ML20114C378

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Semiannual Radioactive Effluent Release Rept 15 for Jan-June 1992
ML20114C378
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/30/1992
From: Henry S, Maynard O, Wideman S
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20114C367 List:
References
NUDOCS 9209020142
Download: ML20114C378 (32)
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Text

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L WOLF CREEK NUCLEAR OPERATING CORPORATION Wolf Creek Generating Station Docket No: 30-482 Facility Operating License No: NPF-42 SIMIANNUAL RADIOACTIVE EFFLUENT RELFASE REPORT Report No: 15 Reporting Period: January 1, 1992 through June 30, 1992 s

Prepated by: Steve A. Henry Steve G. Videman Approved by: . ,

  1. 1&J4//Ap "6tto L. Nay'na/d ~

Director Plant Operations

)

9209020142 920029 PDR ADOCK 05000482 R PDR L- .

l Table of Contents.

Pane Section 1 4 Liquid' Radioactive Effluents 4 Dose Summary 6 I Airborne Radioactive Effluents 8 l

Dose Summary 10

.l Section II 12

~

Offsite Dose Calculation Manual Limits 12 Maximum Permissible Concentrations 13 Measurements and Approximations of Total Radioactivity 14 Batch Releases 16

~ Continuous Releases 16 Solid _ Waste Shipments 17 Irradiated Fuel-Shipments 19 Section III 20 Unplanned or Abnormal Releases 20 ,

Offsite Dose Calculation Manual 21 Major Changes to Liquid, Gaseous or Solid Radwaste Systems 22 Land Use Census- 22 Radioactive Shipments, 22 Inoperability of Aircorne Effluent Monitoring-instrumentation 22 Storage Tanks 23 Full and Low Pressure RCS Gas Samples 23 Attachment 1 Liquid: Effluent Changes to Report 14 and Batch Release Information

= changes to Report 11 Attachment'2 -

Offsite Dose Calculation Manual, Revision 9 l

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Enclosure to NA 92-0035 Page 3 of 23 EXECUTIVE SUM 4ARY The purpose of the Semiannual Radioactive Effluent Release Report is to report on the quantitles of liquid and gaseous effluents and solid waste released from Wolf Creek Generating Station (WCGS). This report covers the period beginning on January 1, 1992, and ending on June 30, 1992.

Section I provides a summary of the quantities of radioactive liquid and gaseous effluents for this reporting period. The format is similar to that recommended in Regulatory Guide 1.21, Revision 1. An elevated release pathway does not exist sc WCGS, therefore, all airborne releases are considered to be ground level releases. The concurrant meteorological conditica gaseous pathway dose determination is met by the WCGS Offsite Dose Calculation Manual methodology of assigning all gaseous pathways to a hypothetical individual residing at the highest ar.nua l X/Q and D/Q location. This results in a conservative estimate of dose to a member of the public rather than determining each pathway dose for each release condition. A conservative error of thirty percent has been estimated in effluent data.

Sections II and III provide additional information required by Regulatory Guide 1.21, Revision 1 and ODCM 7.2.

Attachment 1 provides actual values to replace the estimated values for 11guld effluents provided in Semiannual Radioactive Effluent Release Report No. 14. Analysis results for the Fourth Quarter of Report No. 14 were not completed prior to submission of the report. Actual results of Quarter 4 ~

liquid effluents indicated the presence of Fe-55 in the 11guld batch "

composite. The change decreases the total curies released and decreases the cumulative dose. Because analysis results for the Second Quarter of 1992 have not yet been completed Fe-53, Sr-89 and Sr-90 activities and doses in liquid effluents are presented as an estimate.

Offsite Dose Calculation Manual (ODCM), Revision 9, was approved by the Plant Safety Review Committee during this reporting period. This revision was made to clarify the terms used to calculate the Lower Limit of Detection by defining the decay factors associated with delays from sampling to the start of analysis, during analysis, and during sampling. A complete g copy of the ODCM is included as Attachment 2 of this report.

Enclosure to NA 92-0035  ;

Page 4 of 23 SECTION 1 REPORT OF RADIOACTIVE EFFLUENTS (1992):- 1.IQUID Unit Quarter Quarter-1 2 A. Fission and Activation Products

1. -Total Release (not including tritium, gases, alpha) Ci 1.19E-01 1.82E-02
2. Average Diluted Concentration During Period uCi/ml 1.14E-08 7.79E-09
3. Percent of Applicable Limit (1) I 2.38E+00 3.64E-01
B. Tritium
1. Total Release C1 1.01E+02 3.01E+01
2. Average DJ1uted Cenecntration During Period uCi/ml 9.67E-06 1.29E-05
3. Percent of Applicable Limit (2) 2 3.22E-01 4.30E-01 C. Dissolved and Entrained Gases
1. Total Release ci 8.36E-03 3.21E-04 2 .- Average. Diluted Concentration During Period uCi/mi- 8.00E-10 1.37E-10
3. ' Percent of Applicable Limit (3) t 4.00E-04 6.85E-05 D. Gross Alpha Radioactivity
1. Total Release C1 1.68E-05 9.56E-06 E. Volume of waste released (prior to dilution) liters 1.45E+08 6.03E+07 F. Volume of dilution water used liters 1.03E+10 2.28E+09 L1.jTheapplicable-limitfortheWolfCreekGeneratingStationis5Curiesper-year.

(Reference 10 CFR.50, Appendix 1, ' Guides On Design Objectives For Light-Water-Cooled Nuclear-Power Reactors", paragraph A,2.)- The value. printed here is derived by dividing.

the-total release Curies by 5 Curies and then multiplying the result by 100.

2. .This value is derived by the following formula:

lI of" Applicable Limit = (Averane Diluted Concentration) (100)

(MPC, Appendix B, Table II 10CFR20)

,' 3. .This'value is derived by the following formula:

I of Applicable. Limit = (AveraRe Diluted Concentration) (100)

(2E-4 from ODCM Section 2.1) 4.. Curles in Quarter 2 are based on April composite results for Fe-55 and 1st Quarter composite-results for Sr-89 and Sr-90.

Enclosure to NA- 92-0035 Page,5 of 23 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED- Unit 1 2 1 2 H-3 Ci 3.61E-02 2.30E-01 1.01E+02 2.99E+01 Be-7 C1 0.00E+00 0.00E+00 0.00E+00 3.98E-05 Cr-51 Ci 0.00E+00 0.00E+00 3.21E-03 5.86E-05 Mn *. 4 Ci <7.18E-02 <2.99E-01 2.13E-03 5.12E-04 Fe-d5 Ci <1.44E-01 <5.98E-02 4.45E-02 <5.05E-04 Fe-59 Ci <7.18E-02 <2.99E-02 2.14E-04 <2.53E-04

-Co-57 Ci 'O.00E+00 0.00E+00 2.39E-04 8.65E-05 Co-58 Ci <7.18E-02 <2.90E-02 1.49E 4.54E-03 Co-60 Ci <7.18E-02 <2.99E-02 2.85E-02 5.53E-03 ~

Zn-65 Ci <7.18E-02 <2.99E-02 <7.29E-04 <2.53E-04 Sr-89 Ci <7.18E-03 <2.99E-03 <7.29E-05 <2.53E-05 .

