ML20235T737

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Semiannual Radioactive Effluent Release Rept Jul-Dec 1988
ML20235T737
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/31/1988
From: Mike Williams, Withers B
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WM-89-0056, WM-89-56, NUDOCS 8903080449
Download: ML20235T737 (50)
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WOLF CREEK NUCLEAR OPERATING CORPORATION -

Wolf Creek Generating Station Docket No:- '50-482

-Facility Operating License No: ' NPF-42 a

r SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Report No: 8 Reporting Period: July 1, 1988 through Decemb'er 31,.1988

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C Prepared by Merlin G. Williams February 28, 1989 b

8903080449 890225 l- PDR ADOCK 05000482  : [

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'EncicSuro to WM 89-0056 e s

. EXECUTIVE

SUMMARY

The ' purpose of- the . Semiannual Radioactive Effluent Release Report is to report on the quantities of liquid and gaseous effluents and. solid- waste

' released from Wolf Creek Generating Station (WCGS). This report covers the period.beginning on July 1, 1988 and ending on December 31.

A1 summary of the' quantities of radioactive li' quid and gaseous effluents Lfor this reporting period is .provided. The format .is' similar to that recommended in Regulatory Guide.l.21, Revision 1. .An elevated , release pathwsy does not exist at Wolf Creek Generating Station, therefore, all e y airborne releases. are' considered to be ground level releases. The concurrent meteorological condition gaseous pathway dose determination is met by the Wolf Creek Offsite . Dose Calculation Manual methodology of-assigning all gaseous pathways to a hypothetical individual' residing at the highest annual 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 th4.rty percent has been estimated in effluent data.-

The report also includes major changes madei to Liquid , Gaseous, or Solf3' Radwaste Treatment Systems. Included as'an attachment to the report are the changes.'made to the Offsite Dose Calculation Manual (ODCM). This report meets the requirement of Technical Specification 6.9.1.7 for this reporting-period.

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x jc1:stra t5 let 89-00561 ,e f Enclosure to:WM 89-0056f Table of' Contents

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' Section:l' , 1 5 Liquid Radioactive Effluents. _1 1 Dose Summary 5

-Airborne Radioactive Effluents ..

.7 J Dose Summary .L 11

- Section'II- 13-Jl . Regulatory Limits. .

13

- Maximum Permissible Concentrations ,

14

' Measurements and Approximations of Total Radioactivity. 15 '

. Batch. Release s '- '17

' Continuous Releases 17 Abnormal Releases ' 17 -

Solid' Waste Shipments , 18 Irradiated. Fuel Shipments'. 19 :-

E Section III 20

. Meteorological Data 20 1

Section IV 25 i

Unplanned. Releases 25 Process Control Program 25 Offsite Dose Calculation Manual 25 Major Changes to Liquid, Gaseous or Solid Radwaste Systems 26 Land Use Census -26 Radioactive Shipments ' 26

Inoperability of Airborne Effluent Monitoring Instrumentation 26

Storage Tanks ~27 Attachment I Changes to Offsite. Dose Calculation Manual lii j

_ o_ ___=____..._- = - _ _ . _ _ . . - . . _ ___ . ._ _ _ _ _ _ . _ - _ _ _ _ _ _ _ _ _ ___b

4 Encl sura ts WM.89-0056 -SECTION I

<. s

) Year 1988

' REPORT OF RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter Quarter.

3 4 A. Fission and Activation Products i

1. Total' Release (not including tritium, gases, alpha) Ci 3.42E-02 1.60E-01
2. ' Average diluted concentration during period uCi/ml '4.14E-09 4.32E-08
3. Percent of Applicable Limit .% 6.84E-01( 3;20E+00 B. Tritium
1. Total Release- Ci- 1.37E+02 6.47E+01'
2. Average diluted concentration during period uCi/ml 1.66E-05 1.75E-05
3. Percen't of Applicable Limit  % 5.53E-01( ) 5.82E-01 C. - Dissolved and Entrai.'ed Oases
1. Total ~ Release Ci 3.95E+00 3.61E+00 2.. Average diluted concen: ration during period uCi/ml 4.79E-07 9.75E-07
3. Percent of Applicable Limit  % 2.39E-01(3) 4.88E-01

'D. Gross Alpha Radioactivity

1. Total Release Ci 0.00E+00 0.00E+00 E. Volume of waste released liters 1.92E+06 2.52E+06 F. Volume of-dilution water used liters 8.25E+09 3.70E+09- _
l. The applicable limit for the Wolf Creek Generating Station is five (5) curies per year.

