Text

Semiannual Radioactive Effluent Release Rept,Jan-June 1985
	ML20134K562
Person / Time
Site:	Cook
Issue date:	06/30/1985
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17321A851	List: ML20134K562;
References
	NUDOCS 8508300265
	Download: ML20134K562 (395)
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Sem. Annual a

i-2 Radioactive Effluent L

L i Release Report Q

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January 1, through June 30,1985 0

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G Indiana & Michigan Electric Company

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Bridgman, Mich!gan Z

J Docket Nos. 50-315 & 50-316 l

O' License Nos. DPR-58 & DPR-74 l

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3300265 850823 ADOCK 05000315 R

PDR

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5 Semi-Annual Radioactive Effluent l

Release Report January 1, through June 30,1985 Indiana & Michigan Electric Company Bridgman, Michigan Docket Nos. 50-315 & 50-316 License Nos. DPR-58 & DPR-74 ican rte i

1 1

l TABLE OF CONTENTS PAGE LIST OF APPENDICES 11 I.

INTRODUCTION 1

Unit 1 1

Unit 2 1

II.

RADI0 ACTIVE RELEASES 2

III.

RADIOLOGICAL IMPACT ON MAN 2

Liquid Releases 2

Gaseous Releases 2

IV.

METEOROLOGICAL DATA 2

V.

PROCESS CONTROL PROGRAM (PCP) CHANGES 2

VI.

OFFSITE DOSE CALCULATION MANUAL (ODCH) CHANGES 3

VII.

CONCLUSIONS 3

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3 LIST OF APPENDICES 2 AGE.

1.1 RADIOACTIVE RELEASE DATA 1-1 1.2

SUMMARY

OF MAIIMUM INDIVIDUAL DOSES FOR FIRST QUARTER OF 1985 1-15 1.3

SUMMARY

OF MAIIMUM INDIVIDUAL DOSES FOR SECOND QUARTER OF 1985 1-30 2.1

SUMMARY

OF HOURLY METEOROLOGICAL DATA FOR FIRST QUARTER OF 1985 2-1 2.2

SUMMARY

OF HOURLY METEOROLOGICAL DATA FOR SECOND QUARTER OF 1985 2-17 2.3 METEOROLOGICAL DATA FOR FIRST SIX MONTHS OF 1985 2.-33 3

PROCESS CONTROL PROGRAM (PCP) CHANGES 3-1 4

0FFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES 4-1 r

)

11

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I.

INTRODUCTION i

This report discusses the radioactive discharges from Units 1 and 2 of the Donald C. Cook Nuclear Plant during the first half of 1985, according to Section 6.9.1.9 of " Appendix A" Technical Specifications for the Facility Operating License.

Unit 1:

During this reporting period, Unit 1 of the Donald C. Cook l

Nuclear Plant generated 1,761,840 Hwh Gross of electrical energy. The Monthly Operating Reports indicate that during the reporting period, Unit 1 was operating at a Unit Service Factor of 42.7% and at an average Unit Capacity Factor of 38.3%.

Unit 1-entered this reporting period in Mode 1 at 70% power. On January 11, the unit was removed from service for a scheduled ice condenser surveillance and maintenance outage. The primary maintenance item was to replace the pressurizer safety valves due to leakage problems.. The unit was returned to service on January 29, 1985. Unit 1 was removed from service on April 6,

'i 1985 for the ten-year Inservice Inspection and Cycle II Refueling Outage.

The unit remained out of service for the rest of the reporting period.

Unit 2:

Unit 2 generated 4,439,930 Mwh Gross of electrical energy during the first months of 1985. During the reporting period, Unit 2 operated at an 92.9% Unit Service Factor and at an average Unit Capacity Factor of 93.1%.

Unit 2 entered this reporting period with the Reactor Coolant System, RCS, in Mode 5 and in the process of heating up.

On January 3,1985, approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the reactor was critical, a loose parts event was detected in steam generators 22 and 23 and the reactor was shut down. Inspections of Steam Generators 22 and 23 revealed parts from broken control rod guide tube split pins. Following a thorough analysis of the event, Unit 2 was returned to service on January 12, 1985. On January 26, 1985, Unit 2 tripped due to a failure of vital instrument bus, CRID III inverter from a component short. The capacitor and diodes were replaced and the unit was returned to service on January 27, 1985. Unit 2 experienced no major shutdown during the rest of the reporting period.

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II.

RADI0 ACTIVE RELEASES Since a number of release points are common to both Units, the release data from both Units were combined to form this two-Unit, Semi-Annual Radioactive Release Report. Appendix 1 presents this information in accordance with Section 6.9.1.9 of Appendix A to the Facility Operating License (Environmental Technical Specifications). As in reports preceding this one, the effluents were well within the limits set forth in the Technical Specifications and Appendix I to 10 CFR Part 50.

III.

RADIOLOGICAL IMPACT ON MAN Maximum individual doses were calculated using the measured effluents and meteorological data given in Appendices 1 and 2 of this report, respectively.

Linuld Releases:

The liquid releases consisted of 29 Batch releases in the first quarter and 42 Batch releases in the second quarter of 1985.

These releases were treated as continuous releases for the purpose of dose calculations. The estimated doses in millirers to individuals from the liquid pathways are given in Appendices 1.2 and 1.3.