Sr-90 Ci <7,18E-03 <2.99E-03 7.59E-06 2.63E-06 Sr-92 Ci 0.00E+00 0.00E+00 5.35E-05 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 1.65E-03 8.11E-05 Zr-95 Ci 0.00E+00 0.00E+00 7.39E-04 4 29E-05 Mo-99 Ci <7.18E-02 <2.99E-02 <7.29E-04 <2.53E-04 Tc-99m Ci 0.00E+00 0.00E+00 0.00E+00 9.80E-06 Ru-103 Ci 0.00E+00 0.00EiOO 1.38E-04 0.00E+00 Ag-110M Ci 0.00E+00 0.00E+00 3.20E-04 1.50E-04 Sn-113. Ci 0.00E+00 0.00E+00 9.85E-05 0.00E+00 r Sb-124 Ci. 0.00E+00 0.00E+00 9.25E-04 9.02E-05 Sb-125 C1 0.00E+00 0.00E+00 1.18E-02 5.50E-03 I-131 Ci <1.44E-01 <5.98E-02 <1.46E-03 2.08E-06 Cs-134 Ci 6.89E-05 <2.99E-02 3.94E-03 6.39E-04 Cs-137 Ci 8.10E-05 <2.99E-02 3.97E-03 6.80E-04 Ce-141 Ci <7.18E-02 <2.99E-02 <7.29E-04 <2.53E-04 Ce-144 Ci <7.18E-02 <2.99E-02 1.11E-03 2.41E-04 Gross Alpha Ci <1.44E-02 <5.98E-03 1.68E-05 9.56E-06

=Ar-41 C1 - <1. 4 4E+00 <3.98E-01 <1.46E-02 <5.05E-03 Kr-85 Ci <1.44E+00- <5.98E-01 <1.46E-02 <5.05E-03 Kr-85m Ci <1.44Et00 <5.98E-01 <1.46E-02 <5.05E-03 Kr-87 Ci <1.44Et00 <5.98E-01 <1.46E-02 <5.05E-03 Kr-88 Ci <1.44E+00 <5.98E-01 <1.46E-02 <5.05E-03 Xe-131m Ci <1.44E+00 <5.98E-01 <1.46E-02 <5.05E-03 Xe-133 C. <1.44E+00 <5.98E-01 7.82E-03 3.18E-04 Xe-133m. Ci~ <1.44E+00 <5.98E-01 <1.46E-02 <5.05E-03 Xe-135 Ci <1.44E+00 <5.98E-01 5.37E-04 3.08E-06 Xe-135m Ci <1.44E+00 <5.98E-01 <1.46E-02 <5.05E-03 NOTE: Less than values are calculated using the lower limit of detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not 1

included in the summation for the total release values.

The Fe-55 value for the 2nd Quarter is based on the April monthly composite value.

The Sr-89 and Sr-90 values for Quarter 2 are based on the Quarter 1 composite values.

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- _ _ - _ _ _ _ - _ _ _ _ _ _ - _ = _

_ _ _ - __ _ . _ . ._ _ _ __ l

LEnclosure.to NA 92-0035 ,

Page 6 of 23 '

LIQUID CUMULATIVE DOSE SU M ARY (1992)

TABLE 1 ODCM 1

CALCULATED ODCM Z OF DOSE LIMIT LIMIT QUARTER 1 0F 1992 J TOTAL DOSE (mrem) FOR BONE 3.22E-02 -5.00E+00 6.44E-01

~ TOTAL DOSE (mrem) FOR LIVER

- 7.46E-02 5.00E+00 1.49E+00

-TOTAL DOSE (mrem) FOR TOTAL BODY 6.01E-02 1.50E+00 4.01E+00 ,

TOTAL DOSE (mrem) FOR THYROID 1.68E-02 5.00E+00 3.36E-01

-TOTAL DOSE (mrem) FOR KIDNEY 3.58E-02 5.00E+00 7.16E-01 TOTAL DOSE (mrem)-FOR LUNG 2.33E-02 5.00' ~00 4.66E 01

. TOTAL DOSE (mrem) FOR G1-LLI. 5.03E-02 5.00h+00 1.01E+00 QUARTER 2'0F 1992-TOTAL DOSE (mrem) FOR BONE 3.77E-03 5.00E+0^ 7.54E-02 TOTAL DOSE (mrem)'FOR LIVER 1.83E-02 5. 00Es - ' 3.66E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 1.66E-02 1.50E+L; 1.11E+00

TOTAL DOSE (mrem) FOR THYROID 1.16E-02 5.00E+00 2.32E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.38E-02 5.00E+00 2.76E-01 tTOTAL DOSE (mrem) FOR LUNG ~ 1.24E-02 5.00E+00 2.48E-01
TOTAL DOSE (mrem) .FOR GI-LLI 1.34E-02 5.00E+00 2.68E-01 TOTAL-FOR 1992-

-TOTAL DOSE-(mrem) FOR BONE 3.60E-02 1.00E+01 3.60E-01 TOTAL DOSE (mrem) FOR LIVER 9.29E-02 1.00E+01 9.29E-01 TOTAL-DOSE (mrem) FOR TOTAL BODY 7.67E-02 3.00E+00 2.56E+00 TOTAL DOSE.(mrem) FOR THYROID 2.84E-02 1.00E+01 2.84E-01

~ TOTAL D0'E (mrem) FOR KIDNEY 4.96E-02 1.00E401 4.96E-01 TOTAL ">SE (mrem) FOR LUNG 3.57E-02' 1.00E+01 3.57E-01

TOTAL DOSE (mrem) FOR GI-LLI 6.37E-02 1.00E+01 6.37E-01 Based.on ODCM Section 2.2 which restricts dose to the whole body to less than or equal to 1.5 mrem per quarter and 3.0 mrem per year. Dose restriction to any organ is less than or equal to 5 mrem per-quarter and 10 mrem per year.

l-I

Enclosure to NA 92-0035 Page 7 of 23 LIQUID CUMULATIVE DOSE

SUMMARY

(1992)

TABLE 2 A. Fission and Activation Products Quarter 1 Quarter 2 Total (not includinb H-3 gases, alpha)

1. Total Release -(Ci)- 1.19E-01 1.82E-02 1.37E-01
2. Maximum Organ Dose (mrem) 6.31E-02 6.67E-03 6.98E-02
3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E+01
4. ' Percent of Limit 1.26E+00 1.33E-01 6.98E-01 B. Tritium
1. Total Release (Ci) 1.01E+02 3.01E+01 1.31E+02

'2. Maximum Organ Dose (mrem) 1.16E-02 1.16E-02 2.32E-02

3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E+01
4. Percent of Limit 2.32E-01 2.32E-01 2.32E-01 This table is included to show the correlation between Curies released and the associated esiculated maximum organ dose. Wolf Creek ODCM methodology is used to calculate the maximum organ dose which assumes that an individual drinks the water and eats fish from the discharge point. ODCM Section 2.2 organ dose limits are used.

.WOTE: The 2nd Quarter Category A values were calculated based on the April Fe-55 composite reqults and First Quarter Sr-6 and Sr-90 composite results.

