ML20114C805

Semiannual Radioactive Effluent Release Rept for Jan-June 1992

ML20114C805
Person / Time
Site:	Sequoyah
Issue date:	06/30/1992
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20114C800	List: ML20114C797 ML20114C805 ML20114C813
References
NUDOCS 9209030238
Download: ML20114C805 (20)

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-ENCLOSURE 1

. SEMIANNUAll EFFLUENT RELEASE REPORT FOR1T!!E- PERIOD 0F JANUARY 1 TO JUNE 30, 1992 (S52 920818 150)

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4 EFFLUENT AND UASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION Ist HALF 1992

1. REGULATORY LIMITS A. Gaseous Effluents

1. Dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

a. Noble gases:- Less than or equal to 500 meem/ year to the total body.

- Less than ne equal to 3000 mrem / year to the skin.

b. Iodine-131, iodine-133, tritium, and all radionuclides in perticulate form with half-lives greater than 8 days:

- Less than or equal to 1500 mrem / year to any organ.

2. Air dose due to noble gases released in gaseous offluents to areas at and beyond the site boundary shall be limited to the following:

a. Less than or equal 5 mead for gamma radiation and less than or equal to 10 mead for beta radiation during any ca'endar quarter,

b. Less than or equel to 10 mead for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.

3. Dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives

,- greater than eight days in gaseous offluents released to areas at

and beyond the-site boundary shall be limited to the following:

a. Less than or equal to 7.5 meem to any organ durxng any calendar qucrter.

b. Less than or equal to 15 mrom to any organ during any calendar year.

B. Liquid Effluents

1. The concentration of radioactivity released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of~ Federal Regulations, Part 20 (Standards for Protection Against Radiation), Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/ milliliter (uci/ml) total activity.

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T EFFLUENT AND WAST 2 DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALF 1992

2. The dose or dose commit. ment to a member of the public from ra notctivity in liquid effluents released to unrestricted areas '

sha.. be limited to:

a. Less than or equal to 1.5 meem to the total body and less than or equal to 5 meom to any_ organ during any calendar quarter.

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b. Less than or equal to 3 mrom to the total body and less than or equal to 10-mrom to any organ during any calendar year.

2. MAXIMUM PERMISSIBLE CONENTRATION A. Liquids

• 1. The maximum permissible concentrations (MPC) for liquids are those listed in 10 CFR 20, Appendix B, Table II, Column 2, with the most restrictive MPC being used in all cases. For dissolved and entrained gases the MFC of 2.0E-04 uCi/ml is applied. This MPC is based on the-Xe-135 MPC in-air (submersion dose) converted to an .

equivalent concentration in water as discussed in the Tnternational Commission on Radiological Protection (ICRP),

Publication 2.

B. Caseous

1. The maximum permissible dose rates for gaseous releases are

' defined in plant offsite Dose Calcelation tianual (ODCM).

a. Noble gas dose rate at the site boundary:

• - Less than or equal to 500 mrem / year to the total body,

- Less than or equal to 3000 mecm/ year to skin.

b. Todine-131,-iodine-133, tritium, and particulates with half-lives greater than eight days dose rate at the site boundary:

- Less than or equal to 1500 mrem / year to any organ.

3. AVERACE ENERCY Sequoyah's ODCM limits the dose equivalent rates due to the release of -

fission and activation products to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 meem/ year to the skin.

'Therefore, the average beta and gamma energies (E) for-gaseous effluents as described in Regulatory Guide 1.21, ;suring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive L Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear

-Power Plants," are not applicable.

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• These values are used as applicable limits for liquid and gaseous

, effluents.

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EFFLUENT ~AND' WASTE DISPOSAL SEMIANNUAL REPORT -

SUPPLEMENTAL INFORMATION.

-l Jst HALF'1992 l ' 4; Measurements and Approximations of TotaliRadioactivity

' NOTE! Every effort is mado to ensure that offluent releases from Sequoyah are conducted such that all Offsite Dono Calculation

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Manual (ODCM) Lower Limit of Detection (LLD) values are met.

- :Whenever an' analysis does not identify a radioisotope, a "0.00E-01 Ci" is recorded for the release. This does not necoscarily mean

' that no activity was released for that particular radionuclido, l but that the concentration was below the ODCM and analysis LLD.