Gaseous Releases:

The gaseous releases consisted of 11 Batch releases in the first quarter and 11 Batch releases in the second quarter of 1985.

Doses were estimated for the Batch and continuous releases during each of the two quarters using the measured meteorological data at the times of the releases. The estimated doses in millirens to individuals through the gaseous pathways are listed in Appendices 1.2 and 1.3 i

IV.

METEOROLOGICAL DATA Appendices 2.1 and 2.2 contain the cumulative joint-frequency distribution of wind speed and wind direction corresponding to various atmospheric stability classes for both quarters.

The meteorological conditions during the first six months of 1985 are also furnished in Appendix 2.3 V.

PROCESS CONTROL PROGRAM (PCP) CHANGES The Radioactive Waste Process Control Manual 12 PMP 3150 PCP.001 was rewritten during the report period. This rewrite includes incorporation of change sheets 1 through 6, updated information, coment solidification of resin to meet the stable waste criteria and the equipment, processes and operations for packaging the I

I Unit 1 control rod guide tubes for dispocal. PNSRC approval of the procedure is documented on the procedure cover sheet. These changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

VI.

OFFSITE DOSE CALCULATION MANUAL CHANGER The Offsite Dose Calculation Manual PMP 6010 OSD.001 was changed during the report period and these changes are included as Change Sheet Nos. 2-3 The reasons for the changes and PNSRC approval are documented on the cover sheet.

VII.

CONCLUSIONS Based on the information presented in this report, it is concluded that the Units performed their intended design function without causing any hazard to the health and safety of the general public.

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APPENDIX 1.1 RADIOACTIVE RELEASE DAT!

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12 THP 6040 PER.405 fl$

ATTACHMENT V

=-p EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPO,R,T_ -1ST NALF 1985 Supplemental Information

_jp

~~I 5bk Facility:

D.C. Cook Plant Licensee:

Indiana & Michigan Electric Company m

1.

Regulatory Limits

2 A.

Noble Gases 3q

-T-The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be limited to the following:

g[

y' 1.

During any calendar quarter, to [ 5 mrad for gamma 5;;

radiation and [ 10 mrad for beta radiation; 2.

During any calendar year, to [ 10 mrad for gamma radiation and [ 20 mrad for beta radiation.

EE; B.

Iodines - Particulates 4

2 db

~

The dose to a member of the public from radiciodines,

^

radioactive materials in particulate form, and e

greater than 8 days in gaseous effluents released to radionuclides other than noble gases with half-lives unrestricted areas shall be limited to the following:

.=

1.

-During any calendar quarter to [ 7.5 mrem to any.

[][

organ; 2.

During any calendar year to [ 15 mrem to any

!EI organ.

7c

'L C.

Liquid Effluents 5

The dose or dose commitment to an individual from

]$t radioactive material in liquid effluents released to TEF--

unrestricted areas shall be limited:

l 1.

During any calendar quarter to [ 1.5 mrem to-the

$(_

total body and to [ 5 mrem to any organ, and:

1[_-;

2.

During any calendar year to [ 3 mrem to the total body and to [ 10 mrem to any organ.

A

_ =_

Page 1 of 4

+_

Revision 0 ce y

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12 THP 6040 PER.405 ATTACHMENT V D.

Total Dose The dose or dose committment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thFroid, which is limited to 1 75 mrem) over a period of 12 consecutive months.

2.

Maximum Permissable Concentrations A.

Gaseous Effluents The dose rate due to radioactive materials released in

. gaseous effluents from the site shall be limited to the following:

1.

For noble gases:

1 500 mrem /yr to the total body and i 3000 mrem /yr to the skin, and:

i 2.

For all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than 8 days:

1 1500 mrem /yr to any organ.

a The above limits are provided to insure that radioactive material discharged in gaseous effluents i

will not result in the exposure of an individual in an unrestricted area to annual average concentrations l

exceeding the limits in 10 CFR Part 20, Appendix B,

(

l Table II.

l B.

Liquid Effluents The concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides l

other than dissolved or entrained noble gases.

For i

' dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 pCi/ml total activity.

3.

Average Energy The average energy (E) of the radionuclide mixture in releases of fission and activation gases is not applicable per Regulatory Guide 1.21 Appendix B Section A.3.

j 4.

Measurements and Approximations of Total Radioactivity Fission and Activation Gases A.

Sampled and analyzed on a 4096 channel analyzer and Ge(Li) detector.

Page 2 of 4 Revision 0 1-2

12 THP 6040 PER.405 ATTACHMENT V B.

Iodines

San. pled on an activated carbon filter or silver zeolite cartridge and analyzed on a 4096 channel analyzer and Ge(Li) detector.

C.

Particulates Sampled on a glass filter and analyzed on a 4096 channel analyzer and Ge(Li) detector.

D.

Liquid Effluents Sampled and analyzed on a 4096 channel analyzer and i

Ge(Li) detector.

l S.

Batch Releases' A.

Liquid 1.

Number of batch releases:

29 releases in the 1st quarter, 1985 42 releases in the 2nd quarter, 1985 2.

Total time period for batch releases:

10,901 minutes 3.

Maximum time for a batch release:

179 mir.utes 4.

Average time period for batch release:

154 minutes

]

5.

Minimum time period for a batch rele.sse:

136 minutes

' verage stream flow during periods of release of 6.

A effluent into a flowing stream:

832,535 gpm circulating water l-B.

Gaseous 1.