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Enclosure:

to NA. 92 0035

Page 8 of 231

-REPORT OF RADI0 ACTIVE EFFLUENTS (1992): A1RB0kaE quarter Quarter Unit 1 2 A.- Fission _and'_ Activation Gases i l

1.=--Total Release C1 1.77E+02 5.90E+01

12. Average Release Rate for Pe:iod uCi/sec 2.71E+02 5.85E+02
3. Percentoof ODCM Limit (1) 2 2.41E-01 7.00E-02 B. Iodines
1. Total Iodine-131 Ci 0.00E+00 0.00E+00 2.- Average Release Rate for Period uCi/sec 0.00E+00 0.00E+00 )

3; Percent of Applicable Limit 0.00E+00

_ (2) Z 0.00E+00 l

-C.- Part'iculates 1

1.- Particulates with Half-lives > 8 days Ci 0.00E+00 4.52E-07 2.__ _

Average Release' Rate 'or Period uC1/sec 0.00E+00 5.75E-08

'3.;" Percent of-0DCM Limlt (3)  % 0.00E+00 5.572-04 4.- Gross Alpha Radio'.ctivity Ci 0.00E+00 0.00E+00 D. Tritium-

1. Total' Release Ci 3.74E+00 4.13E+00

'2.:-Average Release Rate for Period uCi/sec 5.09E 1.01E+00

3. Percent.of ODCM Limit' (4)  ! 3.55E-02 3.93E-02 1 .- The percent of ODCM limit for fission and activation gases is calculated using the following methodology:
I of ODCM Limit = (Otrly Total Beta Airdose)(100) cr (Otrly Total Gamma Airdose)(100) 10 mrad 5 mrad LT he largest value calculated between Gamma and Beta airdose is listed as the I of ODCM Limit.

- 2. --The ~ percentL of ODCM limit for iodine is calculated using the following methodology:

I of ODCM Limit = (Total Curies of Iodine-131)(100) 1 Curie

3. The percent of sCM-limit for particulates_is calculated using the following methodology 2.of ODCM Limit = (Hinhest Organ Dose Due to Particulates)(100) 7.5 mrem 4R The percentfof 0DCM' limit for_ tritium is calculated using the following methodology:

2 of'0DCM L'imit = (Hinhest Ornan Dose Due to'H-3)(100) 7.5 mrem NOTE: This; type of methodology is used since the Wolf Creek ODCH ties release limits to doses rather than Curie release rates.

l Enclosure to NA 92-0035

-Page 9 of 23 CAhEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1 2 1 2

1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 5.E3E-07 1.22E-01 Kr-85 Ci 1.29E+02 0.00Et00 4.55E491 3.74E+01 Kr-85M C1 0.00E+00 7.63E-02 0.00E+00 ..OUE+00 Kr-87 Ci <4.42E+01 <4.47E+01 <8.28E-01 <1.99E-02 Kr-88 Ci 4.27E-02 <3.36E+01 <6.22E-01 <1.50E-02 Xe-131M Ci 0.00E+00 0.00E+00 3.55E-03 0.00E+00 r Xe-133 Ci 1.99E-01 1.82E+01 2.28E-01 1.77E-02 Xe-133M Ci <4.96E+01 <5.02E+01 <9.28E-01 <2.24E-02 Xe-135 C1 1.72E+00 3.13E+00 <7.66E-02 3.98E-04 Xe-138 Ci <9.27E+01 <9.39E+ 1 <1.74E+00 <4.18E-02 Total C1 1.31E+02 2.14E+01 4.58E+01 3.75E+01
2. Halogens (Gaseous) -

1-131 Ci <2.55E-04 <2.59E-04 <4.78E-06 <1.15E ,7 I-133 Ci <2.55E-02 <2.59E-02 <4.78E-04 <1.15E-05 Total Ci <2.58E-02 <2.62E 02 c4.83E-04 <1.16E-05

3. Particulates and Tritium H-3 Ci 3.53E+00 4.07E+00 2.07E-01 5.37E-02 Mn-54 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06

~

Fe-39 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 Co-58 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 Co-60 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 2n-65 Ci <2.55S-03 <2.59E-03 <4.78E-05 <1.15E-06 Mo-99 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 Cs-134 C1 <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 Cs-137 C1 <2.55E-03 4.52E-07 <4.78E-05 <1.15E-06 Ce-141 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 Ce-144 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 St-89 Ci <2.55E-03 <2.59E-03 <4.e8E-05 <1.15E-06 Sr-90 Ci <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 Gross Alpha C1 <2.55E-03 <2.59E-03 <4.78E-05 <1.15E-06 Total Ci 3.53E+00 4.07E+00 2.07E-01 5.37E-02 NOTE: Less than values for Noble Gases are calculated using the lower limit of detecticn (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter.

For the Halogens and Particulates the ODCM LLD values are used.

5 Enclosure to NA 92-0035

!Fage 10.of 23- j 4

-1 GASEOUS CUMULATIVE DOSE

SUMMARY

(1992) _l Table 1 ODCM CALCULATED- ODCM Z- 0F QUARTER 1-OF 1992' __p,0S E LIMIT LIM 11 LTOTAL DGSE (mrem) FOR BONE 0.00f+00 7.50E+00 0.00E+00

TOTAL-DOSE (mrem).FOR LIVER _ 2.66E-05 7.50E+00 3.55E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.66E-03 7.50E+00 3.55E-02 TOTAL DOSE _(mrem) FOR THYROID 2.66E-03 7.50E+00 -3.55E-02

-TOTAL DOSE (mrem) FOR KIDNEY 2.66E-03 7.50E+00 3.55E-02

. TOTAL DOSE (mrem) FOR LUNG 2.66E-03 7.50E+00 3.55E-02 ,

TOTAL DOSE-(mrem) FOR GI-LLI 2.66E-03 7.50E+00 3.55E-02

  • QUARTER 2 0F 1992-TOTAL DOSE (mrem) FOR-BONE 4.18E-05 7.50E+00 5.57E-04 TOTAL DOSE (mrem) FOR LIVER 2.99E-03 7.50E+00 3.99E-02

-TOTAL DOSE (mrem) FOR TOTAL BODY 2.96E-03 7.50E+00 3.95E-02 TOTAL DOSE (mrem) FOR THYROID 2.95E-03 7.50E+00 3.93E-02 TOTAL DOSE (mrem) FOR KlDNEY 2.96E-03 7.50E+00 3.95E-02 TOTAL-DOSE'(mrem) FOR LUNG 2.96E-03 7.50E+00 3.95E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.95E-03 7.50E+00 3.93E-02 TOTALSLFOR 1992

~. TOTAL DOSE (mrem) FOR BONE 4.18E-05 1.50E+01 2.79E-04 TOTAL DOSE (mrem) FOR LIVER 5.65E-03 1.50E+01 3.77E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 15.62E-03 1.50Ef01 3.75E-02 TOTAL DOSE-(mrem) FOR THYROID 5.61E-03 1.50E+01 3.74E-02 TOTAL DOSE (mrem) FOR KIDNEY' 5.62E-03 1.50E+01 3.75E-02 TOTAL DOSE (mrem) FOR LUNG 5.62E-03 1.50E+01 3.75E-02

__. TOTAL DOSE (mrem) FOR GI-LLI 5.61E-03 1.50E+01 3.74E-02

.1. Based on Wolf Creek ODCM Section 3.2.2 which restricts dose during any calender quarter to-less-than or equal to 7.5 mrem to any organ and-during any calender year to less than or

= equal to 15 mrem to.any organ.

