1.31-03 l l Xe-13SM 1 C1 il I _

1 1 _l i C1 l 1 1 1 l I _

l C1 1 1 1 1 ___ l l

l Total Dis Gas 1 Ci I 3.57-03 I I i 3.s7-03 l

l. ,

l'

  • l l

TABLE 2.2-3 MILLSTONE NUCLEAR POWER STATION UNIT 2 r r LIQUID EFFLUENTS - BATCH - AWMT/CWMT/TK10 AND TK11

- Year 1988 l l lQUARTERLYi l l l l AUGUST ISEPTEMBERI TOTAL _l l NUCLIOES RELEASED l UNIT l JULY Cr-51 l C1 I 9.49-05 l'2.84-03 12.67-04 13.20-03 _l l 1 3.97-04 12.03-04 16.23-04 _l l Mn-54 i C1 1 2.29-05 13.10-01 l La-141 l C1 1 6.61-04 1 1.43-03 11.01-03 l 1 6.79-03 13.75-03 11.31-07 l Co-58 i C1 1 2.57-03 l

Ci I 4.04-03 1 3.52-02 11.92-02 15.84-07 _I Co-60 i l

Ci 1 5.23-04 1 5.4R-04 13.15-05 11.10-n1 _l l I-131 1 11 R4-01 _l I-133 i C1 1 3.67-04 1 1.66-04 1 l i l i Ci i l 1 l I-135 l? 11-n? l Cs-134 i Ci l 1.11-05 1 1.64-04 l? 77 0?

l 1 3.58-03 15.50-02 15.50-02 l l Cs-137 i C1 1 8.83-04 14.31.04 l NA-24 I C1 1 6.34-05 1 2.50-04 11.18-04 l I l l C1 l l l Co-141 1 l l _l i C1 l l l Ce-144 l l _l C1 1 Zn-65 l 1

_l l

Ci l I l l l Fe-59 I 11.28-04 _I N8-95 i Ci I 7.38-05 l 9.20-04 12.89-04 l l i l i BA-139 I C1 l 1 l 1 l 1 BA-140 i C1 1 l l 1.19-02 15.29-03 12.15-02__l SB-124 l C1 1 4.27-03 11.47-07 l l 1 1.76-02 11.30-02 58-125 i C1 1 4.12-03 l l l l l Co-57 I C1 l l l 1.31-03 11.12-03 12.67-n1 l AG-110M 1 C1 1 2.43-04 14.67 n1 _l l l 2.07-03 11. R S-01 N8-97 i Ci 1 7.04-04 19.55-04 _l l 1 4.74-04 13.63-04 SR-92 l C1 1 1.13-04 l l l l l l LA-140 i C1 l 1 l l 1 l l l l I I i i I I _l l I I I I l SR-89 l l _l l l I l SR-90 11.67 0? l l l l 8.14-03 1R.06-03 l Fe-55 1 9.39-02 11.2R-01 19.41-n1 _l Total F/A Prod. I l 1.88-02 l

  • 4

b

-TABLE 2.2 h, MILLSTONE NUCLEAR. POWER STATION UNIT 2.

l-- .,

^

LIQUID EFFLUENTS - BATCH - AWMT/CWMT/TK10/11

( 1988-L *.. . Year i

l, 1 IQUARTERLYl I l i l AUGUST lSEPTEMBERI TOTAL _l-I UNIT I JULY l NUCLIDES RELEASED i

y i l i I I Xe 131 1 Ci i I I I _l Me 131M I C1 1 l 1 2.67-02 11.83-02 15.67-02 1-

-l Xe 133 1- C1 1 1.17-02 17.0R-01 __f Xe 135 i C1 1 3.67-03 1 3.24-03'11.73-04

! I I I _l l Xe 135M i C1 1 15.23-04 l Xe 133M l C1 l- l 5.23-04 1 l l i 5.00-03 1 15.00-03 l Kr 85 i C1 I l 1 l l

-l C1 l l

.l l C1 1 I I I l l I i l C1 1 l

l 1 l l l l.

l 1- C1 I l l-I l C1- l- 1

_l l 1 1 1 1 C1 1 I- C1 I i l i _l 1

l I i l 1 C1 l l l I I l l C1 I I l i l l C1 I l

[ 1 i i l, I Ci i 1

_l l 1 1 I l C1 l l l I I i l' 1 C1 1 I l l C1 I l- 1 l I I _l 1 C1 1 I l I l l l Cl- 1 I 16.94-02 l l 1 3.55-02-11.85-02 i C1 1 1.54-02 l Total Dissolved Gas 1 1.36+01 12.48+01 14.17+01 l H l Ci I 3.33+00 I l l I I Gross a I C1 1

_l l I I 1- I 1 i I l 1 I l l i l I I I I l

1 I i l 1 C1 1 I l

4' i

i m,

TABLE 2.2-3 MILL 5 TONE NUCLEAR POWER STATION UNIT 2 LIQUID EFFLUENTS - BATCH - AWMT/CWMT/TK10 AND TK11 Year 1988

.j .

j l l l lQUARIERLYl l NUCLIDES RELEASED 1 UNIT l OCTOBER I NOVmarni nrt mman! TOTAL __l Cr=61 C1 1 1 i l i 1 1 l Mn=54 i C1 1 9.43_-05 l 1.81-03 l 1.31-03 3.21-03'l l

na-z'+ l C1 -1 1 1.49-04 1 4 1. 49-04 l l 'Co-SS I C1 1 2.67-03 1 1.35-02 1 7.01-03 1 2.32-02 l l Co 1 C1 i_1.36-02 l 2.96-02 1 5.32-02 1 9.61-02 l l I-131 1 C1 1 6.8443 1 3.71-03 1 3.01-04 1 1.09-02 l l

1 1.88-03 1 3.98-03 1 3.09-05 1 5. 89-03 _ l

~

l~ I-133 l C1 l -!-135 i C1 I i 1.11-03 1 1 1.11-03-1

~

I Cs-134 i C1 1 1.26-01 -l 1.54-04 1 5.41-02 1 1. s0-01_l 1 2.99-01 1 3.46-01 1 1.05-01 1 7.50-01 l l ~Cs-137 - I C1 C1- l 3.47-04 1 6.51-04 1 1 9. 92 l l- _

1 l C1 i i 1 -I _l l Co-14_1 -

Co-144 i C1 l l l 1 1 l

1 Tc 99M I C1 1 1 3.31-05 1 1 1.11-ns l l Fe 1 C1 1. I i 1 _

l l NS-99 _

l C1 1 2.81-04 1 12.64-04 1 5.65-04_f i BA-139 i C1. I 1 1 1

1 i

__ l l

l BA-140 1 C1 1 1 1 $8-124 i C1 1 6.47-04 1 1 6.a7-na l~

l 58-135 i Ci i1.56-02 11.56-03 11.15-03 u1.ns-n9 l l Co-87 1 C1 1 1 -l4.si-05 iA.O ns l l_ AD-110M i ci i 1.44-03 J l 5.66-na 12.ns-nt _l l NS-97 i C1 1 2.48-03 11.59-04 11.20-03 I t.e nt l l 5R-92 l C1 13.96-04 11.72-05 12.3R-04 l K 51 nLl LA-140 1 Ct _ 1 1 1 1 _ l l

l I-132 i C1 1 17.30-05 1 1 i in-nq _l l l l 1 1 _l l

l $ R-89 _ i C1 i i i1.21 04 1- l

. l 5R-90 1 G1 1 I i i l Fe-SS. I C1 16.97-03 I I I _- l l

l Total F/A Prod. I 14.78-01 14.03-01 12.24-01 11.114an !

, i J

p q

]

1

TABLE 2.2-3 MILLSTONE NUCLEAR POWER STATION-UNIT 2 l'

LIQUID EFFLUENTS - BATCH - AWMT/ CWT /TK10/11 Year 1988_

l 1 IquARTERLYl

! l

, l .

l -NUCLIDES RELEASED l UNIT 1 ocTourm I wovrwarmi nrrrMarni TOTAL _l l_ 1 l l No 131 l C1- 1 I No 181M i C1 1 1.13-02 1 1 1.42-03 1 2.55-03_t l

Xe 133 i C1 1 2.02-01 1 5 22-01 1 1.96-02 1 7.44-01-l i

No 135 I C1 1 3.73-03 1 1.23-02 1 8 56-04 11.6' I-02 l l

i C1 I i 1 to_n, 1_ 11.5' l-03 l 1 _ ___ 'No 135M 17.6 L-03 l Ke 133M_ l C1 1 2.58-03 1 5.10-03 1 l

Kr 85 i Ci l- 4.44-4 2 1 1 14.40-02 l l

Kr 85M i C1  ;) 1 6.54-05 1 1 6.54-05 l l i 1 l 1 C1 1 I l i i l I C1 i i l'

l .,_.

I I C1 1__ l 1 l i l l C1, I l 1 l

l C1 1 _

i i i __ l l 1 1 l 1 C1 1 1 l

i i i l l J C1 l i

l l Ci 1 i i l I l l 1 C1 1 1-l I I i 1

1 C1 1 l 1 I I I C1 1 1 l 1- 1 1 1 i 1 C1 1 l_ I I i __ l l C1 1 l I i __l 1 C1 I I l____ l 1 l 1 C1 1 J l

l Total Dissolved Gas l C1 1 2.s4-01 1 5.41-01 1 2.19-o2 Ia.17-oL_I l l

I C1 1 3.97401 1 1. 72401 - l 2. '14+01 1 0. 0 %n i l l H-3 l l l Gross a 1 C1 1 1 1 _l _ _ _

l 1 1 I i 1 l

l l l l ._ I 1

l I I i -_ I 1 1 i l 1 l

' '

  • l 1 1

. l

TABLE 2.2-4 MILLSTONE NUCLEAR POWER STATIDN UNIT 2 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l l l l IQUARTERLYl YEAR 1988 l UNITS _l JULY l AUGUST l SEPTEMBER TOTALS l i A. Fission and Activation Gases l l l l l l l l l_1. TOTAL ACTIVITY RELEASED I C1 1 1.60+011 7.23+01 1 3.08+01 l 1.19Et02 l l l 2. AVERAGE RELEASE RATE FOR l l l l l l l THE PERIOD l UC1/see 1 6.61 1 2.99+01 l 1.02+01 11.51+01 l l l