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:

% applicable limit = (Average diluted concentration) (100)

(MPC, Appendix B, Table II 10CFR20)

3. This value is derived by the following formula:

% applicable limit = (Average diluted concentration) (100)

(2E-4 from Technical Specification 3.11.1.1) l Page 1 of 27

y.- .

Encicsuro to WM 89-0056- Year' ~1988-g s-LIQUID EFFLUENTSi Continuous Mode- Batch Mode-NUCLIDES Quarter . Quarter Quarter . Quarter RELEASED Unit 3 4 3 4~

H-3 Ci 0.00E+00' 7.16E-04 1.37E+02' 6.47E+01 Na-24 Ci 0.00E+00 0.00E+00 4.19E-06 0.00E+00 l

Cr-51' Ci- 0.00E+00 1.03E-06 1.68E-05 1.10E-02 Mn-54 Ci 0.00E+00 6.26E-07 1.13E-03 1.98E-03 Sr-92 Ci- 0.00E+00 0.00E+00 6.11E-06 1.22E-05 Fe-55 Ci 0.00E+00 <1.20E-03 1.77E-02 4.03E-02 Fe-59 Ci 0.00E+00 <6.00E-04~ 2.97E-05 4.38E-03 Co-58 Ci 0.00E+00 2.51E-05 2.89E-03 8.09E-02

-Co-60 Ci 0.00E+00 l'.55E-05 5.79E 9.38E-03 Ag-110M Ci 0.00E+00 -0.00E+00 1.24E-05 1.87E-04 Rb-88 Ci 0.00E+00 0.00E+00 3.31E-03 0.00E-01 Zr-95 Ci 0.00E+00 0.00E+00 3.70E-05 0.00E-00 Nb-95 Ci 0.00E+00 0.00Et00 1. 92E-04 2.55E-04' Ba-139 Ci' O.00E+00 0.00E+00 J2.93E 0.00E+00 Tc-99M Ci 0.00E+00 0.00E+00 8.5 2E-06 2.63E-05 I-131 Ci- -0.00E+00 3.24E-07 5.70E-04 3.42E-04 I-133 Ci 0.00E+00 0.00E+00 4.43E-06 0.00E-01 Cs-134 Ci 0.00E+00 <6.00E-04 1.90E-04 6.40E-04 Nb-97 Ci 0.00E+00 0.00E+00 4.33E-05 1.14E-04 Page 2 of 27

Encicsura to WM 89-0056 Year 1988 a

  • LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4 Cs-137 Ci 0.00E+00 (6.00E-04 4.23E-04 6.81E-04 Zn-65 Ci 0.00E+00 <6.00E-04 <9.60E-04 (9.18E-04 La-140 Ci 0.00E+00 0.00E+00 4.30E-05 8.73E-06 Ce-141 Ci 0.00E+00 <6.00E-04 <9.60E-04 <9.18E-04 Ce-144 Ci 0.00E+00 <6.00E-04 <9.60E-04 <9.18E-04 Mo-99 Ci 0.00E+00 <6.00E-04 <9.60E-04 <9.18E-04 Kr-85 Ci 0.00E+00 0.00E+00 3.68E-02 1.42E-02 Kr-85M Ci 0.00E+00 0.00E+00 3.42E-04 3.80E-05 Kr-88 Ci 0.00E+00 0.00E+00 2.32E-04 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 8.38E-02 7.39E-02 Xe-133M Ci 0.00E+00 0.00E+00 1.84E-02 1.72E-02 Xe-133 Ci 0.00E+00 1.68E-06 3.81E+00 3.50E+00 Xe-135 Ci 0.00E+00 0.00E+00 3.92E-03 1.83E-03 Ar-41 Ci O.00E+00 0.00E+00 4.02E-05 0.00E+00 Sr-89 Ci 0.00E+00 <6.00E-05 1.95E-04 <9.18E-05 Sr-90 Ci 0.00E+00 <6.00E-05 1.27E-06 <9.18E-05 Sn-117M Ci 0.00E+00 0.00E+00 4.32E-06 2.25E-05 Sn-113 Ci 0.005+00 0.00E+00 2.66E-05 4.10E-05 Co-57 Ci 0.00E+00 0.00E+00 3.07E-05 1.96E-04 I