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Enclosure to NA 92-0035 Pags 11 of 23 GASEOUS CUMULATIVE DOSE

SUMMARY

(1992)

TABLE 2 Nuclides Released Quarter 1 Quarter 2 Total

'A. Fission and Activation Gases

1. Total Release (Ci) 1.77E+02 5.90E+01 2.36E+02
2. Total Gamma Airdose (mrad) 5.29E-04 9.97E-04 1.53E-03
3. Gamms Airdose Limit (mrad) 5.00E+00 5.00E+00 1.00E+01
4. Percent of Gamma Airdose Limit 1.06E-02 1.99E-02 1.53E-02
5. Total Beta Airdose (mrad) 2.41E-02 7.00E-03 3.11E-02
6. Beta Airdose Limit (mrad) 1.00E+01 1.00E+01 2.00E+01
7. Percent of Beta Airdose Limit (mrad) 2.41E-01 7.00E-02 1.56E-01 B. Particulates
1. Total Particulates (C1) 0.00E+00 4.52E-07 4.52E-07
2. Maximum Organ Dose (mrem) 0.00E+00 4.18E-05 4.18E-05
3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 1.50E+01
4. Percent of Limit 0.00E+00 5.57E-04 2.79E-04 C. Tritium
1. Total Release (C1) 3.74E+00 4.13E+00 7.87E+00
2. Maximum Organ Dose (mrem) 2.66E-03 2.95E-03 5.61E-03
3. Organ Dose Limit (mrem) 7.50E400 7.50E+00 1.50E+01
4. Percent of Limit 3.55E-02 3.93E-02 3.74E-02 D. Iodine
1. Total I-131. I-133 (C1) 0.00E+00 0.00E+00 0.00E+00 ~
2. Maximum Organ Dose (mrem) 0.00E+00 0.00E+00 0.00E+00
3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 1.50E+01
4. Percent of Limit 0.00E+00 0.00E+00 0.00E+00 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. The maximum organ dose is calculated using Wolf Creek ODCM methodology which assumes that an individual actually resides at the release point. ODCM Section 3.2.2 organ dose limits are used.

Enclosure to NA 92-0035 Page 12 of 23 SECTION II Supplemental Information Pacility: Wolf Creek Generating station License Number: NPF-42

1. ODCM Limits A. For liquid waste effluents A.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20, Appendix B. Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or engrained noble gases, the concentration shall be limited to 2 x 10- microcurle/ml total activity.

A.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

B. For gaseous waste effluents B.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and
b. For Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

Less than or equal to 1500 arems/yr to any organ.

B.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY shall be

-limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrada for beta radiation, and
b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal tv 20 mrads for beta radiation.

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

Enclosure to NA 92-0035 Page 131of 23 i

-B.3' The dose from Iodine-131,-Iodine-133, tritium, and all radionuclides-in-particulate form with_ half-lives greater-than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY shall-be limited to the followings

a. fDuring any calendar quarter: Less than or equal to 7.5

-mrems to any organ, and b .~ During any calendar years Less than or equal to 15 mrems to any organ.

2. -Maximum Permissible Concentrations Water - covered in Section 1.A.

Air - covered in Sect. ion 1.B.

3. Average energy of fission and activation gaseous effluents is not ,

applicable.

t 6

f-

't -

i d -

< , - * = , w-re- r m y

-Enclosure to NA 92-0035.  :

!Page:14 of 23-

- 41 Measurements and Approximations of Total Radioactivity LA. Liquid Effluents LIQUID RELEANE SAMPLING MET!ioD OF TYPE OF ACTIVITY TYPE FREQUENCY ANALYSIS ANALYSIS'
l. Batch Vaste P.H.A. Principal Gamma Release P Emmiters

' Tanks Each Batch P.H.A. 1-131

a. Waste Monitor P Dissolved and Tank One Batch /M P.H.A. Entrained Gases (Gamma Emitters)
b. Secondary Liquid P L.S. H-3 Vaste Each Batch Monitor S.A.C. Gross Alpha Tank P O.S.L. Sr-89. Sr-90 Each Batch 0.S.L. Fe-55
2. Continous P.H.A. Principal Gamma Releases Daily Emitters Grab Sample P.H.A. I-131
a. Steam: M Dissolved and Generator Grab Sample P.H.A. Entrained Gases Blowdown (Gamma Emitters) b.--Turbine Daily L.S. -H-3 7'

Building Grab-Sample-Sump S.A.C. Gross Alpha c.. Lime Daily 0.S.L. Sr-89, Sr-90 Sludge Grab Sample Pond O.S.L. Fe JP= prior to each batch S.A.C. = scintillation-alpha counter M = monthly .

0.S.L. = performed by an offsite laboratory.

L. S. =. liquid scintillation P.H.A. - gamma spectrum pulse height analysis using a High Purity Germanium detector..

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

Enclosure'to-NA'92-0035

.Page 15 of 23

~

B. Gaseous Waste Effluents SAMPLING METHOD OF TYPF OF GASEOUS, RELEASE TYPE FREQUENCY ANALYSIS ACTIVITY ANALYSIS P

Each' Tank P.H.A. Principal Gamma Waste Gas Decay Tank Grab Sample Emitters P .

Principal Gamma Containment Purge or Each Purge P.H.A. Emitters Vent Grab Sample Gas Bubbler and L.S. H-3 (oxide)

.PrincipallGamma i Unit Vent M P.H.A. _Faitters i Grab Sample Gas. Bubbler and L.S. H-3 (oxide)

~

Radwaste Building H P.H.A. Principal Gamma Vent Grab Sample Emittert For Unit Vent and I-131 )

Radwaste Building Continuous P.H.A. l Vent release types I-133 listed above. P.H.A.

Continuous _ Particulate Principal' Gamma Sample Emitters S.A.C.

Continuous Particulate Gross Alpha Composite Sample 0.S.L.

Composite Sr-89, Sr-90 Continuous Pcrticulate Sample t

.. . . . . . - - - .- _ - .. - _. _ . _ . . . _ . . . - _ . _ - . _. _ _ . - . . _ _ _ - .._ ._m . . . _ - . . _ _

Enclosure to NA 92-0035 Page-16 of 23

5. Batch Releases

~

L There were"36 gaseous batch releases during the reporting period. _ The  !

longest gaseous batch release lasted 9,681-minutes, while the shortest lasted 23-minutes. The average release lasted 1801 minutes with a l- -

teial-. gaseous batch release time of'64,847 minutes.

There were 53 liquid batch releases during the reporting period.

The longest liquid batch release lasted 145 minutes, while the shortest lasted 42 minutes. The average release lasted 85 minutes with a total liquid batch release time of14.512 minutes.