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-Refer to Tablos A and B for estimaten of these typical LLD values.

a. Fission and Activation cases Airborno offluent gaseous activity is continuously monitored and recorded. Additional grab samples from the shield buildint,, auxiliary building, service building, and condensor vacuum exhuusts are taken l and analyzed at least monthly to datormine the quantity of noble gas activity rolsased for tho month based on the averago vont flowratos recorded for'the sample period. Also,'nobic gas samples are collected

' and evaluated for ths shield and auxiliary buildings following  !

c startup, shutdown..or rated thermal-power chango excooding 15 percent  ;

l within one hour -(sampling only requirod if dose equivalent 1-131 concentration in.the priniary coolant has increased more than a factor l of-3 or the noblo-gau activity monitor shows that the containment ~

activity has increased more than a factor.of 3), i The quantit.y of noble gao9s released through the shield and auxiliary building exhausts &o to purging- or venting of containtaont and

- releases of;wanto 1;as decay tanks'are also determined. l Theitotal noble' gas activity released for the month is then determined

-by sumning all_ of the . activity released from cach vont for all sampling periods,.the activity released from' purging or venting of l l.-

' - contaltunent, and :the activity' released from waste gas decay tank (s) .

l b, Iodines and particulates _

l IIodino and pahticulate activity is continuously sampled. Charcoal and particulato samples are taken from the shield and auxiliary building exhausts and analyzed at least weekly to determine the total activity

! released from the plant based on the averago vent flowrates recorded for sampling-porlod.

l- Also,' particulato and charcoal samples are taken from the auxiliary j and : shield building lcxhausts onco per' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 2 days following l l startup, shutdown, or a ratod' thermal power change exceeding 15 i l  ;

L percent within one hour. The quantity of lodino and particulate '

L released from each vont during each sampling period is then determined using the average _ vent-flowrates recorded for the sampling period and activity. concentration.

The total particulato and iodine activity released for the month is l l

then ' determined by sunning all of the activity released from the shield and auxiliary building exhausts for all sampling periods. l 1

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EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALP 1992

. A'. lMonsurements atui Approximation of Total Radioactivity (continued)

c. . Liquid Effluents (1) Batch (Radvasto and during periods of primary to secondary leakago, condensato regenerants to. cooling tower blowdown')

Total gance isotopic activity concentrations are dotormined on each batch of liquid offluent prior to roloaso, The total activity of a released batch is determinod by summing each nuclide's concentration and multiplying by the total volumo discharged. The total activity ecloased during a month'is than dolormined by summing the activity contentLof.each-batch discharged during the month.

(2) Continuous Rolmasos and periodic Continuous Rolot:en (Condensato regonorants, turbino building sump and steam generator blowlown)

Total gamma isotopic activity concentration is dotormined daily on a composito sample from the condonsato system and turbine building sump and wookly for staan concrator blowdown. The total activity of the continuous relonso la dotormined by summing ouch nuclido's concentration and multiplying by the total volume discharged. The '

total activity released during the month is then datormined by summing the activity content of each daily and wookly composite for the month.

5. Batch- Valuo , _ _ _

Units quarter Quarter lot 2nd

a. Liquid

1. Number.of batches released-(Radwasto only) 106 69 Each

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L .2.. Total-time period for batch releases 15,115 9,495. Minutos L

[ 3. Maximum time period for a batch releaso 182 167 Minutos

4. Avorago timo period for batch

.roicasos 142 138 Minutos

5. ' Minimum' stream flow during perloos of offluent _into a flowing stream cubic foot /socond (CFS) 37290 19039 CFS i

L il b. Gaseous-l 163 142 Each L 1~. Number of batches colossed

~2. _ Total time period for batch 21,340 10,768 Minutes o .coloases

3. Maximum timo period for a batch releaso 1,620 1,200 Minutos

4. Average time period for batch releases 131 76 Minutos

5. Minimum time period for a batch releaso 10 19 Minutos l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION let HALF 1992

6. Abnormal Releases _ _

Valuo Units Quarter Quarter 1st 2nd

'a. Liquid 0 0

-(1) Number of Roloases (2) Total Activity Released 0.00E-01 0.00E-01 C1 3

'b. Casoous (1) Humber of Roloases- 0 0

-(2) Total I.ctivity Released 0.00E-01 0.00E-01 Ci INOPERABLE INSTRUMENTATION Pursuant to ODCH Section 1.1.1 and 1.1.2, the following information is provided concerning radioactivo -offluent monitoring instrumentation which was inoperable for greater than 30 consecutive days during the period January 1, 1992 through June 30, 1992.