B. Iodines l 1. TOTAL I-131 ACTIVITY l l l l l l l RELEASED l Ci l 9.82-04 1 6.43-04 1 7.75-04 12.40-03 l l 2. AVERAGE RELEASE RATE l l l l l l l FOR THE PERIOD l UCf/sec l 4.06-04 1 2.66-04 l 2.57-04 13.05-04 l C. Particulate l 1. TOTAL PARTICULATE l i~ l l l l l ACTIVITY RELEASED I Ci l N/D l N/D i N/D l N/D __l l 2. AVERAGE RELEASE RATE FOR l l l l l l l THE PERIOD l UC1/sec l N/D l N/D l N/D i N/D l l 3. TOTAL GROSS ALPHA l l l l l l l ACTIVITY RELEASED l Ci i N/D i N/D l N/D l N/D l D. Tritium l l l l l l l l 1. TOTAL ACTIVITY RELEASED I C1 1 8.50 l 6.63 1 1.95+01 13.46+01 l i l 2. AVERAGE RELEASE RATE FOR l l l l l l l THE PERIOD I UC1/sec l 3.51 l 2.74 l 6.46 l4.40 l

_ - _ _ w

TABLE 2.2-4 MILLSTONE NUCLEAR POWER STATION 1

O . UNIT 2  :

GASEOUS EFFLUENTS - $U194ATION OF ALL RELEASES l l l l 140ARTERLYl YEAR 1988 l UNITS iOCTOBER j_NOVEMBEM DEC19fBER1 TOTALS I l

A. Fission and Activation Gases __

i l i i I l .. l l 1. TOTAL' ACTIVITY RELEASED l C1 I 6.87-01 15.31+01 1 3.98+01 1 1.02+02 l l 2. AVERAGE RELEASE RATE FOR l l l 1 l -l l THE PERIOD -

'l Uci/soe i 1.14+01 12.19+01 11.64H11 1 ' 2.06+01 i B. Todines -

i~1. TOTAL I-131 ACTIVITY l .l l l l l l __R ELEASED 1 Ci i 1.44-03 15.07-04 I L22-oa i 2.27 n1 l l 2. AVERAGE RELEASE RATE l l :l l . I l l FOR THE PERIOD 1 UCi/ set 1 4.77-04 l2.10-04 l1.33_-04 1 2.89-04 l.

C. Particulate ___  ;

i 1. TOTAL PARTICULATE l l l l l l l ACTIVITY RELEASED l Ci i 1 26-06 1 4.50-07 lLLD l _1. 71-06 l l 2. AVERAGE RELEASE RATE FOR l l .I i l l l- THE_ PERIOD __

i UCf/see 1 4.17-07 11.86-07 ILLD l 2.18-07 l l 3. TOTAL Gross ALPHA l l l l l l l ACT!VITY RELEASED 'l Cl I LLD ILLD l LLD _ l LLp l D. Tritium i I l l l I i l 1._ TOTAL ACTIVITY RELEASED I Ci i 3.18 l_3.64 13.79 1 1.06+01_l 1 2. AVERAGE RELEASE RATE FOR I l l l l l l THE PERIOD l UC1/see i 1.05 11.50 11.57 1 1.35 l

'1 e,

!O. f mem.

c 'j l

TABLE 2.2-5 1 MILLSTONE NUCLEAR POWER STATION - UNIT 2 l

GASEOUS EFFLUENTS - MIXED RELEASE - CONTINUOUS MODE -l

?

.. )

Year 1988 q l

l l l l l (Quarterlyl i Fission Gas i Unit i JULY l A.UGUST l SEPTEMBER Total l l Xe 133 I C1 11.56+01 1 6.82+01 1 3.01401 11.14+06 l l Xe 135 i C1 1 4.05-01 1 4.11+00 1 6.11-01 1 5.13+00 l l Xe 131M l C1 l l l l l l Xe 135M I C1 1 I l l l Kr 85 l C1 I I I l l l

l l C1 l l l l l l l Ci I l 1 l l l C1 l l l l l l

l l Ci i l 1 l l l l C1 l l l l l ,

I l C1 1 I l l l l l C1 1 1 I l l l l C1 l l l l l l C1 I l l l l l

l Total for Period 1 Ci i1.60+01 17.23+01 13.0B+01 11.1o+n? l

2. Iodines l Iodine-131 l C1 13.32-04 12.70-04 13.20-04 14.77-06 1 l Iodine-133 i C1 16.50-04 13.13-04 14.55-04 11.48-03 l l C1 l l l l l l

l Total Iodine l C1 19.82-04 16.43-04 17.75-04 12.40-n1 1

3. Particulate Mn-54 l C1 l l l l l l

Fe-59 i C1 l l l l l l

Co-58 i C1 I l l l [

l j Co-60 1 C1 I i 1- l l I-131 1 C1 l l l 1 l l

Cs-134 l C1 l l l l l l

Cs-137 i C1 1 I I I l l

l l l Sr 89 I C1 I l l Sr 90 i C1 l l l l l l

Total I C1 1 I I I l l

H-3 l C1 18.50-00 16.63 11. 95+01 13.46+01 l l

Gross a. I C1 1 I i *l l l

l l 1 L l  !

l l l 1 I .-.l . l l

C1 1 I I I l

. . I I

- l C1 1 I I I l l

d -

ei TABLE 2.2-5 MILL 5 TONE NUCLEAR POWER STATION - UNIT.2' s

GASECU$ EFFLUENTS - Mixed RELEASE - CONTINUOU$ MODE

. . .  ; 1 i l l

Year' 1988 l l l l l l (Quarterlyl I NOVrMarni nrrtMarni- Total l l Fission Gas. I Unit i OCTOBER l Me 133 i C1 '

6.54+01 1 4.A1+011 1.7fu.611 1.412 9 l

-l Xe 138 1 C1 1.10400 I s.024nn1 2 Toen i 1. iru.n1 l 1 l Xe 131M i C1 1 I I i -l-l _Xe 13SM l C1 1 1 '1 1 _

__l l Kr 88 i C1 1 1' i 1.24-011 1.24-01 l l l C1 1 1 1 1

___ l l l C1 1 1 1 1 l l 1 C1 1 -1 1 I l l l C1 1 1 1 J _l' l l C1 I l' i I .l l l C1 1 1 i i _

l l l C1 1 1 I i _l

l. 1 C1 1 1 1 I l l i C1 1 1 I I l l __ _ Total for Period 1 Ci 1 6.87401 1 5.11401 1 1. e A+01 1 1. A94 tie i
2. Iodines l Iodine-131 l C1 15.34-04 1 3.90-041 1.36-0411.06-01 1-l~ fodine-133 i Ci I9.02-da i 1.17.na1 1 ma nt i 1 si ns l l l Iodine Via SG Vent 1 C1 13.09-07 l 1 13.09-07 l 1 l Total fodine 1 C1 L 1.44-03 1 5.07-04 1 3.22-04 12.27-n1 l l
3. Particulate 1

l Mn-54 1 C1 1 l l 1 _

i {

Fe-89 i C1 1 i i 1 l '!

l l Co-SS I C1 1 1 1 I l l Co-60 1 C1 1 1 1 i i i 1-131 l C1 _ 11.26-06 1 1 1 1. 26-06 _ l ,

i .Cs-134 ~1 C1 l l l l 1 l Cs-137 1 C1 i I 4.50-07 I I4.50-07 i l Sr 89 I C1 1 1 1 1 _ l  !

l Sr 90 1 C1 1 1 l I _

l .

l Total 1 C1. I1.26-06 1 4.50-07 1 11.71-06 l  !

l H-3 C1 13.18+00 1 3.64+00 1 3.79+0D 11.06+01- l l_ _ _ Gross s._ i C1 I i 1 1 _

.1 l Tota) Vol. I cc 1 1.10+14 1 7. 28+13 1 6. 71+13 12. 50+14 .1

, , l Time leec3 -1 l3.02+06 1 2.42+06 l' 2.62+n6 17_aA4nA l i

1 i C1 1 I 1 i i C1 i i i i 1 l_

1 l

[T i'

TABLE 2.2-6 MILLSTONE NUCLEAR POWER STATION - UNIT 2 1

GASEOUS EFFLUENTS - MIXED RELEASE - BATCH MODE - CONTAINMENT PURGE Year 1988 l l l l IQuarterlyl I

l Nuclides Released i Unit i JULY l AUGUST lSEPTEMBERI Total l NONE

1. Fission cases Xe 133 1 Ci l l l l l l

Xe 135 l C1 l l 1 I l l

Xe 131M l C1: l l l l l l

Xe 133M I C1 l l l l [

1 Kr-85 i C1 l l l l l l

l C1 l l l l l

-1 l C1 l l l l l l

I C1 l l l 1 l l

l Ci i I l l l l

l 1 C1 l l l l l l C1 l l l l l l

l C1 l l l l l l

l C1 I l l l l l

l C1 l l l l l l

l C1 l l l l l Total Gas 1

2. Iodines l 1 l l Iodine-131 l C1 l l l l l l Iodine-133 l C1 l l l C1 I I I l l Total Iodine 1
3. Particulate _

l I l l Cr-51 l C1 l 1 l l l l l Mn-54 l C1 l l l l l Fe-59 I C1 l l l 1 I l l Co-58 l C1 l Ci l I I l l Co-60 1 l l l l l Zn-65 I C1 l l l l l l I-131 l C1 l 1

_l l 1 1 l Cs-134 l C1 l I I I l l Cs-137 l C1 I l l l l l l C1 l I l 1 I l l C1 1 i l I l l l Ci I

,,L , 1 l l Total Part l C1 l 1 l l l l .l

.'. l l i _ __ j.,_, f _l l Total H3 l C1 I l l 1 __ l l 1 C1 l 1 1  !