6. Continuous Releases l- There' vere three liquid release pathways designated as continuous releases during this reporting period. They were the Steam Generator Blowdown, Turbine Building Sump, and Lime Sludge Pond. There were two gas release pathways designated as continuous releases. These were the Unit Vent and Radwasts Building Vent.
r

,, , mm., ,..--n--....-,- - , - , . -- -,, - , - - - - _ - - .,4--an - ., . , ' . , ,

! Enclosure t. ..\ 92-0035 l

Page 17 of 23 EFFI,UENT AND WASTE DISPOSAL SEMIANNUA1. REPORT (1992)

SOLID WASTE S!!IPMFNTS A. SOLID WASTE SilIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste Unit 6-Month Est. Total Period Error I
a. Spent resins, filter sludges, m3* 7.10E+00 evaporator bottoms, etc. Ci 9.58E401 2.50E+01
b. Dry compressible vaste, m3* 1.73E+01 contaminated equip. etc. C1 5.17E-01 2.50E+01
c. Irradiated components, m3* 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00
d. Other m3* 0.00E+0 Ci 0.00E400 0.00E400 m3* = cubic meters
2. Estimate of major nuclide composition (by type of wast.)
a. Spent resins, filter sludges, evaporator bottoms, etc.

Nuclide Percent Name Abundance Curiel Cs-134 24.0612 2.30E+01 Cs-137 20.848Z 2.00E+01 Fe-55 20.4202 1.96E+01 Ni-63 14.694I 1.41E+01 Co-60 8.860 8.49E+00 Co-58 4.332% 4.15E+00 Be-7 3.2572 3.12E+00 Mn-54 2.1272 2.04E+00 Eu-155 1.274% 1.22E+00 C-14 .070% 7.28E-02 Sr-90 .0282 2.65E-02 11 - 3 .023% 2.19E-02 Pu-238 .0002 4.01E-05 Pu-239/40 .000% 3.94E-05 Cm-243/44 .000%  ?.10E-05 Am-241 .000% 1.54E-05 Cm-242 .000Z 0.00E+00 Pu-241 .000% 0.00E+00 1-129 .0002 0.00E+00 Tc-99 .000: 0.00E+00 Nb-94 .000Z 0.00E+00 N1-59 .000% 0.00E+00

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

' Enclosure to NA 92-0035 Page 18 of 23

b. Dry ~ compressible waste, contaminated _ equipment, etc.

i Nuclide- Percent-N9me Abundance Curies Fe 45.1122 2.33E-01 Co 60 21.914Z- 1.13E-01

. 00-58 16.1392 8.34E-02 Ni-63 9.973Z- 5.16E-02 Cs-137 1.585Z 8.19E-03 r Nb-95 1.4852 7.68E-03 Cs-134: 1.3102 6.77E-03 .

I-131 1.128Z 5.83E-03 Mn-54 1.0832 5.60E-03 Cr-511 .219Z 1.13E-03

('-- H-3 .048Z 2.47E-04 C .0042 2.79E-05' Cm-242 .0002 0.00E+00 Pu-241 .000% 0.00E+00

' - 129- .000% 0.00E400 0 -99. .000% 0.00E+00 Sr-90 .000% 0.00E+00 Nb-94' .000% 0.00E+00 Ni-59 .000Z 0.00E+00

c. Irradiated components, control rods, etc.

none- 1

d. Other-

.none

3. Solid Waste' Disposition

Number-of Shipments Mode of_ Transportation Destination 5 Truck Barnwell, South Carolina 4 Truck Richland, Washington

-4. Class of Solid Waste a.--Class A. Class B g b. Class A.

cz 'Not applicable

-1 d . Not applicable

~

5. Type of' Container la . LSA (Strong, tight)-

- b. LSA (Strong,itight)

- c. .Not appl.icable-

d. Not applicable

~

.,2., ,_ , , ,, y ~ mm,. _ _ ,,..,,........a -

- . . , . ,C.. .

Enclosure to NA 92-0035

-Page+19 of:03-

6. - Solidificulon Agent a.--Not applicable b.: Not' applicable
c. Not applicable
d. Not appli' cable

)

B. _ IRRADIATED _ FUEL SHIPMENTS (Disposition)

Der" were no irradiated fuel shipments during this reporting period.

i l

l 3

S h

5 W

I ~

s p a..4 e.,,,,- 7g .ny y .p- . . - - - , -

_.~ .

f-Enclosure to NA f2 0035 Page 20 of 23 SECTION III Additlunal Information

1. Unplanned or Abnormal Releases On March 3, 1992, in preparation for sampling Waste Gas Decay Tank 12 the Radwaste Operator began switching vaste gas decay tanks in accordance with system procedure SYS HA-200, " Waste Gas System Startup and Shutdown." The gas analyzer rack was subsequently placed in standby which lines the gas analyzer rack vent to the Radwaste Building Heating.

Ventilation and Air Conditioning (HVAC) System. Because of pressure reductions through the hydrogen recombiner, the waste gas compressor s cannot maintain high pressures in the low pressure line-up and therefore f the system must be placed in high pressure line-up. However, when the the system was in 6lL Radwaste Operator the low pressure switched line-up and to theWaste Gasat tank was Decay Tank 12,'k which required a a pressur

! high pressure line-up. WasteGasCompressor"A"wassta3tedandhad

l operated for approximately 30 to 45 seconds before flow gad pressure indications made the Radwaste Operator aware that the sydtem should have been in the high pressure line-up. During compressor operation, system pressure had increased above the 50 pound setpoint of the system relief vatve which caused it to lift and vent the vaste gas to the i,'. waste Building HVAC.

The root cause of this event was determined to be a failure of system procedure SYS HA-200 to state tha' prior to switching waste gas decay ~

tanks, ensure the system is in the proper operational line-up for the pressures contained in the onconing Waste Gas Decay Tank.

Because the waste gas decay tank had not been sampled prior to the event, the Control Room notified Chemistry personnel in accordance with the Offsite Dose Calculation Manual. Chemistry personnel sampled the contents of the tank. The estimated dose rate to the whole body was 0.25 mremlyr with a limit of 500 mremlyr and to the skin was 1.16 mrem /yr with a limit of 3000 mremlyr.

System Procedure SYS HA-200 was revised to include a step to ensure the system is in the proper operational line-up for the pressures contained in the oncoming Waste Gas Decay Tank.

On April 23, 1992, a " Process Radiation High" alarm was received in the Control Room. It was subsequently determined that a one pound per

,quare inch (psi) decrease in Waste Gas Decay Tank (WGDT) 14 had occurred when the Radwaste Operator placed the tank in recirculation mode.

_ . _ . - . _ _ _ ._ __ _ _ . _ .. _ _ _ _ _ _ _ . _ ._ _s. .. . . . _ .

Enclosure to NA- 92-0035-Page 21 of 23 It was determined that all controls and equipment were in the proper configuration as the Radwaste Operator was preparing to start the waste gas compressors however, while reviewing the next few steps of the .

startup procedure,_the high pressure WGDT that was in service began pressurizing the hydrogen reconbiner past the relief setpoints. The sample lines from the recombiner have relief valves that lift at 50 psi

.and discharge to,the room ventilation system when in the standby mode l (the mode the system was in at the time).

-l This event occurred as a result of the inlet pressure control valve being in the manual position as required by system procedure SYS HA-200,

' Waste Gas. System Startup and Shutdown," which allowed immediate pressurization of the-recombiner, It was necessary in the past for.the valve to be in manual because of the poor discharge pressure from the compressors. New compressor internals are now present which can allow operators to start.the system with the valve in the automatic position.