The Essential-Raw Cooling. Water (ERCW) radiation monitors consists of two monitors for each unit. During the timo framo of 4/11/92 until 7/12/92 the Unit 1 radiation monitors (1-RM-90-133/140) were intermittently inoperable.

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On 4/20/92 the-flow switch 0-FIS-90-133 malfunctioned and a work requent was

written.for repair, however replacement could not be obtained with proper flow range requirements. Sinco ERCW rad monitors 0-RE-90-133 and 140 sharo. common control room alarm windows, both monitors woro declared inoperabic (thorofore the Train A ERCW rad monitors are inoperable). While attempting to valve out samplo flow to RE-90-133 and re-route total flow to cedundant radiation monitor HE-90-140 the samplo pump breaker tripped. This was corrected by realignment.of'the pump--and motor. On 7/12/92, 0-RE-90-140 was placed back in service and main control-room alarm was cleared.

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l EFFLUENT AND WASTE DZSPOSAh SEMIANNUAL REPORT

-l SUPPLEMENTAL INFORMATION let HALF 1992 i

l 1

INOPERABLE INSTRUMENTATION (Continued)

On 3/24/92, Unit 2, Containment Purge 'B' Train flow instrumentation became inoperable for flow testing. The flow testing identified that this instrument was out of calibration. The -subsequent rework of this instrumentation identified that the sensor to transmitter match required by the original manufacture had not been maintained. This ott of calibration condition was on the high side of the tolerance band and consequently any release from the Unit 2 'B' train containment purge was conservative. As a result of this finding, verification of all shield building flow instrumentation was performed which required greater than 30 days to complete. The table belo-contalas the results of this evaluation.

l Flow Element i Problem i Recommendation j l 1-FE-90-400Al-A4 i Cable tags labeled l Relabel tags in accordance l l CNMT Purge A l incorrectly. I with drawing CCD#1-45W1620-17. l l 1-FE-90-400B1-B4 l Cable tags labeled l Relabel tags in accordance l

-l CNMT Purge B l incorrectly. I with drawing CCD41-45W1620-17. l l 1-FE-90-400Cl-C4 l Sensors C2 & C3 not l Perform as found flow testing. l l AB013. Train A l connected to asso- l connect senss e to associated l l l ciated transmitter. l transmitter, and relabel cable l l l Cable tags labeled l tags in accordance with l l l incorrectly. l drawing CCD#1-45W1620-17. l l 1 l Perform as left flow testing. l l 1-FE-90-40001-03 l None, l None. l l ECTS I I l l 2-FE-90-400Al-A4 -l Sensors A1, A2, J,.1 Perform as found flow testing, l l CNMT Purge A l and A4 not connected l. connect sensor to associated l l l to associated l transmitter, and relabel cable l l l transmitter. Tags j tags in accordanen with l l l labeled incorrectly.l drawing CCD#2-4SW2020-7, l l l l Perform as Icft flow testing. l l 2-FE-90 400B1-B4 l Sensors B1, B2, B3, l Since as found data obtained l l iCNMT Purge B l and B4 not connected l by WR C007374 and flow element i l i to associated l was replaced, relabel cable l

-l l transmitter. Tags l tags in accordance with l l l labeled incorrectly.l drawing CCD#2-45W2620-7. l l 1 i Perform as left floyLienting. l l 2-FE-90-400Cl-CA l Cable tags labeled 1 Retabel tags in accordance l l ABGTS. Train B  ! incorrectly. I with drawing CCD#2-45W2620-7. l l 2-FE-90-40001-D3 l Cable tags labeled' l Relabel tags in acc- iance l l EGTS I incorrectly, _

l with drawing CCD#2-44.2620-7. l l

EF?LUENT-AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1992 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1st 2nd

-A. Fission and Activation Unit Ote  % Error .0tr  % Error _

Products

1. Total Released Curies 3.21E-01 11.8E+01 7.12E-01 11.8E+01

2. Average Diluted Conc.

During Period of All Identified Isotopes uCi/ml 1.86E-07 7.44E-07

3. Percent of Applicable Limit-(IMPCsi)  % 8.11E-01 1.45E+00 NOTE: Percent of applicable limit is bksed on identified isotope concentration after dilution, related to their appropriate-MFC concentration and sum of all the isotope fractions compared to 1.0, B. Tritium