., I I C1 1 ,,

1

TABLE 2.2-6 MILLSTONE NUCLEAR POWER STATION - UNIT 2 s

GA5E005 EFFLUENTS - Mixed RELEASE - BATCN NODE - CONTA! WENT PURGE Year 1988 I. I I I l iguartertyl l Nuc1 ides Released i Unit i OCTOBER g NOVEMBERg DECEMBERf Total l NONE

_1, Fission asses l Xe 133 1 C1 I i 1 I __ l -

I Xe 135 i C1 I l- 1 i -

l l Xe 13_1M- 1 C1 1 1 I J _l l Xs 133M i C1 l l- _ l I l l Kr-85 i Ci i i 1 l l-1 I C1 1 I I i 1 1 1 Ci i i i i _

l 1 l C1 1 i i 1 -l l l C1 1 I H I l

l. _

1 C1 1 I L i _

--l l l C1 1 I I I I l l C1 l- I l_ ~l -

l l l Ci l 1 __ 1 l l l 1 C1 1 I l l l l- Total Gas l C1 1 I i 1 l

2. Iodines l Iodine-131 l C1 1 1 1 1 l

l fodine-133 - 1 C1 l l 1 l l l Total fod ne i C1 1

__ _ l I i _

l

3. Particulate l Cr-51 1 C1 1 1 1 1 l l Mn-54 1 C1 I l l l _

l l Fe-89 l ci 1 i I i _l 1 Co-5s . I C1 1 1 1 1 I I -co-80 i ci I i i _1 l l__ Zn-ss 1 C1 I I i 1 _l l 1-131 l C1 1 i l- I _l l Cs-134 i ci i i i 1 l

l. Cs-137 i C1 1 1 1 1. l l l l Ci i i i I l i 1 C1 1 I i 1 l-l 1 C1 ~ l l I I ~

l

..,'

  • i Tets) Part I C1 J l i 1 1 l, - 1 1_ l i I l l Total H3 i C1 1 I I l I c l l Cf I I I I l I I C1 1 1 1 1 l

.________--__--__--_-----_-__a

s

-TABLE 2.2-7

.q MILLSTONE NUCLEAR POWER STATION - UNIT 2 GASEOUS EFFLUENTS -ELEVATEDRELEASE - BATCH MODE - WGDT -

c..

l Year 1988

.1~ .

! l 1 l IQuarterlyl

- l Nuclides Released l l JULY l AUGUST ISEPTEMBERI Total l

-1. Fission Gases 1 -Xe-131M i C1 1 5.46-02 1 1.05-02 1 1 6.51-02 l-I Xe 133 i C1 1 1.38+00 1 1.06+00 I i 2.44+00 l

[ l Xe 133M i C1 l- 1 1- l l l Xe 135- 1 C1 1 1 1 1 l-l Xe 135M I C1 I I I i 1 1- Kr 85 i 'C1 1 6.33-01 1 1.79-01 1 l'8.12-Ol'l

-l I C1 1 I I I __

l l l C* I I I I I l l C1 1 I I i 1. l l l C1- 1 I I I l

-l I C1 l l l 1 l-l- 1 C1 1 1 I l l l -l C1 1 I i l l l l C1 1 I I I i l l C1 l l 1 l, i l Total for Period l C1 1 2 07+00 1 1.25+00 l l 1132+00 l i i l I I i l l l l l l 1 l l H-3 i Ci l 1.93-04 l 1.30-03 l l 1.49-03 l' r

+. '

i - _- _

t

., TABLE 2.2-7 MILLSTONE NUCLEAR POWER STATION - UNIT 2 GASEQUS EFFLUENTS -ElevatedRELEASE - BATCH MOD'E. - WGDT Year 10AA

~ ~

l l l l l l Quarter 1yl l Nuc11dep Roleased I i OCTOBER 1 NOVEMBERIDECEMBER l Total-_j

1. Fission Gases l_ Xe-131M l Ci 1 4.66-03 i I 8.24-031 1.29-02 l 1 Xe 133 i C1 1 2.23-02 l I 4.05-021 6.28-02 l 1 Xe 133M i C1 1 1 1 3.27-041 3.21-04 l l Xe 135 I C1 1 1 1 6.35-041 6.15-04 l l Xe 135M  ! C1 I i i I l l Kr 85 ___ i C1 1 7.37-02 I i 1.25-011 1.99-01 l l Kr 85M I Ci J l i 1.56-051 1.56-05 l l l C1 1 I I J _

l l 1 Ci i i i l l l l C1 1 _l i I l l l C1 l l l t l l l C1 __ i __ l 1 i l l l C _1 l I i I l l l C1 I i i I .l l l C1 i i i __

l l l Total for Period l Ci l 1.01-01 I i 1.75-011 2.7_A-n1 l l 1 l _ l _ l I l l l I - 1 I I l l HS I c1 I 5.38-05 I i 1. 49-03 1 1. 5_4-0 3-- l 1

_ _ _ _ _ _ _ _ _ - - . _ _ _ _ _ _ . - - - _ - _ _ , _ _ _ _ _ . _ _ - _ _ - a

c TABLE 2.3-1 MILLSTONE UNIT No. 3 p SUMMATION OF LIQUID EFFLUENT RELEASES'-

e, QUARTERLY III TOTALS JULY AUGUST SEPTEMBER YEAR 1988

'A. Fission and Activation Products Ci '1.56E-01 3.52E-02 1.14E-01 3.05E R SED UCi/a1 9.56E-10 '2.21E 7. 40E- 10 6.46E UR N PERIOD B. Tritium 1., TOTAL ACTIVITY-Ci 16.14 43.5- 35.5 95.1 RELEASED

  • fe$,h 3$pggron UC1/mi 1.02E-07 2.74E-07 2 3tE-07 2.01E-07 C. Dissolved and Entrained Cases
1. TOTAL ACTIVITY Ci RELEASED 3.77E-03-- 2.19E-03 1.48E-03 7.44E-03:

I C 7Y PERIOD

.i D. Gross Alpha

1. TOTAL ACTIVITY Ci 4MDA 4MDA 4 MDA 4 MDA RELEASED

'E. Volume

1. VOLUME OF WASTE LITERS 1.8BE+06 1.59EM 6 1.49E+06 4.96E+06 RELEASED 2*'Y LITERS 1.29E+10 1.09E+10 8.84E+09 3.26E+10 D E go LITERS 1.59E+11 1.59E+11 1.54E+11 4.72E+'l

TABLE 2.3-1 MILLSTONE WIT No. 3 SUMMATION OF LIQUID ITFLUENT RELEASE 8 a ,

OCTOBER NOVDIBER DECEMBER gg WIT 5 TEAR 1988 i4 A. Fission and Activation Products 7.54E-02 6.64E-01

. O AcIM Ci 3.52E-01 2.37E-01 ggygp 1.98E-09 5.76E-10 1.70E-09

2. ave Dn pCi/mi 2.51E-09 gg p pgg gp _

B. Tritium

1. TOTAL ACTIVITY .C1 87.4 70 2 275.6 1.18E+02 ggtgAsgo 2.. AVEMCE DILVIED UCi/mi 7.28E-07 5.36E-07 7.05E-07 8.43E-07 ACTIVITY DURING PERIOD C. Dissolved and Entrained Cases 3 09E-03 4.61E-0'3 1.07E-02 I I A Ci 3.03E-02 D

3.52E-11 2.74E-11

2. AVERACE DILUTED D 1/81 2.16E-10 2.58E-11 ACIIVITY DURING PERIOD D. Orces Alpha 4HDA  % MDA I* I ^ Ci 4 HDA 4 MDA 5ED
2. volves 4.85EM 6 f i 1.75E+06 1.599E+C6 1.49BE4C6
1. V UME F WASTE LITERS 1.069E+10 1.074E+10 3.51E+10 0 0 LITERS 1.37E+10 pg 9 1.31E-11 3.91E-11 1.40E-11 1.20E-11 l
    • 3. VOLUME OF DILUTION LITER $

, g DURING TIME PERIOD __

TABLE 2.3-2 MILLSTONE UNIT No. 3 D FMMS - COMMOUS Year 1988 STEAM GENERATOR BLOWDOWN Unit July August September **(17 Nuclideo Released NONE  :

Cr-51 Ci Mn-54 Ci B Tc-99M Ci .

Co-58 Ci Co-60 Ci I-131 Ci 1-133 Ci 1-135 Ci Ci Cs-134 Cs-137 Ci Mo-99 c, Ce-141 eg Cc-144 Ci Zn-65 cs Te-59 c1_

c4 C1 C1 C1 Ci Te-55 Ci Sr-89 Ci Sr-90 Cf

._ Total Activity Ci Xe-133 eg Ye-135 Ci

  • . Xe-135M et Ci

' Ci H-3 Ci l

1 1'

l _ - _ _ _ _ _ _

l l

TABLE 2.3-2 MILLSTONE UNIT No. 3 1,1 QUID EFFLUENTS - CONTINUQUE Yser 1988 2 STEAM GENERATOR 3 LOWDOWN Nuclides Released Dait OCTOBER NOVEMBER DECEMBER ",#d*,Y_

NONE Cr-51 C1 __

Mn-54 Ci _ _

Tc-99H Ci _

Co-58 C1 Co-60 C1 1-131 C1 _ _ _

I-133 Ci 2-135 C1 Cs-134 Ci __

Cs-137 Ci _

Me-99 et Co-141 eg _

to-1LL Ci -

In-65 et Fe-59 et _

c4 _

Ci __ -

Ci _

Ci -

Ci Fe-35 eg _ _

Sr-89 __

eg gr.co ci -

=

Tota _1 Activity Ci _

Xe-133 et re-lis Ci --

- Xe-135M C1 C1 --

C1 -

M-3 eg --

-TABLE 2.3 MILLSTONE UNIT No. 3 Year 1988 LIQUID RAD WASTE EFFLUENTS - BATCH - LWS Y

JULY AUGUST SEPTEMBER Nuclides Released- Unit C1- I cr-51 2.5E-02 2.86E-03 1.780E-02 4.566E-02 Mn-54 C1 C1 2.24E-05 4.710E-05 6.95E-05 Te-99M Ci 3.76E-02 5.13E-03 1.44E-02 5.713E-02 Co-58 3.64E-02 1.06E-02 1.80E-02 6.500E-02 Co-60 Ci 1.48E-03 2.272E-03 7.482E-03 1-131 Ci 3.73E-03 Ci 3.8E-04 5.286E-04 9.086E-04 1-133 Ci 3.8E-04 3.197E-04 6.997E-04 I-135 Ci - 9.54E-03 2.78E-03 1.269E-02 2.501E-02 Cs-134 C1 1.49E-02 4.45E-03 2.137E-02 4.072E-02 Cs-137 Mo-99 eg Ce-141 eg ce.144 cf In-65 et 1.690F-0; Fe-59 ci 1.69E-05 4.07E-03 3.676E-03 7.746E-03 Na-24 ci 2.53E-03 4.16E-04 1.708E-03 4.654E-03 Nb-97 ci 4.8E-04 3.4E-05 1.393E-04 6.533E-04 Co-57 cs 1.17E-03 1.04E-04 2.493E-04 1.523E-03 Nb-95 Cf '

1.650E-03_

Rb-88 Ci 1.65E-03 3.99E-03 1.79E-02 3.3E-02 __

Fe-55 eg 1.11E-02 (MDA Sr-89 Ci 6.5.66E-05 $4.78E-05 65.96E-05 61.49E-05 4MDA Cf  :.1. 89E-05 69.56E-06 Sr-90 See Page 2 ci 1.45E 5_.628E-04 4.101r n1 Xe-133 Cs 2.09E-03 7.28E-04 8.039E-04 2.902E-03_

  • Cf 1.37E-03

. Xe-135 1.059E-04 2.669E-04 Xe-135M eg 1.61E-04 1.2E-05 2.842E-06 1.16RE-04

  • Kr=85M Cf 1.02E-04

, 5.15E-05 Kr-87 Ci 5.15E-05 2.19E-03 :1.48E-03 7.44E-03 Total Ci , 3.77E-03

t

[ TABLE 2.3-3 MILLSTONE UNIT No. 3 .