Number of batch releases:

11 in 1st quarter, 1985 11 in 2nd quarter, 1985 Page 3 of 4 Revision 0 1-3 L

12 THP 6040 PER.405 ATTACHMENT V 2.

Total time period of batch releases:

1 1617 minutes l

3.

Maximum time period for.a batch release:

93 minutes 4.

Average time period for batch releases:

74 minutes 5.

Minimum time period for a batch release:

58 minutes 6.

Abnormal Releases A.

Liquid 1.

Number of Releases:

1st 2nd Quarter Quarter s

0 0

2.

Total activity released:

1st 2nd Quarter Quarter l

0 0

B.

Gaseous 1

iS 1.

Number of Releases:

1st 2nd c-Quarter Quarter 0

0

~

2.

Total activity released:

~..

~ _ _ _

1st 2nd Quarter Quarter 0

0 I

l I

Page 4 of 4 l

Revision 0 1-4 I

12 THP 6040 PER.405 ATTACHMENT VI EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT-IST HALF 1985

(

GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode Batch Mode Nuclides Released Unit IST ZND I

IST 2ND QUARTER QUARTER l

QUARTER QUARTER 1.

FISSION GASES L.

Krypton-85 Ci 3.65 E+2 2.50 E+1 1.91 E+1 Krypton-85M C1 1.67 E-1 9.07 E-2 4.71 E-1 Krypton-87 C1 1.16 E-1 i

8.56 E-2 I

I Krypton-88 C1 3.03 E-1 1

1.43 E 1 i

5.97 E-1 1

4.91 E+2 1 9.98 E+2 Xenon-133 C1 2.01 E+3 8.41 E+2 i

Xenon-135 Ci i 3.80 E+1 3.02 t+1 7.58 E O i 4.32 E O Xenon-135M Ci 3.98 t-3 i 9.98 E-1 i

i Xenon-138 Ci 6.10 E-2 2.43 E-1 I

i Xenon-133M C1 8.99 E O 7.22 1 0 i

3.94 E O i

1.38 E+1 2.06 E O i

1.68 E+1 Xenon-131M C1 1

1.94 E+1 i

I Argon-41 C1 1.30 E-1 4.28 E-1 Total for Period Ci 2.44 E+3 8.80 E+2

!. 5.31 E+2 l1.05E+3 2.

IODINES Iodine-131 Ci 1.83 E-2 7.85 E-2 3.25 E-3 7.37 E-4 Iodine-133 Ci I 9.50 E-4 8.88 E-4 il 3.28 E-4 1 3.25 E-4 Iodine-135 Ci i

7.71 E-S i

Total for Period Ci 1.93 E-2 7.95 E-2 3.58 E-3 1.06 E-3 1

3.

PARTICULATES l

I l

Strontium-89 Ci I

(

Strqntium-90 Ci 6

6

1 U

w" Ceslum-134 C1 1

8.58 E-4 I 2.64 E-5

.I 3.75 E-6 l

1.54 F-5 Cesium-137-C1 8.63 E-4 i 7.00 E-5

!! 5.74 E-6 1 1.68 E-5 Iron.

C1 I

ll t

Cobalt-58 Ci i 8.09 E-4 i 2.48 E-S

'l 5._1_6 E-6 t 3.46 F-6 Cobalt-60 Ci 4.8L E-4 l 4.45 E-5

'l 7.41 F 6 1 7 54 F 6' Manganese-54 C1 2.7 E-5

!l t

Zinc-65 C1 l

i Mobybdenum-99 C1 6

il i

Cerium-141 C1 i

ti i

Cerium-144 Ci i

il Cesium-136 Ci 2.35 E-5 Total for Period Ci 3.06 E-3 1.66 E-4 2.26 E-5 3.83 E-5 Page 1 of 1 Revision 0 1-5

12 THP 6040 PER.405 ATTACHMENT VII EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT-IST HALF 1985 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Units IST 2ND Est. Total QUARTER QUARTER Error, %

A.

FISSION AND ACTIVATION GASES 1.

Total release Ci.

2.97 E+3 1.93 E+3 19.8 2.

Avera'ge release rate pCi/sec 3.82 E+2 2.45 E+2 for period.

3.

Percent of Technical 2.42E0 2.02c0 Specification (T/s 4.29E0 2.92Z0 3.11.2.2) limit.

B.

IODINES 1.

Total Iodine-131 Ci 2.16 E-2 7.92 E-2 3.0 !

2.

Average release rate pCi/Sec 2.78 E-3 1.01 E-2 for period.

3.

Percent of Technical Specification-5.4920' l.73 +1 (T/s 3.11.2.3) Limit.

C.

PARTICULATES 1.

Partict.J.ates with half-Ci 3.08 E-3 2.04 E-4 38.8 lives > 8 days.

pCi/sec 3.96 E-4 2.60 E-5 2.

Average releasc rate for period.

3.

Percent of Technical Specification (T/s 5.49C0 1.73E+1 3.11.2.3) limit.

4.

Gross alpha radioactivity.

Ci j5.35E-5

<5.47 E-5 D.

TRITIUM l.

Total release.

Ci 1.05 E+1 9.86 E O 1.0 2.

Average release pCi/sec 1.35 E O 1.25 E O rate for period.

3.

Percent of Technical Specification limit.