1. Total Released Curies 3.55E+02 11,8E+01 2.27E+02 11.85,+01

2. Average Diluted uC1/mi 2.06E-04 2.36E-04 '

Conc. During Period

3. Percent of Applicable Limit (3.0E-03 uCi/ml)  % 6.87E+00 7.87E+00 C. Dissolved and Entrained Cases

'1. Total Released curies 2.79E-01 13.9E+01 1.21E-02 i3.9E+01

2. Averago Diluted uC1/ml 1. 6.:J-0 7 1.26E-08 Conc. During Period

3. Percent of Applicable Limit (2.0E-04 uC1/ml)  % 8.10E-02 6.29E-03 D. Gross Alpha Radioactivity

1. Total Released curies 0.00E-01 12.0E+01 0' 00E-01 -12.0E+01 E. Volume of Waste Released (Before Dilution) Liters 3.30E+07 14,0E+00 2.94E+07 14.0E+00 F. Volume of Dilution Liters 1.69E+09 11.1E+01 9.32E+08 ' il.1E+01 Water for Period

i 1 - EFFLUENT AND BASTE DISPOSAL SEMIANNUAL REPORT .

1st HALF 1992- 1 LIQUID EFFLUENTS - TOTAL PLANT DISCRARGE l

G. - Nuclido - Summa,ry, (Note: Refer to Table A for ODCM nuclides reported as 1

0. 00 E- 01) -- j Required by ODCM/Others Fission and Activation Products

. Continuous Mode Batch Mode Nuclide Unit Quarter quarter Quarter Quarter 1st 2nd let 2nd

1. Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 1.16E-03

2. Strontium-90 C1 0.00E-01 0.00E-01 0.00E-C1 2.86E-04

3. Iron-55 Ci 2.64E ,03 2.34E-02 4.37E-02 7.64E-03

4. Manganese-54 Ci 0.00E-01 0.00E-01 2.01E-03 3.91E-03

5. Cobalt Ci 0.00E-01 0.00E-01, 1.34E-01 4.315-01

6. Iron-59 Ci 0.00E-01 0.00E-01 4.84E-03.

3.50E-03

7. Cobalt-60 C1 2.14E-06 0.00E-01 la 72E-02 3.00E-02

8. Zine Ci 0.00E-01 0.00E-01 0.00E-01 6.39E-04

9. Molybdenum-99 C1 1.04E-06 0.00E-01 0 00E-01' O.00E-01

10. Iodine-131 Ci 1.74E-06 1.12E-06 2;46E-03 9.56E-04

11. Cesium-134 -Ci 2.38E-04 4.00E-05 1.28E-02 1.84E-02

12. Casium-137 C1 2.52E-04 1.24E-04 1.26E-02 1.45E-02

13. Cerium-141 Ci 0.00E-01 0.00E-01_ 4.87E-05 0.00E-01

14. Cerium-144 Ci 0.00E-01 0.00E-01 7.18E-04 1.76E-04

15. Antimony-125 Ci 0.00E-01 0.00E-01 4,27E-02 1.118-01

16. Cobalt-57 Ci 0.00E-01 0.00E-01 5.79E 1.58E-03

17. Chromium-51 Ci 0.00E-01 0.00E-01 1.99E-02 4.17E-02

18. Niobium-95 Cl 0.00E-01 0.00E-01 5.90E-03 6.41E-03 1

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT let HALF 1992 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

Continuous Mode Batch Mode Nuclide Unit Quarter Quarter , quarter guarter 1st 2nd 1st __2nd