Year __

1988 LIQUID RAD WASTE ETTLUENTS - BATCH - LVS

  • j I  ?'

AUGUST SEPTEMBER Unit JULY Nuclides Released o.

1.29E-04 r Ci 1.29E-04 '

Y-88 2.976E-03 Ci 1.85E-03 1.12E-03 6.149E-06 a:

Sb-125 3.19E-04 6.78E-04 dr-yz Ci 3.59E-04

  • 3.599E-05 1.43E-04 Ci 1.07E-04 I-132 3.79E-04__

Zr-95 Ci 3.79E-04 7.355E-04 7.35SE-04 Ag-110M C1.

Ci C1 C1 Ci ci ci Ci Ci I cf Ci Ci Ci .

Ci __.

C1 Ci 1.14E-01 3.05E-01_.

1.56E-01 3.52E-02 Total Activity Ci 4 MDA 4 MDA _ _ _

Ci 4MDA 4MDA Gross Alpha Xe-133 cg Ye-135 Ci

    • Xe-135M eg Ci
    • Ci a-

'35.47 95 11 H-3 I ci 16.14 43.5 l

TABLE 2.3-3 i

WILLSTONE UNIT No. 3 Year 1988 LIQUID RAD WASTE EFFLUENTS - RATCE - LWS

., Quarterly OCTOBER NOVEMBER DECDfBER Unit .raras Nuclides Released i

cr-51 Ci 3.153E-02 8.466E-03 6.11E-02 Mn-54 C1 2.lb8_-02 E Ci 9.707E-03 2.166E-04 4.08E-05 2.P_6E-03 Tc.99M __

C1 1.968E-02 4.870E-02 8.84E-03 7.72E-02 Co-58 Ci 7.376E-02 2.28E-02 1.45E-01 Co-60 4.896E_-02 Ci 1.086E-01 2.856E-02 1.323E-03 1.38E-01 2-131 1-133 Ci 2.521E-03 6.636E-05 --------- 2.59E-03 1 135 Ci _

Cs-134 C1 2.427E-02 8.165E-0j 1.72E-03 3.42E-02 6.26E-02

~

Cs-137 C1 4.469E-02 1.464E-M_

3.28E-03 4 x,-,, c1 _

Ce-141 e, _

c .its ei _

In-65 ci 2.12 0E-04__ _

2.12E-04 Te-59 eg _,

1.3_65E-03 1.2_62 E-03 1.38E-04 2.78E-03 Nb-95 cf 5.342E-03 5.734E-03 3.142_E-03 1.42E-02 Nb-97 ci _

1.805E-04 4.932E-04 4.56E-04 1.13E-03 i Sb-125 et 3.727E-04 5.683E-04 1.60E-06 9.43E-04 Co-57 eg _

3.452E-03 2.577E-03 1.82E-03 _ 7.85E-03 An-110M _Cf 1.58E-02 1.47E-02 2.25E-02 5.30E-02 To-55 c3 _

Sr-89 eg 1.17E-04 4.64E-05 47.49E-05_ _2.38E-04 ci bl.75E-05 11.44E-05 63.00E-05 t. 6.19E-05 Er-90_ __

    • #E" ci - _

2.828E-03 1.02E-03 2.67E-02 Xe-133 et 2d88E-02 et 4.787E-03 2.592E- 4 5.06E-04 5.55E-03_

y. 133 -------
x. 135x ci Ci 2.670E-03 - ------- -- - - 2.67E-03 Xe-131M 3.03E-02 3.09E-03 4.61E-03 1.07E-02_

Total ci __

117.9 87.37 70.2  :

275.5 H-3 eg

TABLE 2.3-3 M'ILLSTONE UNIT M2. 3 Ysar 1988 LIQUID RAD WASTE EFFLUENTS - BATCH - LWS

'a Nuclides Ralsased Unit DCTOBER NOVEMBER DECEMBER 8'(17

Mo-99 Ci 8.848E-03 _

8.85E-03 Ci 4.882E-03 1.740E-04 -------- 5.06E-03 cm-1%

Na-24 Ci 1.827E-04 1.617E-03_ 1.06E-04 _ _1. hie-03 Ci _

Ci _

Ci _

Ci . _ _

Ci _ _

f f_ _ _

21 ci _ _

ci _

Ci Ci -

Ci_ _ __ __

ci _

Ci _

_~

_Ci _

Ci _

Ci _

ci _

2.37E-01_ 7.54E-02 6.64E-01 Total Activity __ Ci 3.52E _01 Gross _ Alpha Ci 41.75E-04 61.6E-04 17.49E-05 3 4.10E-04 ci __

ci - _

- ci Ci _

Ci _

l' TABLE 2.3-4 MILLSTONE UNIT No. 3-1988, LIQUID RAD WASTE EFFLUENTS - BATCH y,,,

CFF WASTE NEUTRALIZING SUMPS l,

Unic JULY AUGUST SEPTEMBER *NN I

.- Nuclides Relessed NONE Cr-51 Ci Mn Ci Tc-99M Ci .  !

Co-58 Ci  !

Co-60 Ci I-131 .Ci 1-133 Ci  ;

I-135 Ci Cs-134 Ci j Cs-137 Ci Mo-99 Ci l Ce-141 ci I 1

co-1LL Ci  !

Zn-65 Ci-Fe-59 ci i ci Ci Ci l 1

Ci  !

Ci  ;

i Te-55 Ci Sr-89 Ci Er-90 Ci Total Activity Ci xe-133 Ci.

Ye-135 Ci

, Xe-135M Ci Ci

  • '. Ci ,

)

H-3 Ci

)

1

.j

TABLE 2.3-4 MILLSTONE UNIT No. 3 LIQUID RAD WASTE EFFLUENTS - RATCE.

Year 1988 CPF WASTE NEUTRALIZING StMPE

, Nuclides Released Unit ~ OCTOBER NOVEMBER DECEMBER rN$

~

l NONE f

cr-$1 C1 _

Mn-54 Ci _ _

Te-99M y Ci _

Co-58 ci

)

~

Co-60 Ci _

2-131 Ci _ _

1-133'- Ci _

1-135 C1 Cs-134 C1 Cs-137 C1 ,,

)

Mo-99 I , ci_ --

Co-161 _

e4 --

c.-1&L cf En-65 ci -

7e-59 ci __

ci c i __. _ -.

Ci -

ci -

Ci- _

Fe-55 Ci st-89 __

ci . - - - - --

sr-to ci _

Total Activity _

C1 - -- __

xe-133 ci _

  • - Ia-115 Ci Xe-13SM eg _

\* * --

C1 C1 - - -

_R-3 ci '

.. i s .. . . . _ _ . . . . . - . _ _ . . . . _ _ .- a.- - . . - .........w- ..i.mI

1 TABLE 2.3-5 j MILLSTONE UNIT No. 3 h SUMMATION OF CASEOUS EFFLUENT RELEASES l *

,1 QUARTERLY UNITS JULY AUGUST SEPTEMBER TOTAI.S 1988 f YEAR i

A. Fission and Activation Cases

1. TOTAL ACTIVITY Ci- <MDA Z.MDA 7.49 7.49 RELEASED
2. AVERAGE RELEASE RATE I/8'C ----- ---- 2.99 1.01-FOR THE PERIOD B. Iodines
1. TOTAL I 131 ACTIVITY C1 6.04E-04 1.44E-04 5.45E-05 8.03E-04 UCi/see 2.41E-04 5.95E-05 2.17E-05 1.08E-04 p

C. Particulate

1. TOTAL PARTICULATE Ci 'fMDA 6.8E-05 < MDA 6.8E-05 ACTIVITY RELEASED
2. AVERAGE RELEASE RATE UCi/sec 9.14E-06 2.81E-05 ----

FOR THE PERIOD

3. TOTAL GROSS ALPHA ACTIVITY RELEASED

' ' MA 4MDA (MDA ----

D. Tritium

1. TOTAL ACTIVITY Ci 13.1 8.06 9.04 30.2 RELEASED
  • i, 2. AVERAGE RELEASE RATE UCi/sec 5.21 3.33 3.60 4.06 FOR THE PERIOD 1 - __ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

TABLE 2.3-5 MILLSTONE UNIT No. 3 SUMMATION OF GASEOUS EFFLUENT RELEASES 9 QUARTERLY' VNITS OCTOBER NOVEMBER DECEMBER TOTALS HAR 1988 --

]

i A. Fission and Activation Cases __

1. TOTAL ACTIVITY .Ci 41.8 4.82 4.NDA 46.6 l RELEASED I*

y UC1/see 13.8 1.99 4MDA 5.51 1

l l

3. Zodines _

l

.T Ci 4.46E-04 3.78E-04 2.11E-03 E SD 1.29E-03

2. AVERAGE RELEASE RATE FOR THE PERIOD UCi/sec 4.27E-04 1.84E-04 1.25E-04 2.50E-04 ]

l C. Particulate _

1, TOTAL PARTICULATE 6.48E-05 1.09E-05 4MDA 7.57E-05 Ci ACTIVITY RELEASD

2. RA WE WE UC1/sec 2.15E-05 4.50E-06 (MDA 8.95E-06
3. TOTAL GROS $ ALPMA Ci 2.14E-07 tMDA 2.14E-07 ACTIVITY RELEASED 7.73E-10 l

D. Tritive __ _ _ _ _ _

' '. 3. TOTAL ACTIVITT C1 25.4 1.53 /.MDA 26.9 gggggggy -

2. AVERAGE RELEASE R' ATE C1/sec g ,.4 0.63 LMDA 3.18  ;

FOR THE PERIOD l

l

\ _ _ _ _ _ _ - - - _ _ _ _ - . _ _ _ _

TABLE 2.3-6 MILLSTONE UNIT No. 3 - GASEOUS EFFLUENT - CONTINUOUS NORMAL VENTILATION Year 1988 S

l_Micl{derRelessed

, Unit l $ULY- AUGUST SEPTEMBER Ft'{I f

1. Fission gases

'~

Xe-138 C1 tv-s7 C1 E>88 C1 Er-85m C1 .