9.94 E 0 5.47 E 0 (10 CFR 20) 4 Page 1 of 1 Revision 0 1-6

L 12 THP 6040 PER.405 ATTACHMENT VIII EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - iST HALF 1985 LIQUID EFFLUENTS BATCH CONTINUOUS MODE MODE IST 2ND IST 2ND Nuclides Released Quarter Quarter Quarter Quarter Strontium-92 Ci 2.35 E-3 i

Strontium-89 Ci 5.53 E-5 I

Strontium-90 C1 5.53 E-5 l

1 Casium-134 C1 4.31 E-3 I 2.85 E-2 ! 7.25 E-3 3.00 E-3 Casium-137 C1 2.92 E-2 1 2.58 E-2 1 8.03 E-3 i 4.38 E-3 Iodine-131 C1 6.92 E-3 1 6.43 E-3 t 2.24 E-3 2.33 E-4 Iodine-135 Ci I

i 1.77 E-4 Iron-55 Ci 3.34 E-3 i

! 7.95 E-2 Cobalt-58 Ci 2.16 E-1 i 1.65 E-1 i 1.46 E-2 1.53 E-3 Cobalt-60 C1 2.29 E-2 1 4.34 E-2 i 7.79 E-3 1 3.63 Ee3 Iron-59 C1 1.41 E-4 i

L I

Zinc-65 C1 3.52 E-4 i 1.31 E-3 I

Manganese-54 Ci 2.23 E-3 1 4.20 E-3 3.73 E-4 1

Chromium-51 Ci 9.20 E-3 I 6.24 E-3 i

Antimony-125 Ci I 9.14 E-4 !

t t

Zircoilium-Niobium-95 Ci 1.16 E-2 1.07 E-2 i 7.29 E-5 6.61 E-5 Molybdenum-99 51 I

I i

Tcchnetium-99M C1 i

I Barium-Lanthanum-140 C1 I

I Carium-141 C1 i

t t

l 3.16 E-4 Cesium-136 Ci 4.18 E-4 Sodium-24 Ci i

i i

Iodine-133 Ci 9.79 E-5 1.58 E-4 I 1.04 E-3 Cobalt-57 Ci 4.73 E-4 i 6.33 E-4 5

i Zirconium-97 C1 8.15 E-5 6 7.34 E-5 i

Silver-110M C1 2.16 E-3 6 4.55 E-3

't I

C1 i

il t

Cerium-144 -.. '

Ci 1.57 E-4 I 1.90 E-4

't I

Tin-113

! 3.27 E-2 4.24 E-3 Xenon-133 Ci 1.01 E O 5.39 E-2 Xenon-131M Ci i 3.20 E-3 i i

Xenon-133M Ci 6.25 E-3 i

1.76 E-4 1 853 F-2 Xenon-135 C1 2.00 E-2 1 3.60 E-5 Argon-41 C1 I

i l

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Strontium analysis results were unavailable at the time of submittal.

I Page 1 of 1 Revision 0 1-7

k 12 THP 6040 PER.405 ATTACHMENT IX EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - IST HALF 1985 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT

- BATCH CONTINUOUS Est. Total Quarter Quarter Quarter Quarter Error, %

1 2

i A.

FISSION AND l

ACTIVATION PRODUCTS t

1.

Total Release i

(N:t including j

Tritium, Alpha, G:s s)

Ci 3.12 E-1 2.98 E-1; 1.20 E-1 1.41 E-2 2.62 1

f 2.

Average dilut:d concen-trctica during perird.

pCi/ml 2.60 E-8 1.33 E-8 1.58 E-E 2.54 E-11 3.

Percent of Epplicable Tech.

2.40 E-1 1.32 E-li 1.23 E-3 4.59 E-4 I

Spec. 3.11.1.1 limit.

i B.

TRITIUM Total Release Ci 1.94 E+2 2.02 E+2 3.23 E-1 6.37 E 0 0.22

~

2.

Average dilutad concen-tration during p2ried.

pCi/ml 1.62 E-5 9.02 E-6 4.26 E-10 1.15 E-8 3.

Percent of rpplicable Tech.

5.39 E-1 3.01 E-1; 1,42 E-5 3.82 E-4

,/

I Spec. 3.11.1.1 limit.

I C.

DISSOLVED AND ENTRAINED GASES 1.

Total Release Ci' 1.04 E O 5,71 E-Zi 3.29 E-2 1.?5 E-2 4.46 2.

Average diluted concen-tration during P;ried.

pCi/ml 8.67 E-8 2.55 E-9 4,.fi f all: 1,51 E-11 l

3.

Percent of 4

epplicable Tech.

4.33 E-2 1.27 E-3 2.17 f:$

1,75 E-5 g

~

i Spac. 3.11.1.1 limit.

t 14 e t

,f ?

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12 THP 6040 PER.405 ATTACHMENT IX UNIT BATCH l

CONTINUOUS Est. Total Quarter Quarter Error, *.

Quarter Quarter!

i 1

'2 1

2 D.

GROSS ALPHA RADI0 ACTIVITY 1-Total. Release ci

<1.24 E-3

<1.45 E-3 NA NA NA E.

VOLUME OF WASTE RELEASED Liters 2.24 E+6 3.17 E+6 1.94 E+8 2.16 E+8 2.00 F.

VOLLHE OF DILUTION WATER USED DURING PERIOD Liters 1.20 E+10 2.24 E+1C 7.58 E+11 5.56 E+11 3.48 i

l s..