19. Iodino-133 Ci 0.00E-01 0.00E-01 2.60E-04 1.27E-04 i

20. Zirconium-95 Ci 0.00E-01 0.00E-01 3.47E-0 3.66E-03

21. Technetium-99m C1 1.04E-06 0.00E-01 0. C 37 _LL 0.00E-01

22. Ruthenium-103 Ci 0.00E-01, 0.00E-01 2.83E-04 1.898-04

23. Tellurium-132 Cl 0.00E-01 0.00E-01 5.29E-04 7.59E-05

24. Antimony-124 Ci 0.00E-01 0.00E-01 4.32E-03 9.81E-03 l

25. Lanthanum-140 Ci 0.00E-01 0.00E-01 1.43E-03 2.89E-04

26. Cesium-136 - Ci 0.00F-01 0.00E-01 1.11E-04 3.98k-04

27. Sodium-24 Ci 0.00E-01 0.00E-01 5.06E-05 1.09E-04

28. Iodine-135 Ci 0.00E-01 0.00E-01 4.28E-05 0.00E-01

29. Strontium-92' Ci 0.00E-01 ,0.00E-01 5.26E-05 .1.13E-04

30. Yttrium-91 Ci 0.00E-01 0.'0E-01 2.,16E-03 0.00E-01,

31. Iodine-132 Ci 0.00E-01 0.00E-01 8.89E-04 3.01E-05

32. Cesium-138 Ci 0.00E-01 0.00E-01 1.85E-05, 4.66E-05

33. Cerium-143 Ci 0.00E-01 0.00E-01 4.13E-06 0.00E-01

34. ' Silver-110m Ci 0.00E 0.00E-01 1.44E-04 1.13E-04

35. Iodine-134 Ci: 0.00E-01 0.00E-01 1.26E-05 2.84E-05

36. Barium-140 Ci 0.00E-01 0.00E-01 3.21E-65 0.00E-01

37. Manganese-56 Ci 0.00E-01 0.00E-01 8.10E-06 1.11E-05

38. Niobium-97 Ci 0.00E-01 0.00E-01 1.85E-04 1.21E-04

39. Argon-41 C1 0.00E-01 0.00E-01 0.005:-01 6.92E-05 t -

D EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALE,1992 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

Continuous Mode Batch Mode Nuclide Unit Ouarter Quarter Quarter guarter 1st 2nd 1 s t __ 2nd

40. Tellurium-129m Ci 0.00E-01 0.00,E-01 3.80E-03 2.96E-03

41. Nickol-65 Ci 0.00E-01 0,.00E-01 0.00E-01 3.80E-05

42. . Neptunium-239 Ci 0.00E-01 0.00E-01 6.94E-05 0.00E-01 Total for Period' C1 3.14E-03 2.36E-02 3.18E-01 6.91E-01 C. Nuclide jummary .( NOTE: Refer to Table A for ODCM nuclides reported as 0.00E-01)

Required by ODCM/Others Dissolved and Entrained Noble Cases Continuous Mode Batch Mode ~

Nuclide Unit Ouarter. Quarter Quarter Quarter I 1st 2nd 1st 2nd

1. Krypton-87 Ci 0. 00E -01 0.00E-01 0.00E-01 0.00E-01

2. Krypton-88 Ci 0.00E-01 0.00E-01 9.288-06 0.00E-01

3. Xenon-133 Ci 0.00E-01 0.00E-01 2.62E-01 1.05E-02 A. Xenon-133m Ci 0.00E-01 0.00E-01 3.75E-03 A.41E-05 -

'5. Xenon-135 Ci. 0.00E-01 0.00E-01 6.24E-03 l'19E-03

6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0'00E-01

'7. Krypton-85m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 8 Xenon-131m Ci 9 00E-01 2.57E-04 6.62E-03 0.00E-01

9. Xenon-135m Ci 0.00E-01 0.00E-01 1.89E 0.00E-01

10. Krypton-85 Ci 0.00E-01 0.00E-01 'O.00E-01 0.00E-01 Total for' Period Ci 0.00E-01 2.57E-04 2.79E-01 1.17E-02 4

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1992 TABLE A LIQUID " TYPICAL LLD" EVALUATION (1)

At(2)

Nuclido ODCM LLD 15 min 30 min 1 hr 2 hr Manganeso-54 5.0E-07 9.12E-09 9.12E-09 9.12E-09 9.12E-09 Cobalt-58 5.0E-07 8.21E-09 8.21E-09 8.21E-09 8.21E-09 Iron-59 5.0E-07 1.62E-08 1.62E-08 1.62E-08 1.62E-08_

Cobalt-60 5.0E-07 1_.,,08 E-08 1.08E-08 1.08E-08 1.08E-08 Zine-65 5.0E-07 2.14E-08 2.14E-08 2.14E-08 2.14E-08 Molybdenum-99 5.0E-07 5.24E-08 5.25E-08 5.28E-08 5.34E-08 ,

Cesium-134 5.0E-07 9.82E-09 9.82E-09 9.82E-09 9.82E-09 Cesiumm137 5.0E-07 9.31E-09 9.31E-09 9.31E-09 9.31E-09 Cerium-141 5.0E-07 1.06E-08 1.06E- 08 1.07E-08 1.07E-08 Corium-144 5.0E-06 4.03E-08 4.03E-08 4.03E-08 4.03E-08 Iodine-131 1.0E-06 7.28E-09 7.28E-09 7.30E-09 7.32E-09 Krypton-87 1.0E-05 1.62E-08 1.85E-08 2.43E-08 4.20E-08 Krypton-88 1.0E-05 2.13E-08 2.27E-08 2.56E-08 3.27E-08 Ienon-133 1.0E-05 2.03E-08 2.04E-08 2.0.r -08 2.05E-08 Xenon-133m 1.0E-05 S.05E-08 5.07E-08 5.10E-08 5.17E-08 Xenon-135 1.0E-05 5.60E-09 5.70E-09 5.93E-09 6.40E-09 Ienon-138 1.0E-05 2.82E-08 5.87E-08 2.55E-07 4.79E-06 Q ~31- \