Xe-1M C1 3.22 3.22 Xe-133 C1 4.27 4.27 Kr-89 Ci X -137 C1 Xe-1Ms Ci 1r-85 Ci Ke-133m Ci Xe-131m C1 i Kr-85 Ci Ar-37 Ci Total For Period Ci N/D M/D 7.49, 7.49 {

t. Iodines iodine-13) Ci 6.04E-04 1.44E-04 5.45E-05 8.03E-06 iodine-133 C{ 67.97E-05 fl.43E-04 6.62E-05 6.62E-05
3. Particulate cr-51 C1 Mn-54 Ci Fe-59 C1 Co-58 C1 Co-60 C1 2n-65 c1 I-131 Ci _. =

Cs-134 C1 Cs-137 Cf Ba-140 C1 Ce-141 C1 Ce-144 Ci ND-147 ci 6.8E-05 _6.8E-04 Gross Alpha _

C1 13.6E-06 12 .2E-06 13.2E-06 1t.nr-nA

. . C1 Sr-89 C1 61.2E-06 61.92E-06 kl.61E-06 .61.spr nA  !

Sr-90 C1 6.3. 2 E-07 63.2E-02 5.3.2E-07 6 3. 2E-07

- Total Ci 6.8E-05 6.8E-05 H-3 C1 13.I 8.04 B.85 _

29.99.

I

I TABLE 2.3-6 MILLSTONE UNIT No. 3 - GABE0US EFFLUENT - CONTINUOUS WORMAL VENTILATION

% Year 1988

_ mielides Released Unit otTOBER NOVEMBER DECEMBER

$IF

1. Fission gases

~

Xe-138 _C1 -

d EA-

=

teJ7 C1 l tr.as C1 __. -

4 89a - C1 384)$ C1 1.2 1.2

___ b 133 C1 19.95 L al _

_ 21.56 6 99 Ci

~

to-1M Ci ,

~

Xe-l h __

Ci _

b t3m _ _

Ci Xe.113e _ .C1 to-111e et ~

Er-85 __ _ tt _

Ar-37 et - e

._fotal For h rted ti 19.95 4._81 _ HDA ~

24.7.6

2. todines _ __

10d(ne 13) _Ci 1.06E-03 1 4.38E-04 3.7Bh-04 1. mrv ni

_ {ed{ne-133 Ci 3.37E-04T t.10E-06 6.12E-05 4.05E-04 4

3. Particulate Cr-51 C1

~

4 MDA m.s4 C1 _

Fe-59 et _ _

Co-58 C1 Co-60 ci _ _

I

___ _2n-65 es _ ~

I-131

___C( 4.85E-05 1.02r-os -

_s.aar-ns Co-134 _ C1 Cs-137 _Ci l'. 633 E-05 1 A"-nt Ba-140 Ci _ _

_Co.14_1 _ C1 Co-144 '

CI cf- --

Gross Alnhn . Ci 2.09E-07 <MDA __

1.09F-07 C1 _ --

_ u Sr-89 Ci 4MDA 4GA iMDA _ dVNA Sr-90 _ Ci LMDA _

LJOA 4.MDA _

'MDA Total _

Ci 6.48I-03 1.02E dMnA 7_nne ny H3 _ C1 12 . 'A 9 'MnA  : fMDA j l2.82 -

TABLE 2.3-7 MILLSTONE UNIT No. 3 - GASEOUS EFTLUENT - CONTINUOUS EST BUILDING VENTILATION Year 1988

[ Eclides Released l Unit JULY AUGUST SEPTDIBEF eu

  • 1. Fission gases C1 Xe-138 gr.gr Ci gr 38 Ci C1 tr-Sh C1 Xe-135 C1 Xe-133 C1 Kr-39 te-ly7 Ci _

C1 Ie-135m Er-8b Ci Ke-133m C1 Xe-171m Ci Kr-85 Cf Ar-37 Ci 4 MDA 4 MDA 4MDA 4 MDA Total Fer Period Ci

2. lodines <smA Ci 4 MDA l 4 MDA 4mA I iod {ne-131 4 MDA 4 MDA 4MDA 4 km A iodine.133 Ci
3. Particulate cr-51 Cf Mn-se Ci Fe-59 C1 Co-58 C1 j

Co-60 __Ci Zn-65 cf I-131 Ci _

Cs-134 C1 Cs-137 Cf Ba-140 C1 Ce-141 C1 l

Ce-144 Ci Ci 54,6E-08 12.2E-08 . it; . 21 F-08 Ignp Gross Alpha C1

  • C1 iMDA Sr-89 C1 61.86E-08 61. 48 E-08 12.23E-08 6:5 2E-09~ <fibA
  • Sr-90 C1 53.7E-09 $3.71E-09 4MDA CIDA 4fDA 4 MDA _

Total _

4MDA 2.5E-02 ,1.9E-01 2.1E .D.l H3 C1 i

TABLE 2.3-7 MI!.!. STONE 13417 No. 3 -' GASEOUS EFFLURit? - CONTINUOUS Year 1988_

[ hetides Released Unit j OCTOBER _ l NOVEMBER DECEMBER ,' I

1. Ffssion gases

_Xe-138- _Cf MDA MDA MDA EA -

rs.rr C1 __

~

sees ___

C1 Er=8ss C1 to-ass Ci se.in Ci sp-se C1

~

Es-in C1 Ie-l h Ci tr-8) Ci Ze+1Mn 24 _ _

se ima et __

Er-es -_ et 4r 37 24 total For h riod et c v er uni

t. todines - - --

l (edine-13) Ci 1.18E-05 3.22E-06_ 4MDA _

1.30E-05 (odine.133 Cf 3.59E-06 'MDA_ tMDA 3.59E-06

3. Portfeulates -

Cr-51 Cl 4MDA zMnA m.3A C1 2.21E907 2.21E 07 Fe-59 21 Co-58 _

_ Ci _ _ 4.41E-07 _ 6. 41r-n t .

Co-60 __ Ci _

En-65 e4 __ _

I*131 et _

_Cs-134 _ _ __ _

Cf __

Cs-137 Cf Ba-140 Cf co-141 Ci _ . _ _

l Co-144 _

C1 y w __

ci_ _ _

Gross Aloha _. Il 5.1RF-no _( MDA _ 7.73E-10 5.59E-nQ-i Ci Sr-89_ _C1 4MDA 'WA _ (MDA _ __

Sr-90 C1 'MDA _

cMDA AMDA_ _ -_

Total .Cl_ _ r MDA _ 6_.62E-07 .

4FnA 6.62E tr_ t _ C( l.4E-01_ _

1.53 4MDA 1,67 _

1

1 TABLE 2.3-8 MILLSTONE UNIT No. BATCH CONTAINMENT DRAWDOWN Year 1988 I

l kc11 des Released l Unit JULY AUGUST SEPTEMBER eta _

NONE

1. Tission cases ,

Xe-138 Ci re-s7 C1 te-se Ci tr-sse C1 C1 Ee-135 3e-133 Ci Kr-89 Ci re-irr C1 te-135s Ci i Ci tr-s>  !

2e-133m C1 Ke-131m c1 Kr-85 ti Ar-37 ti Total For k rfod ti

2. lodines '

C1 fodine-131  !

iodine-133 Ci

3. Particulate Cr-51 C1 C1

%-s4 Fe-59 c1 Co-58 Ci Co-60 C1 ,

Zn-65 cf I-131 C1 Cs-134 C1 Cs-137 C0 Ba-140 C1 C -141 Ci 5-144 C1 Ci

' Ci

  • TOTAL C1 C1 i,

C1 ___

TABLE 2.3-8 HILLSTONE UNIT No. 3 - RATCE CONTAIlOtENT DRAWDOWN Tsar 1988 belfdes blessed $1% l _

OCTOBER l NOVEMBER DECEMEER- thuh l .,

- 1. Fission gases Xe-138 Ci N/A rs.s? - -

C1 _ _

ap.es C1 _

3,.ess C1 _ _ _ _ _

3e-135 Ci l so.133 C1 4.44E-01 9.59E_-03 _4.53E-01 m,.m Ci h ist Ci _ [

ze.i m C1 tr-th Ci Ie-ish C1 4,51E-03 _. 4. sir _o1 l Ze-131m ti Er-95 et _

Ar.M t4 total For period C4 4.48E _9.59E-03 4.sar-01

2. ledines (odine.131 Ci 5.11E-06 5.20E-06 1.03E-05 todtne.133 Ci LMDA 4 NDA y 41!DA l
3. Partfes1 stas Cr-51 Ci N/A __

&-S& C1 Fe-59 ei co-58 gg co_-60 _ C1 , __

En-65 t'4 __ __

T-131 et ,

Cs-134 Ci _ _

Cs-137 Ci _

' Sa-1_40 C1 Co-141 C1 Co-144 ~ Ci cf _

. . , . Ci _ __ _ _

TOTAL _

Ci 'MDA MIDA_ _

4HDA ___

_ Ct_ __ _

Ci ._

y.3 C1 _

_ 2.42E-03_ 1._94E-03 4.36E-03 C4 _ _

,_V

I I

TABLE 2.3-9 MILLSTONE. UNIT No. 3 - BATCH CONTAINMENT PURGES

Year 1988 ,

, [fbclfdesReleased Unit l JULY AUGUST SEPTEMBEB eta

1. Fission gases NONE Xe-138 C1 l 6 37 C1 Er ss C1 Er-85m C1 Ie-135 C1 3e-133 Ci Kr-39 :Ci Ie-137 Ci Xe-135m Ci tr-83 Cf Xe-133m C1 Ie-131m Ci Kr-85 ti Ar-37 C1 Total For Period ti
t. Iodines todine-131 Ci iodine-133 C1
3. Particulate Cr-51 Ci Mn.s4 C1 Fe-59 C1 Co-58 C1 Co-60 Ci Zn-65 cf I-131 C1 _. _=

Cs-134 C1 Cs-137 Ci Ba-140 C1 Ce-141 C1 Ce-144 C1 Ci C1 l TOTAL C1 o . C1  !