Ps:

2 of 2 Rev non 0 y_g e

12 THP 6040 PER.405 Attachment X EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT-lST HALF 1985 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

Solid Waste Shipped Offsite for Burial or Disposal 1.

Type of Waste Unit 6 month Est. Total Period Error, %

a.

Spent resins, filter m3 1.66 E+2 1E0 sludges, evaporator bottoms, Ci 7.96 E+2 4E0 I

etc.

b.

Dry compressible waste, m3 2.12 E+2 1E0 contaminated equipment, etc.

C1 1.97 E O 2E0 i

c.

Irradiated components, m3 control rods, etc.

Ci d.

~Other m3 Ci f

I 2.

Esta: ate of Ma;;r Nuclide :

esitic:

a.

CS-137 50 %

CS-134 40 7e CO-58 5%

co-60 5%

b.

Qn Q

c 7

C-3 i~

3.

Solic A ste Dispositi;r- -

of Tran.cortation Dest;:

ion No. of Shipments

_..e Barnweli.

21 4

4 i

Richland,.A I

1 Je,cf Containers UL

'or Sh;.; int sins - 7A

/

E 3porator Bott=s/ DAW nor.

ressible - Strong Tight D.

Compressible -7A Al aere shipped arked

-:tive LSA 5.

Soi:dification Agent

{

~ vaporator bottoms are solidifi a in v.'.ent i

Page 1 of 1 Revision 0 1-10 h-

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9 R

7 2

1 i

4 J

4 2

7 s

2, 5

2 1

1 I

2 1

1 C

4 1

8 4

7 7

I 8

5 8

8 8

1 6

8 E

E 7

E E

E 3

E E

E 0

1 6

3 0

1 7

5 0

4 0

2, 2

2 3

7, 3

5 3

7 3

5 0

7 4

9 7

3 8

4 2

1 5

1 3

C I

4 4

5 4

5 1

5 7

7 6

8 8

7 7

7 8

6 8

8 7

8 6

7 E

E E

E 8

E E

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0 2

0 6

4 5

2 3

1 4

5 8

5 ie 3

6 7

0 9

1 6

0 9

5, 3

5 0

1 2

5 4

0 2

1 1

6 6

C 2

4 2

h 9

4 7

l 2

N 6

7

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6 N

8 8

7 7

0 E

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1

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5 15 4

0 2

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l l

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2 1

2

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3 4

4 1

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9 f

1 2

1 1

6 H

5 2

4, 1

3 I

l 5

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5 8

2 r

K 2

l 5

l 1

l 2

3 1

1 0

2 2

2 3

l E

E E

E

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3 E

E E

D 0

5 7

5 8

6 0

9 1

3 5

3 8

0 6

3 6

8 0

0 9

3 2

5 2

3 5

6 2

7 2

2 8

1 4

6 1

4 4

6 2

9 K

1 2

1 8

5 6

2 6

m 3

0 1

1 1

l 1

I O

O n

l 0

1 O

1 E

E E

E r

E E

E F

E E

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0 2

7 7

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10 5

6 1

8 1

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6 1

7

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1 5

6 5

7 3

3 3

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l I

3 1

1 6

8 u

7 1

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2 2

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12 TEP 6040 PER.405 ATTACEMENT VIII EFFLUENT AND WAS"'I DISPCSAL SEMI-ANNUAL REPCR"' - 2ND HALF 1984 LIQUID EFFLUENTS BATCH CONTINUOUS MODE MODE 3RD 4TH 3RD 4TH Nuclides Released Quarter Quarter Quarter Quarter Strontium - 92 Ci 1.74 E-3 2.25 E-3i i

E 2.29 E-4 Strontium-89 Ci 1.13 E-5 2.63 E-5 Strontium-90 C1 1.31 E-5 i 4.57 E-6 i

Cesium-134 C1 6.85 E-3

+ 3.78 E-24 2.12 E-3i 2.28 E-3 Cesium-137 C1 1.53 E-2 1 4.85 E-24 5.74 E-3i 2.96 E-3 Iodine-131-C1 2.04 E-3 i 2.71 E-34 1.18 E-36 3.23 E-5 Strontium - 85 Ci i G.48 E-a i i

Iron - da C1 9.84 E-4

! 3.9'7 E-4 9.19 E-3 Cobalt-58 Ci 6.30 E-2 I a.36 E-z:

4.39 E-zi

/.6J 6-J Cobalt-60 C1 4.43 E-2 i 5.28 E-2n 1.72 E-21 9.47 E-3 Iron-59 C1 5.69 E-5 i

i i

Zinc-65 C1 7.31 E-4 i 5.34 E-4 Manganese-54 C1 1.79 E-3 1 2.21 E-3a 2.92 E-4 3.32 E-4 Chromium-51 C1 2.86 E-3 t 2.51 E i 1./t c-2.