It was-not identified until this event had occurred that the procedure should'be changed because_the procedure was written for operation of the system in the manual position. An additional factor in the system relief valves lifting was that the recombiner sample isolation valves were in an open position, as specified by system procedure SYS HA-205,

" Gaseous Radwaste System Gas Analyzer' Racks (HA-161/HA-152) and Catalytic Hydrogen Recombiners (SHA01A/SHA01B). Operations,' while the-hydrogen-analyzers were in the standby mode.

Effluent radiation levels immediately returned to normal following the

initial spike. -Control Room Operators-cleared the process radiation alarm, reset the radiation monitor and notified Chemistry personnel of a

-possible radioactive. gas release. The dose rates of the release were subsequently-calculated and determined to be significantly below the

-regulatory. limits.

System Procedure'SYS HA-200 has been revised to ensure that Hydrogen

.Recombiner: Inlet Pressure Control _ Valve PCV'1103 is in the automatic position and initially set to-control at 20 isi to prevent rapid pressurization. : Additionally, system procedure.SYS HA-205 has been revised to ensure the analyzer rack instrument sample isolation valves are closed until the system is recirculating and:all1 parameters are stable.

2-. 'Offsite Dose Calculation Manual (ODCM)-

OffsiteLDose Calculation Manual.1 Revision'9, was approved this reporting period by the Plant' Safety Review Committee (PSRC) with subsequent i Director Plant Operations approval on April 17, 1992. The revision was made to clarify the terms'used.to' calculate the lower limit of detection E by defining.the decay factors associated with delays from sampling to l -this start of analysis, during analysis and during sampling. As required by-Technical Specificttion 6.14, a complete legible copy of the entire ODCM is provided as Attachment 2..

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

Enclosure to NA 92-0035 Page 22 of 23

3. Major Changes to Raduaste Treatment Systems The following two changes were identified as being permanent changes which would alter the capacity of handling radioactive vastes or differ in the method of treatment. Therefore, these changes are considered major changes to Radwaste Treatment Systeas. The information following each change description is required by ODCM Section 7.2.c which requires a justification for the change, 10 CFR 50.59 summary, and a comparison ~

of projected effluents and doses prior to and resulting from the change.

Plant Modification Request (PMR) 03406 Removal of Stock Equipment Company and Reverse Osmosis equipment.

This modification removes obsolete equipment which is no longer in use.

Removal of this equipment will free up space in the Raawaste Building to better utilize vendor supplied waste processing equipment.

Because this change only effects equipment that is not in use its removal has no impact on other plant systems, releases or exposures.

This PMR was reviewed and approved by the PSRC on May 13, 1992.

Plant Modification Request (PMR) 03761 Radwaste Storage Modification This modification will add the concrete slab upon which a future '

radwaste storage facility will be constructed. Resulting radwaste processing changes will be included .n future revisions of this PMR.

Steps taken through this revision have no impact on other plant systems, releases or exposures.

This PMR was reviewed and approveu Ly the PSRC on May 13, 1992.

4. Land Use Census There were no new locations for dose calculations identified during this report period.
5. Radioactive Shipments There were nine shipments of radioactive radwaste during this report period. Five shipments were to Barnwell, South Carolina, the remaining four shipments were to Richland, Washington. All nine shipments were by truck.
6. Inoperability of Effluent Monitoring Instrumentation There were no events that involved inoperable liquid or gaseous effluent monitoring instrumentation not being corrected within the time spec!fied in Technical Specifications 3.3.3.10 or 3.3.3.11.

eEnclosure to NA 92-0035 j

Page 23 of-23 j i
7. -Storage Tanks There were no-events leading to liquid holdup tanks or gas storage tanks exceeding the limits of. Technical Specifications 3.11.1.4 or 3.11.2.6.
8. Full and Low Pressure RCS Cas: Samples

--During Cycle-5, RCS Hot Leg sample points were isolated due to excess '

' leakage past VALCOR' containment isolation valves. A decision was mado to use the CVCS demineralizer inlet saapi point (~50 psig; instead of the RCS sample ~(~2235 psig) to periorm s 'ech Spec E-Bar sample. This ,

decision was made with confidence that i gas activity would still remain in solution at 50 psig. This decision was communicated with the

-NRC who-in turn requested that the gas activities of the two samples be

, compared once-they were both available and if necessary correct the E-Bar analysis.

On February 2,:1992,-a= pressurized RCS sample (2235 psig) was pulled and compared to a CVCS demin inlet cample (40 psig). The data can De found on Table 1. . Xe-133M and Xe-135M were not included due to the ingrowth from I-133 and I-135 between sample acquisition and the count time.

The -*erage variation between the nuclide activities was 4.7I with a'

- rang yf -7 2% to +9.9%. The. acceptance criteria used by the NRC when fperforming crosschecks with in house lab counting equipment was used to

-verify these measurements.

The gas activities all were.well within the acceptance criteria allowed.

for counting systems. Also the results did not indicate a bias, that

'is,.all of the lower pressure gases were not_ lower than the high-

. pressure samples. These results indicate that the sample at 40 psig does contain the same gas activity:as the full pressure sample.

Therefore the E-Bar counts performed during Cycle 5 with the lower pressure (~50 psig) samples were valid and no corrections are. required.

-TABLE 1 Activity Activity

'(uCi/ml) (uCi/ml) Acceptable Nuclide t1/2 @2235 psig- @ 40'psig Resolution Ratio Ratio Ar-41 -1,83hr 3.969E-3 -4.057E-3: 7.413E+01 1.022~ .80 -' 1.25 Kr-85M 4.48hr 1.655E-3 1.716E-3 1.075E+02 1.037 .80 - 1.25 Kr-87 76.4m 3.940E-3 3.691E-3 7.461E+01 0.937- .80 - 1.25 Kr-88 2.84hr 4.311E-3 4.738E-3 6.604E+01 1.099 .80 - 1.25 Xe-133 5.29d 8.142E-3 7.868E-3 1.423E+02 0.966 .80 - 1.25 L Xe-135 9.08h~ 1.257E-2 1.262E-2 3.428E-02 1.004 .85 - 1.18 Xe-138- 14.13m- 1.424E-2 1.3212-2 4.221E+01 0.928 .75 - 1.33

r n -- r ,mn nw., -

-w w,,,,e ,

-~m-.- e ,-emx er-. -.,,,.1 , we ~ -- ,

ATTACHMENT 1 i

At t a clunent. 1 provides actual values to replace the estimated values for liquid effluents provided in Semiannual Radioactive Effluent Release Report 14 and a correction to the batch release information submitted by Semiannual Radioactive Effluent Release Report No. 11. New values are denoted by bold face type, 1

.. - - - . . - - . - . . . . - . . . .- - . ~. - - - . . - . . .