C1 H-3 C1 Ci __

' TABLE 2.3-9 MILLSTONE UNIT No. 3 - BATCH CONTAINNDT FURCES

., Year 1988 lbc11 des Released _ _ _

Unit OCTOBER NOVD2ER DECEMBER kMD

'1. Fission gases Xe-138 ,81 y/A N/A

= ,

t>ss ___

_C1 __

Epsis C1 2.14E-03 2.14E-03 Ie-135 Cl 5.94E-01 5.94E-01 )

ie.133 _ _

Ci 2.04E+01 _

2.04E+01 KNM _ Ci _ _

twin C1 1 > 199s - Ci _

EN8h Ci _ _

_ Re. ins ti 3,0E-01 __

3.0E-01 l Xe-131a - ei . 1.14E-0_1 _

_ _ 1.14E-01 )

tr-es et .__  ;

A>W E4 _-

_ Total For period _ ti 21.4 91_A

t. Iodines _

ledine.131 C1 2.10E-04 N/A _ N/A 2.10E-04 ledine.133 _

_C1 3.37E-05 N/A N/A- ~3.37E-05

3. Particulate Cr-51 Ci N/A N/A m.sa Ci _

Fe-59 ~~

ti _ _ ^

Co-58 Ci co-60 Ci _ _ _

~ ~

zn-65 -

m I-131 ti _ _ __

Cs-134 ti__ _ _ _ _ _ _

Cs-137 Ci sa-1_4__0 _ _ _ _ _ C1 _

j Co-141 C1 ~ ~

Ce-144 Ci_

ci 1- - - -

TOTAL C1 ' MD A _ . $MDA _ emA __

. __ C1 Ci _ __

M-3 CL l 1.24E+01_

[1.24E+01 _

ci _

m . -

TABLE-2.3-10 MILLSTONE UNIT No. 3 - CONTINUOUS TURBINE GLAND SEALING SYSTEM EXHAUST l

, Year 1988

'l

[ kclides Released Unit l JULY AUGUST SEPTEMBEl .

u

1. Fission gases NONE Xe-138 C1 I i ge-37 C1 ge-38 Ci Er-sse C1 Xe-135 Ci ite-133 Ci  !

Kr C1 te-177 Ci Ie-13$s Ci tr-8% C1' Xe-133m C1  ;

Xe-131m f C1_

Kr-85 ti Ar-37 ti Total For Period Ci t todines todine-13) Ci todine.133 C1

3. Particulate Cr-51~ Ci Hn-54 C1 Fe-59 c1 Co-58 C1 Co-60 C1 Zn-65 cf I-131 gg ,

Cs-134 C1 Co-137 Ci Ba-140 C1 Ce-141 C1 Ce-144 Ci cf

. . C1 TOTAL C1 Ci C1 C1 Ci __

l

\

TABLE 2.3-10 MILLSTONE UNIT No. 3 - CONTINUOUS TURBINE GIAND SEALING STSTDi EKHAUST Year 1988

[ &clides Released Unit dCTOBER NOVEMBER DECD4BER ta

. 1. Ffsifon_ gases NONE j e-138 Ci l gr.yr _ _Cf_ _

gr.sg C_1 _

g,.gs. C1 - _

s Re-13$ ___

C1 _

3. 133 C1 --

Kr-89 _ _

C1 --

t iyy Cl_ _ _ _ _ _

Fa-199s -

- Si -

=

tr-t), Ci te-133e C1 _

Ie.111m - Cf Kr.8$ Et __

Ar.17 Cf - -

Total For Period Ci -

t. Iodines ---

iodine 131 Ci __

iodine 133 Ci

3. Particulate __ _ __

cr-51 C1 h-u C1

_ _ _ Fe-59 ft -- - - - - - - -

Co-58 Cl -- - --

~

Co-60 Ci --- .--

2n-65 cf __

I-131 Ct .

Cs-134_ _ Cf _

Co-137 Cf - --

Sa-140 -- C1 Ca-141 __

Cf co-144 C1 et

.. C1 _.

TOTAL C1 - - -

~

C1

~

. C1 _

Cl -

C1 _ _ _

TABLE 2.3-11 MILLSTONE UNIT No. 3 - BATCH MAIN CONDENSER MECHANICAL VACUUM PUMP EXHAUST

$ . Year 1988 l_shelfdesReleased Unit JULY AUGUST SEPTEMBER ta

1. Fission gases NONE Xe-138 .Ci Kr-87 C1 6 88 C1 j Kr-85s Ci

, Ze-135 Ci Xe-133 C1 .

Kr-89 Ci ,

bly7 Ci Xe-13% Ci tr-8 2 CI xe-133m Ci Ie-131m C1 Kr-85 Ci Ar-37 Cf l

Total Fer Period Ci

2. lodines iodine-131 Ci I iodine-133 Cl
3. Particulate Cr-51 C1 Mn-54 C1 Te-59 C1 Co-58 C1 Co-60 Ci Zn-65 cf I-131 C1 Cs-134 C1 Cs-137 Ci Ba-140 C1 Ce-141 C1 Ce-144 Ci Ci Ci TOTAL C1 C1 C1 __

~

C1 Ci .

TABLE 2.3-11 MILLSTONE IfMIT N>.'3 - BATCE MAIN CONDENSER MECHANICAL VActJUM' PUMP EXEAUST l_ abelfdes Raleesed Unit CCTOBERl NOVEMBERDECEMBER To

- 1. Fission gases AgA Xe-138 Cf __

y/A gaggg 'MDA h et Ci __

b as C1 _

se.sps Ci

_3e 135 Ci Xe-133 Ci _

tr-09 C1 b1TP _ _Ci hina C1 _

CP 83s Ci

_Ie-133m tt Xe-131m et Re-85 21 Ar-37 21 total For k ried et $r er er OGM

t. ledines (odfre-131 Ci 8.49E-08 Ji/A g.aer-na (edine.133 Cl AMDA } 4MDA-
3. Particulate Cr-51 Ci 4tDA N/A ._ 4MDA omA h-1A Ci Ta-59 21 _

Co-58 g4 _ _

Co-60 ci En-65 et I-131 et __

Cs-134 C4 Co-137 Ci Sa-140 C1 Ce-141 _ Ci _

Ce-144 C1 ci __

. C1 gr C1 @A 4MDA TOTAL Ci -

_ Ct C1 Ct ar .ar

[-.

);

t-

,t 1 l 1'

l

. 3.0 . Radioactive' Solid Waste Sumaries ,of solid waste shipments for each unit are given in, the attached Tables. The prinetpal rsdionuclidas.were considered to be those included on the shipping manifest. '

l Solidification Agent (s)- .j Portland l Cement Types and typical volumes of conta,iners- ,

y

.\

55 gallon steel drum DOT 17-H container g 202 ft3 steel container 87 ft3 LSA steel box 132 f t3 Polyurethane high integrity container 202 ft 3Polyurethane high integrity. container 92.7 ft3steel box c . ,

4 D. . ,

2,.

TABLE 3

. ;j!;

Page 1 of 16

~

EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT -

< SOLID WASTE AND IRRAD1ATED COMPONENT SHIPMENTS s

MILLSTONE UNIT 1-JULY 1, 1988 - DECEMBER 31, 1988 6-Month Est. Total

1. Type of waste Units Period Error, %'

(CNSI) M3 94.9 -

Burial Ci 7.02E+02 2.5El l a) Spent Resin, Filter Sludge, Evaporator Bottoms, Etc. (SEG) M3 N/A Super Compaction Ci N/A 2.5El

-(CNSI) M3 30.1 Burial Ci 1.11E+00 2.5El b) Dry Compressible Waste, (SEG) M3 32.3 Contaminated Equipment, Etc. Super Compaction ci 2.02E-01 2.5El (B&W M3 15.3' Buria)l Ci 2,10E-01 2.5El' ,

c) ' Irradiated . Components, M3 .1.1 Control Rods, Etc. Ci 4.43E+02 2.5El M3 N/A d) Others (Describe) Ci N/A 2.5El

2. Estimates of Major Nuclides Composition (By Type of Maste) j i

a) Spent Resin, Filter Sludges, Evaporator Bottoms, Etc. (Burial) )

MRGli.ilf M.l.

H-3 <0.01

,, 4 g ,

' i 1

l

.. , '1.

' S.

t . ,j Page 2 of 16

-j

  • -3.38 Cr-51 Mn-54 '

9.09 Fe-55 13.62 ,

' 'k Co-58 0.54 Fe-59 0.64 Co-60 16.57 .

Ni-63 0.60 Zn-65 53.71 Sr-89 0.02 i

Sr-90 0.03 Tc-99 <0.01 I-129- <0.01 l l

I-131 0.02 I Cs-134 0.04 Cs-137 1.65 Ba-140 0.02 La-140- O.01 Ce-141 0.01

-- p Ce-144 <0.01  :

'1 l

Pu-238 <0.01 )

Pu-239 <0.01  !

-r Pu-241 -

0.03 Am-241 <0.01 Cm-242 <0.01

+ .

Cm-244 <0.01 L ,; . .

I

_ _ .-___-.-_ _ a

icf, r  ; l ':

'N.

y , s l., -l.f . >

v'

(, ll g... :t

'4 Page 3 of l'6 4-  ;.

c. :.

b) Dry Compressible Waste, . .-

' Contaminated Equipment, Etc.-(Burial)

Nuclide . .LU.

.a .

C-14 <0.01 l Mn-54' 12.72 Fe-55 10.42 N>

Co-60 60.66 Ni-63 9.18 _-

Zn-65., 4.93 Sr-90 <0.01 Cs-137 2.05 s :_ _

Pu-238- <0.01

u Pu-239 <0.01

~

-Pu-241. 0.02

> .Am-241 <0.01

~ .

a- .

Cm-242 ,

<0.01 Cm-244 'G.01 l

b) Dry Compressible Waste, .

t

' Contaminated Equipment, Etc. (Super Compaction)

,c Egclide .LM.

14,59 Mn-54 __.

Fe-55 16.72 Co-60 59.72 a

,- Ni-63 .-

4.41

'~

~

Zn-65 1.78 Cs-137 2.78 K.. .

]

)

p

, . I D

.. .p Page 4 of 16

.n b)-Dry Compressible Waste, contaminated Equipment, Etc. (Burial from Babcock & Wilcox)

Ruclide ,[t).