I Page 3 of 27

Enclosure to WM 89-0056 Year 1988 s

  • Li, D EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4 Sb-124 Ci 0.00E+00 0.00E+00 0.00E+00 1.09E-03 Sb-125 Ci 0.00E+00 1.17E-06 1.52E-03 8.80E-03 Gross Alpha Ci 0.00E+00 <1. 20E-04 <1.92E-04 <1.84E-04 l Note: Less than values are calculated using the lower limit of detection l (LLD) values obtained at the Wolf Creek Generating Station multiplied by the volume of waste discharged during the respective quarter.

Note: There were no radioactive continuous mode releases during the third quarter 1988.

Page 4 of 27

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Encicsura:t3 WM 89-0056 ' Yesr '1988-

LIQUID CUNUIATIVE DOSE SitetARY TABLE 1

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ODCM TECHNICAL I

CALCULATED SPECIFICATION  % OF l DOSE LIMIT LIMIT L fUNIT 1,-QUARTER 1 0F 1988-TOTAL _ DOSE. (MREM) FOR BONE . 1.65E-03' 5.00E+00. 3.30E-02 TOTAL DOSE (MREM) FOR LIVER 6.95E-03 5.00E+00 -1.39E-01

~TOTALJDOSE (MREM) FOR~ TOTAL. BODY 6.31E-03 1.50E+00 4.21E-01 l

TOTAL; DOSE'(MREM) FOR THYROID 4.79E-03 -5.00E+00 9.58E-02 TOTAL DOSE (MREM) FOR KIDNEY' 5.09E-03 5.00E+00 1.02E-01 TOTAL-DOSE'(MREM) FOR LUNG' 4.45E-03 5.00E+00- 8.90E-02, sTOTAL DOSE (MREM) FOR GI-LLI 6.81E-02 5.00E+00 .1.36E+00 UNIT 1, QUARTER 2 0F 1988

' TOTAL DOSE- (MREM) FOR BONE 5.31E-03 5.00E+00 1.06E-011

-TOTAL DOSE-(MREM) FOR LIVER. 2.06E-02 5.00E+00 1 4.12E-01:

TOTAL DOSE (MREM) FOR TOTAL BODY l'.88E-02 1;50E+00 1.25E+00 TOTAL DOSE (MREM) FOR THYROID 1.46E-02 5.00E+00 2.92E-01

. TOTAL DOSE (MREM) FOR-KIDNEY- 1.6]E-02 5.00E+00 3.22E-01 TOTAL DOSE (MREM)-FOR LUNG 1.47E-02 5.00E+00 2.94E-01 TOTAL' DOSE -(MREM) FOR GI-LLI 4.24E-02 5.00E+00 8.48E-01 UNIT 1, QUARTER 3 OF 1988 TOTAL DOSE (MREM) ~ FOR BONE 2.31E-03 5.00E+00- 4.62E-02

' TOTAL DOSE (MREM) FOR LIVER 1.49E-02 5.00E+00 2.98E-01~

TOTAL DOSE (MREM) FOR TOTAL BODY 1.39E-02 '1.50E+00' 9.27E TOTAL" DOSE (MREM) FOR THYROID. 1.28E-02 '5.00E+00 2.56E-01 TOTAL DOSE (MREM) FOR KIDNEY 1.25E 5<.00E+00 2.50E-01

! TOTAL DOSE.(MREM) FOR' LUNG 1.18E-02 5. 00E +00 - 2.36E TOTAL DOSE (MREM) FOR GI-LLI 1.51E-02 5.00E+00 3.02E-01,

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.. UNIT 1, Quarter 4 0F 1988 TOTAL DOSE (MREM) FOR BONE 9.00E-03 5.00E+00 1.80E-01.