Antimony - 124 c1 L1 3.14 E-4 i 8.34 E-a Antimony - 125 Zirconium-Niobium-95 Ci 3.14 E-3 i 2.79 E-3 8.47 E-4{ 6.7i E-4 Molybdenum-99 C1 i

i i

Technetium-99M C1 i

e Barium-Lanthanum-140 C1 Cerium-141 C1 i

i i

Tin - 113 ci 1.01 E-4 Cesium-136 Ci Sodium-24 C1 i

Iodine-133 C1 i 8.00 E-4: 2.90 E-5 Cobalt-57 C1 7.42 E-5 2.32 E-4I Zirconium-97 C1 7.36 E-5 4.31 E-5i 5.48 E-3*

t Silver-110M C1 4.94 E-3 Cerium-144 C1 i

i i

i Krypton - 85 Ci 6.46 E-3 i 1.91 E-2-i i

Xenon-133 CI 6. / / Eo i 2.// E ui 3.zz t-zi 2.ao c-3 Xenon-131M C1 5.z/ E-4 i

Xenon-133M C1 1.13 E-1 2.20 E-2 i Xenon-135 C1 2.30 E-1 6 5.06 E-3 1.49 E-ai 1.49 E-a

-l Argon-41 C1 Krypton - 85m c1

/.iz E-4 i

Page 1 of 1 Revision 0 1-13

12 THP 6040 PER.405 ATTACHMENT IX i

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 2ND I*ALF 1984 REVISED LIQUID EFFLUENTS - SUMMATION Of ALL RELEASES UNIT BATCH j

CONTINUOUS.

Est. Total Quarter Quarter!

Quarter Quarter Error, %

3 4

A.

FISSION AND ACTIVATION PRODUCTS 1.

Total Release

-(Not including Tritium, Alpha, G:s:s)

Ci 2.18 E-1 2.88 E-1 7.21E-2 :3.29 E 2 5.91 l

2.

. Average diluted concen-1

.tration during paried.

pCi/ml 7.45 E-9 1.46 E-8 8.43E-ll

3. 8 3 E-lI.

3.

Percent of applicable limit.

3.69 E-2 9.30 E-2 7.41E-4 1.21E-4 I

I B.

TRITILM Total Release Ci 4.32 E+2 5.59E+2 6.44E-1I7.06E-1 0.24 2.

Average l

diluted concen-i tration during p2riod.

pCL/mi'l. 47 E-5 2.84E-5 7.53E-10 8.21E-10!

t 3.

Percent of applicable limit.

4.91 E-1. 9.46E-1 2.51E-5 2.74E-5 {

l I

j!

C.

DISSOLVED AND ENTRAINED GASES i

I 2.82 E O 5.22E-2 l 5.57E-3 5.54 1.

Total Release Ci 7.12 E O l

j 2.

Average l

j diluted concen-tration during i

6.llE-ll 6.48E-12 p2riod.

pCi/ml 2.43 E-7 1.43E-7l l

'3.

Percent of l

applicable limit.

1.22 E-1 7.16E-2, 3.05E-5 3.24E-6 Page 1 of 2 1-14 Revision 0

(T i

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J 1

1

y-L APPENDIX 1.2 4

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES l'OR FIRST QUARTER OF 1985 i

i

=

f-I I

l I

b f

{

The following~ distances were used in the calculation of the maximum individual doses:

SECTOR - DIRECTION SITE BOUNDARY (HETERS)

NEAREST RESIDENCE (METERS)

B - I4NE 617 814 C - NE 789 1052 0 - ENE 1497 1852 E-E 1274 1705 F - ESE 972 1628 G - SE 629 914 H - SSE 594 1093 J-S 594 863 K - SSW 629 770 1-15

12 THP 6040 PER.405 Attachment XII

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES - IST OVARTER 1985

' ESTIMAIw LOCATION

% OF Quarterly APPLICABLE DOSE AGE DIST DIR APPLICABLE LIMIT EFFLUENT ORGAN (MREM)

GROUP (M)(Toward)

LIMIT (MR)

Liquid Total Body 1.18 E-1 Adult Receptor 1 7.87 E 0 1.5 Liquid Liver 1.72 E-1 Teen Receptor 1 3.44 E 0 5.0 Noble Gas Air Dose (Gamma-mrad) 1.21 E-1 All 594 S 2.42 E 0 5.0 Noble Gas Air Dose 4.29 E-1 All 594 S 4.29 E 0 10.0 (Beta-mrad)

Noble Gas Total Body 2.85 E-2 All 814 NNE 5.70 E-1 50

'!!!j#

Noble Gas Skin 1.00 E-1 All 814 NNE 6.67 E-1 Iodines and Thyroid 4.12 E-1 Child 914 SE 5.49 E O 7.5 Particulates i

i Page 1 of 1 Revision 0 1-16

\\

~

el FOR HECEPI(R 64 I

73f4L LIQUID DOSE ACCUNULATIONSanENI STARY DATE 95 l i I Ese DATE SE 33:24 SONE liver T.OODY THTSD KIDeEV LtesG G1-LLI SICIN WATER 7.2E-8 7 5.SE-86 5.EE-SS 8.4E-SS 5. sE-e8 4.SE-tG 5.SE-SS S.SE*00 AOutf 7.SE-87 4.4E-SE 3.SE-SE S.EE-OS 3. 7E-SS 3.4E -96 4.0E-e6 S.K+0S