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______.-.-_--_-.-_----_-_-__------_---_-__----.--.---.-----_.-_.---_------------_---J

EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT lat HALF 1992 TABLE A LIQUID "TYPICA1. LLD" EVALUATION (1)

(Ct e.c inued)

Nuclide ODCM LLD Iypteal LLD Tritium 1,0E-05 1.0E-06 Cross Alpha 1. 0E-07 2.0E-08 Strontium-89 5.0E-00 2,0E-08 Strontium-90 5,0E-08 1,0E-0E 1ron-55 1,0E-06 3.0E-01 -

NOTESt (1) LLD values are in uCi/ml. Sample analysos are performed to ensure that ODCM LLD limits are mot. These are typical LLD values.

(2) At is the time between sample collection and counting time.

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALP 1992 _

GASEOUS EFFLUENTD-SUMMATION OF ALL RELEASES tGROUND LEVEL RELEASES) 1st 2nd Summation of All_ Releases Unit _qte  % Error Otr  % Error A. Hobis Cases

1. Total Released C1 6.93E+01 11.1E+01 3.20E+01 11.1E+01

2. Averago Release Rate of Period UC1/sec 8.84E+00 4.07E+00

3. Porcent et Applicable Limit  % 4.96E-03 2.10E-03 B. Iodines

1. Total Iodine-131 Cl 7.08E-07 11.3E+01 4.63E-06 11.3E+01 Average Release Rate for Period uCi/sec 9.00E-08  !, , 89 E- 0 7

3. Percent of Applicable '

Limit (1.60E-01 pci/sec) % 5.63E-05 3.68E-04 ,,

C.- Particulates

1. Particulates with Ci 1.92E-05 11.eE+01 3.06E-05 11.6E+01 half-lives >8 days

2. AveraSe Release Rate for Period uCi/sec 2.44E-06 3.89E-06

3. Percent of Applicable Limit  % 2.06E-05 1.65E-05

4. Cross Alpha Radio- Ci 0.00E-01 12.1E+01 0.00E-01 12.1E+01 activity D. Ipttium

1. Total Release Cl 8.73E+00 11.5E+01 1.16E+01 11.5E+0i

2. Average Release Rate for Period uCi/see 1.11E-00 1.48E+00 3.- Percent of Applicable Limit (8.47E+04 pCi/sec) 1.31E-03 1.74E-03 4 uryng e'e- g- --y-, y- e- -g nas 4 +-w**---++- +-a--+-- ---*++ewwre-rgr-e w y y g y w we m q y 9%=,-,+y-s--g- - - - ---Ww -m-m4-t v m y w-79g-7y

~. - _ - . - . . .-. . , - . - - . - - . - - - . - - . - - _ . - ~ ~ - - -

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1992 GASEOUS EFFLUENTd-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

Continuous Mode Batch Hode Unit Ouarter Quartog Duarter quarter 1st 2nd let 2nd

, F. Nobin casos Required by ODCM/Others

1. Krypton-87 Ci 4.58E-03 0.00E-01 0.00E-01 0.00E-01 l

2. Krypton-88 Ci 5.43E-03 0.00E-01 7.96E-03 6.39E-02

3. Xenon-133 C1 1.75E+01 0,00E-01 4.52E+01 2.82E+01

4. Xenon-133m Ci 0.00E-01 0.00E-01 1.50E-02 4.48E-01

5. Xenon-133 Ci 4.66E&00 0.00E-01 8,15d-01 1.97E+00

6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

7. Krypton-85 Ci 0.00E-01 0,00E-01 0.00E-01 7.03E-01

8. Argon-41 Ci 0.00E-01 0.00E-01 1.06E440 3.35E-01

9. Krypton-85m Cl 1.69E-03 0.00E-01 1.07E-02 9.42E-02

10. ' Xenon-131m Ci 0.00E-01 0.00E-01 3.97E-02 5.51E-02

11. Xenon-135m C1 1.35E-02 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 2.22E+01 0.00E-01 4 . 7 2 E +01 3.19E+01 G. Iodines

1. Todine-131 Ci 7.08E-07 4.62E-06

2. lodine-133- Ci 0.00E-01 0.00E-01

-3. Toding-135 C1 0.00E-01 0.00E-01 Total for Period Ci 7.08E-07 4.62E-06 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT let HALF 199?