.- Enclosure to h0-92-0067

= Page 4 of 68 SECTIOP 1 l

R'IPORT DF RAD 101.f,TIVE EFFLUENTS (1991): LIQUID Unit Quarter Quarter 3 4 A. : Fission and Activation Products j 1.. Total Release (not including triti:2, gaseu, alpha) Ci 7.27E-01 5.89E-01 L 2. Average Diluted Concentratign During Period uC1/mi 1.69E-07 1.07E-07 L 3. Percent of Applicable Limit I 1.45E+01 1.18FJ01 B. Tritium l

l 1. : Total Release Ci 1.84E+02 5.12E+01 l 2. Average Diluted Concentratign During Period uC1/mi 4.28E-05 9.33E-06

'3. Percent of Applicable Limit I 1.43E+00 3.11E C. Dissolved and Entrained Gases

1. Total Release Ci 6.67E+00 5.66E+00
2. Average Diluted Cencentratign During Period uCi/ml 1.60E-06 1.21E-06
3. : Percent of Applicable Limit I 8.00E-01 6.05E-01

~

D. Gross Alpha Radioactivity

1. Total Release Ci 2.74E-05 1.84E-05 E. -Volume of. waste released (prior to dilution) liters 3.70E+06 1.90E+07 Fe LVolume of dilution water used liters 4.30E+09 5.47E+09 1

The applicable: limit for the Wolf Creek' Generating Station is 1 Curies per year.

(ReferenceL10 CFR 50, Appendix I, ' Guides On Design Objectives For Light-Water-Cooled 1 Nuclear Power Reactors", paragraph A.2.) The value printed here is derived by dividing the~ total' release Curies by 5 Curies and-then multiplying the result by 100.

21 This value is derived by_ the following formula:

Z of-Applicable Limit ='(Averane Diluted' Concentration) (100)

(MPC, ppendix B, Table II 10CFR20)

[ This 'value is derived by the foliawing fonnula:  !

(. I of Applicable Limit-= ( Averace Diluted Concentration) (1001 ]

l (2E-4 from ODCM Section 2.1) l 2.74E-01 of the 5.89E-01 Curies in Quarter 4 are due to Fe-55.

l-I r

l l

. _ _ -. _ _ _ __ _ _.._ -._ ._ m _ . _- _ m _ m l

Enclosurei to NO 92-0067 Page 5 of 68 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES' Quarter Quarter Quarter . Quarter

-RELEASED Unit -3 4 3 4  ;

H-3 C1 1.66E-02 7.01E-02 1.84S+02 5.11E+01 Be-7 Ci 0.00E+00 0.00E+00 0.00E+00 2.75E-03 Na-24 Ci 0.00E+00 0.00E+00 0.00E+00 5.50E-04 Cr-51 Ci 0.00E+00 0.00E+00 4.97E-03 3.92E-02 Mn.54 Ci <1.21E-03 <8.71E-03 7.96E-03 2.30E-03 Fe-55 Ci <2.42E-03 <1.74E-02 5.27E-01 2.74E-01  ;

Fe-59 Ci <1.21E <8.71E-03 2.60E-04 3.77E-03 Co-57 Ci 0.00E+00 0.00E+00 9.48E-04 1.16E-03 Co Ci <1.21E-03 <8.71E-03 .3.08E-02 5.45E-02 Co-60 Ci <1.21E-03 <8.71E-03 1.30E-01 6.98E-02 Zn Ci <1.21E-03 <8.71E-03 9.C1E-05 <8.07E-04 1

Sr-89 Ci- <1.21E-04 <8.71E-04 9.12E-05 <8.07E-05 Sr.'O Ci <1.21E-04 <8.71E-04 <6.42E-05 <8.07E-05 Sr Ci 0.00E+00 0.00EF00 1.13E-04 0.00E+00 Nb-95 Ci 0.00E+00. 0.00E+00 7.36E-04 1.54E-03 1

-Nb-97 C1 0.00E+00 0.00E+)G 2.02E-06 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 4.61E-04 6.96E-04 Zr-97. Ci 0.00E+00 0.00Et06 0.00E+00 0.00E+00 Mo-99 Ci <1.21E-03 <8.7]E 03 <6.42E-04 <8.07E-04 Tc-99M Ci 0.00E+00 0.00F+C0 1.53E-04 2.08E-05

'Ru-103 Cif 0.00Et00 0.00E+00 4.13E-04 5.69E-04 Ag-110M Ci 0.00E+00 0.0GEt0D 4.08E-03 1.76E-04 Sn-113 Ci- 0.00E+00 0.00V+00 1.76E-04 8.53E-05 Sn-117M Ci 0.00E+00 0.00Et00 1.70E-04 2.77E-04 Sb-124 Ci 0.00E+00 0.00E+00 1.40E-03 8.65E-03 Sb-125 Ci 0.00E+00 0.00E+00 9.26E-03 2.84E-02

.Sb-126 Ci 0.00E+00 0.00E+00 1.01E-04 1.44E-05 I-131 Ci ~< 2.42E-03 <1.74E-02 9.56E-04 2.06E-03 Cs 134- Ci- <1.21E-03 <8.71E-03 2.31E-03 4.58E-02 i Cs-136~ Ci 0.00E+00 0.00E+00 0.00E+00 1.91E-04 Cs-137 Ci <1.21E-03 <8.'1E-03 3.45E-03 4.96E-02 Ba-139 Ci 0.00E+00 0.00E+00 8.71E-04 2.46E-03 La-140 Ci 0.00E+00 0.00E+00 1.08E-04 3.47E-04

Ce-141: Ci <1.21E-03 <8.71E-03 7.63E-05 2.99E-04

-Ce-144 Ci <1.21E-03 <8.71E-03 3.49E-04 1.62E-04 Hf-181 Ci 0.00E+00 0.00E+00 0.00E+00 1.65E-05 Np-239- Ci 0.00E+00 0.00E+00 2.32E-05 0.00Et00 1 Gross Alpha Ci <2.42E-04 <1.74E-03 2.74E-05 1.84E-05 ,

Ar Ci <2.42E-02 <1.74d-01 <1.28E-02 <1.61E-02 Kr-85M Ci <2.42E-02 <1.74E-01 8.29E-05 <1.61E-02

Enclosure to NO 92-0067 Page 6 of 68 LIQUID EFFLUENTS CONTINUED Continuous Mode Batch Mode UUCL1 DES Quarter Quarter Quarter Quarter

)

RELEASED Unit 3 4 3 4 Kr-85 Ci (2.42E-02 <1.74E-01 7.66E-01 1.89E-01 Kr-87 C1 <2.42E-02 <1.74E-01 <1.28E-02 <1.61E-02 Kr-88 Ci <2.42E-uc (1.74E-01 <1.28E-02 <1.61E-02 Xe-131M Ci <2.42E-02 <1.74E-01 1.21E-01 2.19E-01 Xe-133M Ci <2.42E-02 <1.74E-01 2.74E-02 8.51E-03 Xe-133 Ci <2.42E-02 <1.74E-01 5.94E+00 6.24E+00 Xe-135M Ci <2.42E-02 <1.74E-01 <1.28E-02 <1.61E-02 Xe-135 C1 <2.42E-02 <1.74E-01 6.90E-03 <1.61E-02 NOTE: Less than values are calculated using the lower limit of detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

The Fe-55 and Sr-S9 values for Quarter 4 are based on the Quarter 3 Composite results. Estimated values for Quarter 4 have now been replaced with actual test results.