'E E N 2.SE-SS 8.5E.-86 S.9E-SS I.4E-SE 7.8E-GS 5.SE-98 S.ef-86 S.8E *SS CHILD 18Fasef 2.lE-86 S.eE-OS 6.7E-95 l.K-95 S.SE-OS S.M-95 S.5E-e6 S.0E*e8 SHORE f.f E-07 f. lf-07 1.1E-87 f. tE-07 1.1E-87 1. tE-07 l.N-87 1.IE-87 ADULT E.K-07 E.GE-87 5.K-47 E.EE-47 5.K-47 5.9E-87 5.K-87 6 8E-07 TEEN CHILD 1.2E-87 8.2E-97 1.2E-01 8.N-47 f.N-47 8.N-47 f.N-87 5.4E-97 INF ANT S.SE+0S e.K+88 8.gE+ee 8.K+40 8.Keeg S.0E+49 9.K+0S 5.OE*00 FW SPT FISH f.tE-84 4. M -98 5.5E-e4 1.eE-45 e. K -OS 0.8E+49 t.tE-84 t.SE-84 ADULT

l. IE-84 1.7E-94 S. E-SE 4.K-98 5.EE-e5 2.N-SE S.N-55 S.SE+et TEEN CHILD l.4E-64 1.EE-84 2.EE-SE 4. IE-95 4.K-05 1.7E-GE 2.N-95 f.K+98 INFANT 3.K +et 9.eE+0e e.eE+ee 0.eE+0S 8.8E+ee 0.0E+GS 8.5E*e8 0.0E+0e ENTER: (stETune43 CONTIDSJE.(901 staRY OWR. TEX 1 EXf f i

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3 DOSE iTPE ENIER: tGA1 G4MM4 (EE 3 SESA teEtuRN) GO e4CK TO PREVIOUS OPit0N G4 1 1 e 70 e5 33124 5 DATES OF TOTAL AIR DOSE ACCUMUL4Tl0N ARE Fut0M e51 DOSE ACCUMULATION FOR Ge#994 RAD esDIRECit04 FROM N

.2145E-04 l.4724E-85 S.544JT-86 3.7264E-06 2.5472E-86 8.200 E-06 4.305tE-07 2.02GIE-e7 8.248tE-e7

7. 3083E -08 seDIRECTION FROM NNE 4.828tE-85

5. 4 3SeE-SS 2.5el5E-es 1.4eSeE-08 t.8182E-e6 5.tel5E-07 1.ee37E-87 0.124eE-te 5.73e4E-te 3.5337E-te eeDIRECTION FROM NE 1.055tE-84 1.2374E-es 5.4eeEE-86 3.1287E-06 2.l22 K-eG 0.9530E-e7 3.425 X-87 1.580SE-47 0.Se83E-ee 5.637tE-te seDIRECT!04 FROM E E 6.58SSE-85 7.972M-es e.655M-46 2.5327E-48 f.478M -SS 7.195M-87 2.6301E-87 1.27e4E-67 e.eSISE-te

4. ele 5E-08

- DIRECTION FROM E

3. 333lf -84 1.SS4tE-es 7.7ES4E-es 4.575eE-e6 3.te2et-es l

i l.SSlet-es S.04SM-e7 2.0258E-47 5.SSSSE-47 8.l58tE-87

eDIRECTION FROM ESE 0.lE47E-85 f. e837E-95 4.98l5E-es 2.e445E-e8 t.9524E-GS 0.3te7E-e7 3.3082E-87 1.SteeE-e7 lose 95E-47 S.SSSK-64 l

eeDIRECTIOps FROM SE l.28 tee-94 8.43 tee-85 S.648tE-es 3.822eE-e8

2. 72'AE-GS l

I.33tE -es 5.9558E-87 2.4e58E-07 1.5800E-97 9.7742E-ee 1

en0IRECTION FROM SSE 8.0834E-85 1.0682E-OS

4. 8290E-38 2.8230E-SS I.eSSSE-46 0.7etSE-87 3.SGSIE-e7 8.el4K -87 1.1530E-47 7.tSIK -Se se3IRECTION FROP S H

7.575eE-e5 e.eStEE-SS 4.4874E-es 2.8705E-SS 1.9935E-eG e

0. 65 t M-8 7 3.e644E-07 1.941 4 -87 1.25eSE-e7 7.e4eK-08 seCIRECit0N FROM ESS 1.2254E-e4 1.4eetE-e5 7.8419E-96 4.200SE-e6 3.ee9tE-es 1.4905E-SS 5.05eSE-87 2.9tS4E-47 1.SSO2E-07 1.1710E-e7

)

- 0tRECTID'e FROM sw 8.429tE-e4 5.715eE-SS 7.e t SM-es 4.537eE-46 3.83S3E-06 t.5204E-SS 5.5400E-07 2.735 4-87 1.7213E-e7 I.e582E-47 se0lRECTION FROM wSW 1.5693E-84 l.e248E-95 S.2262E-es 4.7505E-46 3.'2505E-OS I.555SE-e6 5.657 X-87 2.7ee4E-07 t.Sel4E-s7 4.9213E-e7 eeDIRECTION fit 0M W t.1717E-04 8.3869E-SS 6.212SE-OS 3.5474E-es 2.4425E-86 l.lSteE-96 4.tel3E-87 8.Ge73E-47 l.2345E-87 7.3042E-OS se0IRECTION F810M WNW 9.7327E-85 9.eSOM-SS 4.7681E-e6 2.734eE-06 1.SS27E-86 e.7420E-87 3.llS3E-87

1. 4 e30E-8 7 9.2447E-ee 5.5427E-te se0IRECTION FROM hv S 03:3E-85 7.5845E-es 3.4053E-06 1.967eE-06 1.3453E-06 S.3682E-87 2.2994E-97 1.0000E-47 S.790eE-te