, H-3 0.08 C-14 0.92 i

Mn-54 1.00  :

Fe-55 6.21 l Co-58 <0.01 Co-60 83.94 r Ni-63 2.82 s

Zn-65 ,

0.07 i

Sr-90 <0.01 Tc-99 <0.01 Ag-110m 0.01 Sb-125 4.46 .

j __

I-129 <0.01 Cs-137 0.14  ;

J Pu-241 0.26 li Cm-242 0.02 l Other Tru 0.06 l i

c) Irradiated Components, Control Rods, JItc. .(Burial)

[ Nuclide _(.11. f 1

)

H-3 0.49 C-14 <0.01 <

Cr-51 <0.01 o

e 8 1 L

3 1

    • " Page 5 of 16 f Mn-54 12.83 Fe-55 60.44 i

Ni-59 0.01 i

Co-60 24.36

.Ni 1.87 Nb-95 <0.01 Tc-99 <0.01  ;

Pu-238 <0.01  ;

i Pu-239 <0.01 Pu-241 <0.01 Am-241 <0.01 i

Cm-242 <0.01  !

Cm-242 <0.01 i

3. Solid Waste Disposition'(From Millstone)'

Nudber of Shipments Mode of Transportation Destination .

20 Truck (Sole Use Vehicle). Chem-Nuclear Barnwell S.C.

1 Truck (Sole Use Vehicle) Scientific Ecology i Group Oakridge Tenn.

i Solid Waste Disposition (From Babcock &'Wilcox) (See Note)  !.

' Number of Shipments Mode of Transportation Destination L 6 Truck (Sole Use Vehicle) Chem-Nuclear Barnwell S.C.

3 Truck (Sole Use Vehicle) U.S. Ecology

?, Richland Wash,

s. .

NOTE: No unit assignment, shipments charged to Station i

i 1..

l

7 e

i 1

Page 6-of 16 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT -

SOLID WASTE AND' IRRADIATED COMPONENT SHIPMENTS MILLSTONE UNIT 2 L JULY.1, 1988 - DECEMBER 31, 1988 6-Month .Est. Total

1. Type of Waste Units Period -Error, %

(CNSI) M3 2.1 Burial Ci 9.88E+00 2.5El a) Spent Resin, Filter Sludge, Evaporator Bottoms, Etc. (SEG) M3 8.1 Super Compaction Ci 1.22E-01 2.5El

. (CNSI) M3 14.8 Burial Ci 3.60E+00 2.5El b) Dry Compressible Waste, (SEG) M3 g,9 Contaminated Equipment, Etc. Super Compaction Ci 5.40E 2.5El (B&W) M3 6.2 Burial Ci 8.55E-02 2.5El c) Irradiated Components, M3 N/A Control Rods, Etc. Ci N/A 2.5El M3 N/A Ci 2.5El d) Others (Describe) N/A l-l l

2. Estimates of Major Nuclides Composition (By Type of Waste) a) Spent Resin, Filter Sludges, Evaporator Bottoms, Etc. (Burial)

Nuclidt 111 H-3 0.02 o . C-14 <0.01

1 Page 7 of 16 Mn-54 0.09 Fe-55 64.06 Co-58 5.36 Co-60 19.70 Ni-63 9.07 Sr-90 0.02 Tc-99 0.01 Ag-110m 0.80 Sb-125 0.43 Cs-137 0.31 Pu-238 <0.01 Pu-239 <0.01 Pu-241 0.10 Am-241 <0.01 i

Cm-242 0.02 l

Cm-244 <0.01 a) Spent Resin, Filter Sludges, Evaporator Bottoms, Etc. (Super Compaction - Filters only)

Nuclide 1%1 H-3 93.50 C-14 0.14 Mn-54 0.03 Fe-55 3.68 Co-60 2.17 o .

Ni-63 0.03 L, Cs-137 0.03 ,

L _ _ __ _

Page.8 of 16 a-Am-241 0.04 Cm-242 0.09 Cm-244 0.01 b) Dry Compressible Waste, Contaminated Equipment, Etc. (Burial)

Nuclide D1 Fe-55 10.35 Co-56 36.55 Co-60 17.61 Ni-63 32.21 Cs-134 1.17 Cs-137 2.11 b) Dry compressible Waste, Contaminated Equipment, Etc. (Super Compaction)

Nuclide D1 Fe-55 10.35 Co-58 36.55 Co-60 17.61 Ni-63 32.21 Cs-134 1.17 .

Cs-137 2.11 b) Dry Compressible Waste, Contaminated Equipment, Etc. (Burial from Babcock & Wilcox)

Nuclide D1 t

', H-3 0.08 C-14 0.92

I

' c Page 9.of 16

. Mn-54' O.99 j Fe-55 6.21

. i.

Co-58 <0.01' i

Co-60 83.94 Ni-63 2.82  ;

Zn-65 0.07'

]

Sr-90 <0.01 Tc-99 <0.01 i Ag-110m 0.01 Sb-125 4.46 I-129- <0.01 h Cs-137 0.14 Pu-241 0.26  ;

Cm-242 0.02 U Other Tru 0.06  ;

1 7- .

j e

1

l l Page 10 of 16

  • 3. Solid Waste' Disposition (Frt dillstone)

Number of Shipments Mode of Transportation Destination 2 Truck.(Sole Use Vehicle)- Chem-Nuclear Barnwell S.C.

1 Truck (Sole Use Vehicle) Scientific Ecology Group oakridge Tenn.

Solid Waste Disposition (From Babcock & Wilcox)

Number of Shipments. Mode of Transportation Desination Truck (Sole Use Vehicle) Chem-Nuclear Barnwell S.C.

See Page 5 Truck (Sole Use Vehicle) U.S. Ecology Richland Wash.

.i 3

i I

Page 11 of 16-EFFLUENT.AND WASTE DISPOSAL SEMI ANNUAL, REPORT -

SOLID WASTE.AND IRRADIATED COMPONENT SHIPMENTS 1

MILLSTONE-UNIT 3 JULY 1, 1988 - DECEMBER 31, 1988

'6-Month Est. Total-

1. Type of Waste Units Period Error,lb (CNSI) _- M3 10.7.

Burial Ci 6.65E+00 2.5El a) Spent Resin,_ Filter Sludge, Evaporator Bottoms, Ect. (SEG) M3 0.2 Super Compaction Ci 6.26E-04 2.5El (CNSI)- M3 11.4 Burial Ci 1.69E+00 2.5El b) Dry Compressible Waste, (SEG) M3 ~ 14.8 Contaminated Equipment, Ect. Super-Compaction Ci 3.82E-02 2.5El (B&W) M3~ 4.5 Burial C4 6.19E-02 2.5El c) Irradiated' Components, M3 N/A Control Rods,_Ect. Ci N/A 2.5El M3 N/A d) Others (Describe) Ci N/A 2.5El

2. Estimates of Major Nuclides Composition (By Type of Waste) a) Spent Resin, Filter Sludges, Evaporator Bottoms, Etc. (Burial)

Nuclide 111 l

H-3 0.11  !

l

> . C-14 <0.01 l

!I i l- = . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I

7, Page 12 of 16-Mn-54 11.15 Fe-55' 27.56 Co-57 0.08 Co-58 33.81 Co 24.23 Ni-63 21.55 Sr-89 0.02 Sr-90 0.02 Nb-95 0.29 Tc-99 0.05 Ag-110m 0.75 I-129 0.05 I-131 0.15 Cs-134 0.40 Cs-137 0.68 Pu-238 <0.01 Pu-239 <0.01 Pu-241 0.09 Am-241 <0.01 Cm-242 <0.01 Cm-244 <0.01 a) Spent Resin, Filter Sludges, Evaporator Bottoms, Etc. (Super Compaction - Filters only)

Nuclide 111 H-3 0.14 l

I. C-14 0.02 l

L_______--

f

'd Page 13 of 16

  • Mn-54 12.31 Fe-55 50.18 Co-57 0.18 Co-58 1.58 Co-60 23.81 Ni-63 11.14 Tc-99 0.21 I-129 0.19 Pu-238 0.02 Pu-239 0.02 Pu-241 0.18 Am-241 0.02 Cm-242 0.02 b) Dry Compressible Waste,

. Contaminated Equipment, Etc. (Burial)

Nuclide- _dil Cr-51 0.95 Mn-54 4.16 Fe-55 27.49 Co-58 54.43 Fe-59 0.33 j Cc-60 4.48 Ni-63 7.93 1

Nb-95 0.21 i Zr-95 0.12 l

l 1

I

(<

l

[. .'

L-Page 14 of 16 b)' Dry Compressible Waste, Contaminated Equipment, Etc. (Super Compaction)

Nuclide .(11.

'Mn-54 -4.14

,,- Fe-55 35.20 Co-58 45.49 i Co-60 4.69 Ni-63 10.48 b) Dry Compressible Waste, Contaminated Equipment, Etc.-(Burial from Babcock & Wilcox)

Nuclide .(31 H-3 0.08 C-14 0.92 Mn-54 1.00 Fe-55 6.21 Co-58 <0.01 Co-60 83.94 Ni-63 2.82 Zn-65 0.07  ;

Sr-90 <0.01 Tc-99 <0.01 Ag-110m 0.01 Sb-125 4.46 I-129 <0.01

' - Cs-137 0.14 Pu-241 0.26 i

i 4

Page 15 of 16

  • Cm-242 0.02 Other Tru 0.06 3.'8olid Waste Disposition (From Millstone)

Number of Shipments Mode of Transportation Destination 3 Truck (Sole Use Vehicle) Chem-Nuclear Barnwell S.C.

O. Truck (Sole Use Vehicle) Scientific Ecology Group oakridge Tenn.

Solid Wasta Disposition (From Babcock & Wilcox)

Number of Shipments Mode of Transportation Destination Truck (Sole Use Vehicle) Chem-Nuclear Barnwell S.C.

See Page 5  ;

Truck (Sole Use Vehicle) U.S. Ecology Richland Wash.

h 'l

l. .

lc t

l L

3'.'

  • Page 16 of 16

.9 l

January 1 - June 30 1988 Corrected Update Unit 1 reporting of Irradiated Components incorrectly listed the. Curie Content.