\

v '

.\

Enclooure to NO 92 0067 Page 7 of 68 LIQUID CUMUI.ATIVE DOSE Sutt'.ARY (1991)

TABLE 1 ODCM CALCULATED ODCM 2 0F DOSE LIMIT LIMIT QUARTER 1 0F '991 TOTAL DOSE s

  • m) FOR SONE 3.33E-03 5.00E+00 6.66E-02 TOTAL DOSE (4.em) FOR L1VER 1.77E-02 5.s0E+00 3.54E-01 TOT /> DOSE (mrem) FOR TOTAL BODY 1.61E-02 1.50E400 1.07E400 TOTAL DOSE (mrem) FOR TilYROID 1.27E-02 5.00E+00 2.54E-01 TOTAL DOSE (prem) FOR KIDNEY 1.42E-02 5.00E+00 2.84E-01 TOTAL DOSE (mrem) FOR LUNG 1.35E-02 5.00E+00 2.70E-01 TOTAL DOSE (mrem) FOR GI-LLI 1.55E-02 5.00E400 3.10E-01 ,

QUARTER 2 0F 1991 ~

TOTAL DOSE (mrem) FOR BONE 7.79E-03 5.00E+00 3.56E-01 TOTAL .10SE (mrem) FOR LIVER 3.78E-02 5.00E+00 7.56E-01 TOTAL DOSE (mrem) FOR TOTAL BODi 3.42E-02 1.50E400 2.28E+00 TOTAL DOSE (mrem) FOR THYROID 2.84E-02 5.00E+00 5.68E-01

?OTAL DOSE (mrem) FOR KIDNEY 3.C4E-02 5.00E+00 6.08E-01 TOTAL DOSE (mrem) FOR LUNG 3.07E-02 5.00E+00 6.14E-01 TOTAL DOSE (mrem) F0" GI-LLI 5.07E-02 5.00E400 1.01E400 QUARTER 3 0F 1991 TOTAL DOSE (mrem) FOR BONE 1.47E-01 5.00E+00 -2.94E400 TOTAL DOSE (mrem) FOR LIVER 3.13E-01 5.00E400 6.26E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 2.46E-01 1.5cE+00 1.64E+01 TOTAL DOSE (mrem) FOR THYRCID 7.75E-02 5.00E+00 1.55E+00 TOTAL DOSE (mrem) FOR KIDNEY 1.45E 01 5.00E400 2.90E400 TOTAL DOSE (mrem) FOR LUNG 9.26E-02 5.00E400 1.85E+00

, TOTAL DOSE (mrem) FOR GI-LLI 1.87E-01 5.00E400 3.74E400 QUARTER 4 0F 1991 TOTAL DOSE (mrem) FOR BONE 5.31E-01 b.00E400 1.06E401 ~

TOTAL DOSE (mrem) F0k LIVER 9.85E-01 5.00E400 1.97El01 TOTAL DOSE (mrem) FOR TOTAL BODY 7.43E-01 1,50E+00 4.95El01 TOTAL DOSE (mrem) FOR TilYROID 4.05E-04 5.00E+00 8.10E-01 TOTAL DOSE (mrem) FOR KIJNEY 3.47E-01 5.00E+00 6.94E+00 TOTAL DOSE (mrem) FOR LUNG $ 19E-01 5.00E400 2.78E100 TOTAL DOSE (mrem) FOR GI-LLI 1.36E-01 5.00E+00 2.72E600 TOTAL FOR 1991 TOTAL DOSE (mrem) FOR BONE 6.89E a'l 1.00E+01 6.89Fl00 TOTAL DOSE (mrem) FOR LIVER 1.35Etwo 1.00E401 1.35RiO1 TOTAL DOSE (mrem) FOR TOTAL B0bY 1.04E4004 3.00E400 3.47E+01*

. TOTAL DOSE (mrem) FOR THYR 0"D 1.59Ec01 1.00E401 1.59E+00 TOTAL DOSE (mrem) FOR KIDN: . 5.37E-01 1.00E+01 5.37E+00 TOTAL DOSE (mrem) FOR LUNC 2.76E-01 1.00E401 2.76EiOO TOTAL' DOSE (mrem) "*7 GI-LL. 3.89E-01 1.00E+01 3.89E400 n . . r . , . - i

Enclosure to NO 92 0067 Page 8 of 68 Based on ODCH Section 2.2 which restricts dose to the whole body to less than or equal to 1.5 mrem-per quarter and 3.0 mrem per year. Dose restriction to any organ is less than or equal to 5 mrem per quarter and 10 mrem per year.

NOTE: The. values for Quarters 1 and 2 of 1991 given above differ from the values reported in Semiannual Radioactive Effluent Release Report No. 13 due to adjustment for Fe-55 and

$r 90 compoalte data. ,

  • There were no significant. changes to these values and at e therefore reported the same as the values in Report. 14.

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Enclosure to NO 92-006V Pege 9 of 68 L1 QUID Ci!HJLATIVE DOSE StJMHARY (1991)

TABLE 2 A. Fission and Activation Products Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (not including H-3 gases, alpha)

1. Total Release - (Ci) 9.03E-02 7.17E-01 7.27E-01 $.89E-01 2.12E100
2. Maximum Organ bose (mrem) 5.00E-03 2.23E-02 2.39E-01 9.45E-01 1.21E600*
3. Organ Dose Limit (mrem) 5.00E490 5.00E+00 5.00E400 5.00E+00 1.00E+01
4. Percent of Limit 1.00E-01 4.46E-01 4.78E+00 1.89E601 1.21E101*

B. Tritium _

1. Total Release (Ci) 1. 25E4 02 3.57E+02 1.84E402 5.12E+01 7.17E+02
2. Maximum Organ Dose (mrem). 1.27E.02 2.84E-02 7.39E-02 4.04E-02 1.55E-01
3. Organ Dose Limit (mrem) 5.00E+00 5.00E400 5.00E+00 5.00E+00 1.00E+01
4. Percent of Limit 2.54E-01 5.68E-01 1.48E+00 8.00E-01 1.55E+00 This table is included to show the correlation between Curles released and the associated calculated maximum organ dose. WCGS ODCM methodology is used to calculate the maximum organ dose which assumes that an individual drinks the water and eats 'ish from the discharge point.

ODCM Section 2.2 organ doce limits are used.

NOTE: The Quarter 4 Category A values were calculated based on the Quarter 3 Fe-55 concentrction. Entimated values for Quarter 4 have now been replaced with actual test results.

  • There were no significant changes to these values and are therefore reported the same as the vsluus in Report 14.

Enclosure to NO 90-0237

? age 17 of 45.

5. Batch Releases l l

There were 34 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 9,931 minutes, while the shortest lasted 104 minutes. The average release lasted 2,787 minutes with a total gaseous batch release time ot' 94,753 minutes.

There were 84 liquid batch releases during the reporting period. The longest liquid batch release lasted 147 minutes, while the shortest release lasted 43 minutes. The average release lasted 103.1 minutes with a total liquid batch release time of 8,664 minutes.

6. Continuous Releases I

There were three liquid release pathways designated as continuous releases during this reporting period. They are the Lime Sludge Pond, Turbine Building Sump and Steam Generator Blowdown. There were two gas release pathways designated as continuous releases, these are the Unit Vent and Radwaste Building Vent.

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