CASE 00S EFFLUENTS-SUKMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

H. Eprt icu l a t_es Required by ODCM/Ot'oers Nuclide Unit Continuous Modo Quarter Quarter let 2nd

1. Strontium-89 Ci 0.00E-01 0200E-01 P

2. Strontium-90 Ci 0.00E-01 0.00E-01

3. Iron-59 Cl 0.00E-01 0.00E-01

4. Cobalt-60 C1 4.96E-06 3.68E-06

5. Zine-65 C1 0.00E-01 0.00E-01 -

6. Mangr. te n o-5 ' Ci 0.00E-01 ,0,00E-0?

7. Cobalt-58 Ci 1.17E-05 1 88E-05_

0. Molybdenum-99 Cl 4.27E-07 0.00E-01

9. Cesium-134 Ci 0.00E-01 0.00E-01

10. Cosium-137 Ci 0.00E 'y 0.00E-01

11. Cerium-141 Ci 0.00E-01 0.00E-01

12. Cerium-144 Cl 0.00E-01 0.00E-01 -

others (Specify)

13. Technetium-99m CL 4.27E-07 0.00E-01

14. Niobium-95 Ci 1.60E-06 0.00E-01

15. Chromium-51 Ci 0.00E-01 8.02E-06 -

Total for Period Cl 1.91F-05 3.05E-05 TOTE: Refer to Table D for ODCM nuclides reported as 0.00E-01.

A. i. .. . .- . . .. . . . . . . . . . _.._. .__w

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT '

Ist HALF 1992 TABLE B '

GASEOUS " TYPICAL" LLD EVALUATION (1)

Noble Gas at(2)

Nuclido ,_ ODCH LLD 1 hr l'.5 hr Krypton-87 1.0E-04 1.19E-06 2.69E-06  !

Krypton-88 1.0E-04 1.22E-06 1.76E-06 $

Xenon-133 1.0E-04 5.51E-07 5. 56 E- 0 7 r

Xenon-133m- 1.0E-04 1.99E-06 2.02E-06

, Xenon-135 1.0E-04 2.59E-07 2.90E 07 Xenon-138 1.0E-04 5.38E-05 8.55E-05 Particulate Samp(e 2.02 da 2.79 da 5.79 da Kansanese-54 129E-10 1.83E-12 7.65E-14 1.10E-14 Cobalt-58 129g 10, 1,60E-12 4.79E-14 9.99E-15 Iron-59 1.0E-10 3.21E-12 1236E-13 2.03E-14 Cobalt-60 1.01:10- 1,74E-12 7.46E-14 1.07E-14 Zine-65 '1203-10 4.08E-12 .1. 71E-13 2.46E-14  !

'Holybdenum-99 1.0E-10 2.08E;11 1.05E-13 3.18E-14 t Cesium-134 1,0E-10 f.03E-12 8.45E-14 1.21E-14 Cealum-13 7 - 1.0E-10 1.85E-12 7.71E-14 1.10E-14

. Cerium-141 J.0E-10 2t3RE-Lg 9.8]E-14 1.50E-14

. Cerium-144 1.0E-10 1.03E-12 4.28E-13 6.16E-14 lodine-131- 1.0E-10 -1.85E-12 8.22E-14 1.52E-14 Charcoal Sample -

2.0 da 2.5 da 5 . 5_d a _

lodine-131 1.0E-11 2.53E-12 1.10E-13 2.00E-14

._.. - . ~ . - . . . _ . - . - .

'. I I

EFFLUENT AND t3ASTE DISPOSAL SEMIANilVAL REPORT let HALL 1992 TABLE B i GASEOUS " TYPICAL" LLD EVALUATION (1)

(continued)

I Nuclldo ODCM LLD Typleal LLD i l

Tritium 1.0E-06 1.0E-11  :

Gross Alpha 1.0E-11 1.5E-14 j~

Strontium-89 1.0E-11 1.0E-14 Strontium-90 1.0E-11 1.0E-15 '

I NOTES (1) LLD values are tr> v(n- . l (2) ~ht for noble gatw (v (N 'W < rom sampling to analysis.