4. 0943E-te eeDIRECTION FROM NNW 5.0744E-05 S.7CSEE-86 3.elseE-86 l.73SSE-86 1.200SE-06 5.eS82E-87 2.les2E-87 1.eS99E-07 S.796tt-ce 4.19EeE-te DISTANCES USED IN CALCULATIONS 504.0 2416.0 4e28.0 SS30.8 7248.0 12867.8 24l35.8 40225.0 56315.8 esses.e ENTER: (RETURN) WHEN READY TO CONTINUE

i f

i e1 DOSE TiPE ENTERS (648 GAMMA ISE)

SEIA (REtuR48 GO GACK TO PmEvtous OPil0N K

DATES OF TOTAL AIR DOGE ACCUMULATION ARE FROPI SE I I I e 70 e5 33124 e l

i DOSE ACCumutAT!04 F04 KTA e40 seOIRECT LON FROM 94 l

4. 2830E -04 5.2842E-eG 2.3 tele-85 1.32 elf-85 0.027tE-SS a

d 4.20sSE-06 1.52S E-05 7.202SE-87

4. 4304E-47 2.83eEE-47 enDimECT!ON FROM NME l.5221E-44 l.790ef-SE

'7.steX -06 4.564E-OS 3.lS27E-SS l.5407E-SE 5.7407E-97 2.77eSE-07 f.734K-57 8.053SE-07 0

se0IRECTION FROM NE 1

3.37eSE-94 3.0000E-SE l. 75ESE-SE l.teelE-85 S.7ellE-e8 3.14SIE-eS l.ee30E-06 5.074M-97 3.Ge33E-87 l.70eSE-47 septeECTION FAON E8E 2.4825E-04 2.8300E-SE l.3EleE-95 7.0000E-08 5.44eEE-es 2.627eE-SS 9.?Sl2E-07 4.73SE-07 2.eeESE-07 1.0230E-47 ee0IRECTION FSOM E j

5.el41E-84 S.27e M-95 2.0273E-SE l.7271E-SE l.2SilE-GE 1

5.se2eE-SE 2.244M-05 l.leetE-SS 7.0211E-47

4. 330lE-47

?

seDIRECTION FIlON ESE i

3.leeX -04 3.7534E-SE I.0022E-SE e.7840E-86 E.883SE-48 i

3.le87E-06 l.14tX-SE 5.4225E-07 3.362eE-47

2. mamar -87 seOthEtit0N FROM SE l

4.5223E-44 E.3estE-SE 2.5eEFE-SE I.477M-SE 3.825 E-GE 5.0130E-SS 1.Ge2E-SS e.357 E-87

5. eel 3E-47 3.6790E-47

}

seeleECil0N FROM SSE 3.2488E-e4 3.e75EE-SE l.7720E-SE I.0320E-SE 7.171E-98 3.525SE-e8 I.332E -es S.524eE-07 4.13eK -97 2.5620E-47 seeleEtiteel FRON S 2.0684E-44 3.IGGIE-SE 1.54SSE-SE 0.4le7E-OS 6.See2E-es g

w 3.410E-SS I.374 E-06 S. ele 6E-87 4.4Sl4E-07 2.94 t M-47 j

g j

se0IRECTION FRtpl Sew o

4.10llE-44 5.8Ee4E-SE 2.4tteE-05 l.452SE-GE I. ele 2E-95 l

5.eSe4E-GS 1.070M-SS 9.037K-07 S.200SE-07 3.040lE-4 7 se0IRECT104 FSOM SW 5.28 43E -84 S.2736E-OS 2.eGe7E-SE I.6527E-95 1.44e4E-SE E.El4K-88 2.9404E-es e.eeeeE-87 S.1951E-87 3.779EE-47 es0IRECil0N FROM WSW 5.SeeM-44 5.8736E-SE 2.630M-05 1.521eE-SE 1.e42E-GE 4.0724E-eS I.e84SE-e6 0.6376E-47 5.306SE-87

3. 258K-47 L

l

- OISECTION FNOM w 4.2SS7E-e4 5.8448E-e5 2.252M-GE l.2ee7E-SE e.eleEE-SS i

l

4. lS70E-es I.4eeM-86 7.045eE-47 4.362eE-07 2.604eE-47 I

- 0:nECTION FNOM WNe 3.7870E-04 4.0531E-SG l.7054E-4G 1.020M -86 S.Se5eE-GS 3.2613E-e8 1.1521E-06 5.45SSE-97

3. 387 7E-07 2.0'sM-8 7 seDiHECTION FROM Nw l

2.5477E-04 2.e244E-SS 1.250$E-95 7.2440E-es 4.etSEE-eS 4

2. 3163E -GS e.2+eSE-47 3.Se21E-07 2.4102E-97 1.4468E-97 1

se0!RECit04 FROM NNW 2.*E10E-04 2.4828E-85 1.073tE-SE 6.1545E-SS 4.2487E-e6 2.9563E-SS 7.GG7tE-87 3.70l?E-97 2.3447E-e7 1.44 tee-87 i

DISTANCES USED IN CALCULATIONS 1

504.0 2416.0 4528.0 5630.0 7240.0 j

12067.5 24135.8 4e225.0 56315.8 09550.9 l

i ENTER: LRETURN3 w*.EN READY TO CONF!NUE 4

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ML20134K562

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