Correction: Reported 7.44E+04 Ci Change 9.36E+04 Ci i' .

e f' e e-

.. __ _ : T?_ 1____ _

o ,

lGr 4.0' SUPPLEMENTALINFORMATION A. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 4.1 Gaseous Releases

a. : Unit 1 Stack'- Gaseous Releases (1) Fission and Activation Gases Stack monitors continuously record the effluent activity and flow rate. During periods when the augmented off-gas system is not operable, the radiation monitor reading is related to pCi by off-gas sampling at the steam jet air ejectors and subsequent isotopic analysis. The isotopic activity at the SJAE is mathematically decayed to establish the activity in the stack using the known holdup time. During periods of augmented off-gas system operation, samples are taken directly from the.

stack with a subsequent isotopic analysis. In both cases, the  ;

calculated activity in the stack is then correlated to the monitor i reading. The isotopic concentrations at the release point are '

multiplied by the total stack flow to obtain total pCi release for each isotope.

(2) lodines and Particulate Charcoal cartridges and particulate filters are'used to collect iodines and particulate, respectively The filters are then analyzed for isotopic content using a gamma spectrometer; particulate filters are also analyzed for strontium. Isotopic -

concentrations are multiplied by the release flow rate to determine the total amount of activity released.

b. Unit 2 Vent Total effluent volume from the Unit 2 Vent per month is multiplied i by the isotopic concentrations as measured by gamma spectrometer Ge(Li) analysis of grab samples of gases, iodine and particulate to obtain total pCi released from the Vent.
c. Unit 2 Containment Puroes i

Grab samples are taken for gaseous, particulate, and iodine. These are analyzed on Ge(Li) gamma spectrometer and concentrations computed. Computed concentrations are then multiplied by the purge volume for total pCi released.

Tritium collection is accomplished by the gas washing bottle method. The sample is counted on a liquid scintillation counter. i Concentration is computed using worst possible case,100%

e humidity. Concentration is multiplied by volume purged to give totalpC released.

[ .

J. d. Unit 2 Steam Generator Blowdown Tank Vent A decontamination factor (DF) across the steam generator blowdown tank vent has been determined for iodines by

2 comparison of the results of gamma spectrometry, Ge(Li), analysis'  ;

of-steam generator blowdown water.and grab samples of l

', ' condensed steam exiting.the blowdown tank vent. This DF was i then applied to the total iodine releases via the steam generator blowdown water to determine the' iodine releases.out of the 1 blowdown tank vent. An additional factor of 0.33 was utilized to account for the fraction of blowdown' volume actually flashing'to l steam in the blowdown tank.  ;

= e. - Unit 3 Vent and ESF Buildino Vent The Unit 3 Ventilation Vent collects gas streams from the Auxiliary, Fuel, Waste Disposal,-and Service Building exhausts, containment t purge and gaseous waste process vent. The Unit 3 Vent is located - 'l on the roof of the turbine building and discharges.133 feet above.  !'

grade. The Unit 3 ESF Building Vent collects gas streams from the' Engineered Safety Features Building Ventilation System. This vent ,

is located on the south wall and~ discharges 23 feet above grade, i Total. Effluent Volume per month is multiplied by isotopic L

concentrations from the analysis of grab samples to obtain the total ,

activity releared. These grab samples are obtained monthly.for i fission gas and tritium, weekly filters for iodines and particulate, monthly composites of particulate filters for gross alpha and ')

Strontium. j 1

L f. Unit 3 Cont'ainment Drawdown and Purae  ;

Unit 3 Containment is drawn down and purged intermittently The

(

drawdown is accomplished by using the containment vacuum steam i

' jet elector and releases through an unmonitored vent on the roof of the Auxiliary Building. The containment vacuum pump

' discharge, which maintains sub-atmospheric pressure following the initial drawdown,is released through the Unit 1 Stack. The purge is H the process of discharging air from containment to maintain l' temperature, humidity, pressure, concentration, etc., where air is replaced. Purges are filtered and normally released through the Unit 3 Vent but may use the Unit 1 Stack. Purges and Drawdowns' I are intermittent and are therefore considered batch releases..

Calculated volume discharged is multiplied by isotopic concentrations from the analysis of grab samples to obtain activity released.

g. Unit 3 Turbine Gland Sealina System Exhaust The turbine gland sealing system prevents air leakage 'into the turbine and valve stems and collects steam leakage. A mixture of l-air and steam drawn from the turbine shaft packing is condensed and the noncondensable gases are vented to the atmosphere at a point above the condensate polishing building. This vent is at an elevation of 48 feet above grade. Noble Gas Activity released is
  • calculated using the air ejector monitor activity concentration and I

the percentage of steam to the gland sealing condenser. lodine i .

and particulate activity is calculated using the steam generator 4- blowdown activity concentration and appropriate carry over fraction. (See Appendix H,ODCM).

i

v 0 4 3.

h. Unit 3 Main Condenser MechanicalVacuum Pump Exhaust;
The main Condenser Evacuation System draws the initial vacuum in:

. the condenser during startup and maintains vacuum during startup.

lh 'i. The Main Condenser mechanical vacuum pumps exhaust through-the vent on the condensate polishing building roof. Steam Jet Air.

Ejectors maintains condenser vacuum during normal operation. Air and noncondensable gases removed from the condenser by the' 1 steam jet air ejectors are discharged to the Unit 1. Stack.

Noble Gas Activity released during startup by the Main Condenser:

.z Vacuum Pumps is obtained by multip ing the condenser volume by a grab sample of the air ejector ecay corrected for time'of

. shutdown. lodine and particulate activity'is obtained from a grab

. sample of the mechanical vacuum pump exhaust and volume

. discharged. (See Appendix H, ODCM).

4.2 Liould Effluents

a. Liauid Tanks There~are numerous tanks which are used to discharge liquids-containing radioactivity to the environs; they are:

Unit 1 - Decontamination Solution Tank Unit 1 Floor Drain Sample Tanks (2)

Unit 1 -Waste Sample Tanks (2)-

Unit 2 - Clean Waste Monitor Tanks (2)

Unit 2 - Aerated Waste Monitor Tank Unit 3 - High Level Waste Test Tanks (2) . l Unit 3 - Low Level Waste Tanks (2)

Prior to release, a tank.is recirculated for two equivalent tank volumes, a sample is drawn and analyzed on the Ge(Li) gamma spectrometer for individual radionuclides composition. An aliquot  ;

of the sample is composited and analyzed for H 3, Fe-55, Sr-89/90.

Isotopic concentrations are multiplied by.the volume released to obtain the total activity released. ' A proportional aliquot of each discharge is retained for composite analysis for strontium and gross

alpha.

L.

l .

b. Unit 2 and Unit 3 Steam Generator Blowdown j l Grab samples are taken of steam generator blowdown water, and I' .

are analyzed by amma spectrometry, Ge(Li). Total volume of blowdown is mul lied by the isotopic concentrations to determine the total activity released via blowdown. The calculated activity released out of the blowdown tank vent is accounted for pending

.the point of blowdown sampling.

1 i

i _ _ _ - _ _ _ _ _ _ - _ _ _ . _ _ - -

Tritium is determined through liquid scintillation counting and 5 strontiums are. analyzed by radiochemical separations and.

appropriate counting techniques.

. 4.3 Estimates of Errors Estimates of errors associated with radioactivity measurements were-made using the following guidelines:

1) Samplino and Data Collection - 10% accounts for ~ variation in personnel obtaining required data, y
2) Calibration - 5% instrument calibration to NBS standards.
3) Countino of Samples - 10% maximum error due to. counting statistics.
4) Flow and Level Measurements - 10% maximum errors on volumes released.

i h

l 6 l' i fa e

I

l

, 4.4 BATCH RELEASES .

Liquid  ;

UNIT 1 UNIT 2 UNIT 3 .

a. Number of Batches 264 299 306
b. TotalTime: (Min.) 24,540 50,753 29,432. )

~

c. MaximumTime: (Min.) 237 480 508-l

{

d. AverageTime: (Min.) 93 170 96 i
e. MinimumTime: (Min.) 30 31 -15 j Average Stream Flow - Not Applicable - Ocean Site Gaseous )

UNIT 1 UNIT 2 UNIT 2 UNIT 3 . UNIT 3 PURGE PURGE- WGDT PURGE DRAWDOWN

a. Number of Batches 'O O 7 2 2
b. TotalTime: (Min.) - - 2,463 540 240

( c. Maximum Time: (Min.) - -

440 270 120

d. Average Time: (Min.) - -

352 270 120

e. MinimumTime: (Min.) - -

151 270 120 I

L 4.5 ABNORMAL RELEASES None i,

s

b.0 CHANGES TO THE REMM/0DCM/PCP

~ There were no changes to the REMM/0DCM/PCP during the. period.

'I

-1 i

4 M

5

r

(^ ,

i 6.0 EFFLUENT MONITOR INOPERABILITY t

During the period covered by this report, .the following

' monitors were inoperable for greater than 30 days:

1. Unit 3. Steam Generator Blowdown Monitor This monitor has not been placed in initial service Until this monitor is in-service, Steam yet.

Ge ner atcr Blowdown is b eing recovered without discharge to the environment.

h e

4

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l l

k 5

l APPENDIX A - UPDATED TABLES 1

1 I

l D

R 4

I

Page 1 of 13 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT -

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS i

)-

MILLSTONE UN,ITJ JANUARY 1, 1988 - JUNE 30, 1988 6-Month Est. Total Period Error, %

Unit 1.- Type of Waste (CNSI) M8 9.25El 6.76E2 2.5El Spent Resins, Filter Sludges, Burial ,, , ,Ci _

a) Evaporator Bottoms Etc. (SEG)

Super Ms 8.00E-1 Filters Ci 1.29E-2 2.5El Only Compaction (CNSI) MS 1.22E1 Ci 8.68E-1 2.5El Burial Dry Compressible Waste (SEG)

Super MS 3.56El b) Contaminated Iquipment, Etc. 5.83E-1 2.5El Compaction ci See Page 13 (SEG) Burial Data MS 2.80E0 .

Irradiated Components, Ci l 9.36E4 [ 2.5El c) Control Rods, Etc. -

Ms Ci N/A N/A l d) Other (Describe) . . _ .

l

2. Estimate of Major Nuclide Composition (By Type of Waste) a) Spent Resins, Filter Sludges, Evaporator Bottoms, Etc. (Burial)

(%)

Nuclide 2.00E-2 H

1.54E0 -

C . . . . . . . . . . . . . . -

4.89E0 __

Cr _

54 2.56El Mn ._ -... ..........

3 1

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