At_for charcoal aus p.f mlate waples is the midpoint of sampling, to analysis.

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l l .

EFFLUENT AND BASTE DISPOSAL SEMIANNUAL REPORT 1st llALF 1992 SOLID WASTE (RADIOACTIVE SilIPMENTO)

A. Solid Waste Shipped Of fsite for Burial or Disposal (not Irradiated Fuel) 6 Month Est. Tot.

1. Type of Wasto Unit period Error %

a. Spent resins, filter sludges, m3 1.86E+1 11.00E-1 evaporator bottoms, etc. Cl 9.33E+2 11.50E+1

b. Dry Active Waste, Comprescible Wasto m3 5.29E+1 11.00E-1 Contamlnated Equipment, etc. Ci 2.12E+1 11.50E+1

c. Irradisted Components, m3 None N/A Control Rods, etc. C1 None N/A

d. Other: Mechanical Filters m3 3.36E+0 11.00E-1 Ci 2.31E+1 11.50E+1

2. Estimate of Major Nuclido Composition (by type of wante)

a. Spent resins, filter sludges, evaporator bottoms, etc. ,

(nuclides detetwined by measurement)

Curies F_ercent

1. Manganese-54 3.03E+1 .

3.25E+0

2. Iron-55 4.76E+1 5.10E+0

3. Cobalt-58 4.04E+2 4.33E+1

4. Cobalt-60 7.96E+1 8.52Et0

5. Nickel-63 1.42E+2 1.52E+1

6. Cesium-134 1.20E+2 1.29E+1

7. Cesium-137 1.00E+2 1.07E+1

b. Dry active waste, congressible waste, contaminated equipment, etc.

(nuclides determined by estimate)

1. Chromium-51 1.45E+00 6.83E+00

2. Manganese-54 3.86E-01 1.82E+00

3. Iron -55 4.38E+00 2.06E+01

4. Cobalt-58 6.62E+00 3.12E+01

5. Cobalt-60 5.00E+00 2.39E+01

6. Nickel-63 8.63E-01 4.06E+00

7. Niobium-95 6.54E-01 3.08E+00

8. Zirconium-95 3.55E-01 1.67E+00

9. Cesium-134 2.12E-01 1.00E+00

10. Cesium-137 3.01E-01 1.41d+00

11. Cerium-144 2.37E-01 1.11E+00

c. Irradiated Components N/A N/A

d. Other: Mechanical Filters (nuclides determined by estimsto)

1. Iron-55 5.71E+0 2.47E+1

2. Cobalt-58 3.12E+0 1.35E+1

3. Cobalt-60 9.11E&O 3.95E+1

4. Nickel-63 4.64E+0 2.01E&1 419/1/1 _1g_ ,

l l

._ __ . _ _ _ _ _ _ . . - _.- . _ ._. .~ _ .__ _ _ _ _ ._ _ _ _ _.__

. I l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT  !

Ist HALF 1992  ;

SOLID WASTE-(RADI0 ACTIVE SHIPMENTS) i

3. Solid Waste Disposition l Number of Shipments Type Ouantity Modo of Transportation Destination a) Spont resins, filter sludges, evaporator bottons, etc.

[

7 A-LSA Motor Freight Barnwell SC l 3 B-LSA Motor Froight Barnwell, SC Number of Shipments Type Ouantity Mode of Transportation Destination e

b) Dry active waste, compressible waste, contaminated equipment, etc.

54 A-LSA Motor Freight Barnwell, SC Number of Shipments Type Ouantity Mode of Transportation pestination  !

c) Irradiated components, control rods, etc.

Nono ..

Number of ,ghipments Type Quantity Mode of Transportatioq Destination d) Other: Mechanical Filters -

i 1 B-LSA Motor Freight Barnwell, SC  !

a. Irradiated Puel Shipments (Disposition)

Number of Shipments _ Type Ouantity Modo of Transportation pestination None N/A N/A N/A t

5. Solidification of Waste Was solidification performed? - No If yes, solidification media: ,N/A

6. Were any changes made to the process control program? , Yes X No; If yes, add as an attachment at the end of report in accordance with Process Control

. Program Section 9.0.  ;

7. Wera any major changes made to the radioactive wasto systems (liquid, gaseous or solid)? Yes X No, If yes; add an attachment at the end of report in

• accordance with Technical Specification Administration Control 6.15.

t 419/1/2 >

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ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL 9

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