TOTAL DOSE (MREM) FOR LIVER 6.31E-02 5.00E+00 1.26E+00'

" TOTAL DOSE (MREM) FOR TOTAL BODY 5.88E-02 1.50E+00 3.92E+00

-TOTAL DOSE (MREM) FOR THYROID 5.80E-02 5.00E+00 1.16E+00

-TOTAL DOSE (MREM) FOR' KIDNEY 5.25E-02 5.00E+00 1.05E+00 TOTAL DOSE =(MREM) FOR LUNG 5.16E-02 5.00E+00 1.03E+00 TOTAL DOSE (MREM) FOR GI-LLI 8.70E-02 5.00E+00 1.74E+00 UNIT 1, TOTALS FOR 1988 TOTAL DOSE (MREM) FOR BONE 1.83E-02 1.00E+01 1.83E-01 TOTAL DOSE (MREM) FOR LIVER 1.06E-01 1.00E+01 1.06E+00

. TOTAL DOSE (MREM) FOR TOTAL BODY 9.77E-02 3.00E+00 3.26E+00

; TOTAL DOSE (MREM) FOR THYROID 9.02E-02 1.00E+01 9.02E-01

. TOTAL DOSE (MREM) FOR KIDNEY 8.62E-02 1.00E+01 8.62E-01 TOTAL DOSE (MREM) FOR LUNG 8.25E-02 1.00E+01 8.25E-01

. TOTAL DOSE (MREM) FOR GI-LLI 2.13E-01 1.00E+01 2.13E+00 Based on Technical Specification 3.11.1.2 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.

Page 5 of 27

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' Encledura toLWM-89-0056 Year 1988

7. . LIQUID CUMULATIVE DOSE

SUMMARY

TABLE 2 I A.- Fission & Activation Products Quarter 1 Quarter 2 Quarter 3 Quarter 4- Total'

.(not-including H-3,

1. Total Release - gases, alpha) C1 1.24E-01 6.04E-02 3.42E-02 1.60E-01 3.79E-01 '

2.- Maximum Organ Dose (arem) 6.38E-02 2.83E-02 4.00E-03 7.70E-02: 1.73E-01'

3. ' Organ Dose Limit'(mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 1
4 '. % of Limit 1.28E+00 5.66E-01 8.00E-02 1.54E+00 1.73E+01 B. Tritium
1. Total Release C1 3.80E+01 1.66E+02 1.37E+02 6.47E+01 '4.06E+02
2. Maximum Organ Dose (mrem) 4.26E-03 1.41E-02 1.11E-02 9.97E-03 3.94E-02
3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00' 5.00E+00 5.00E+00- 1.00E+01
4.  % of Limit 8.52E-02 2. 82E-01 2.22E-01 1.99E-01 3.94E-01

-This table is included to show the correlation between curies released and the associated esiculated maximum organ done. Wolf Creek ODCM methodology is used to calculate the.

mzximum organ dose which assumes that an individual drinks the water and eats fish from the.

discharge point. Technical Specification 3.11.1.2 organ dose limits are used.

Page 6 of 27

Enc 1:surJ t3 WM 89-0056 Yair 1988 REPORT OF RADIOACTIVE EFFLUENTS: AIRBORNE

  • Quarter Quarter Unit 3 4 A. Fission & Activation Gases
1. Total Release Ci 1.24E+02 1.18E+02
2. Average release rate for period uCi/see 1.23E+02 4.31E+01
3. Percent of Technical Specification Limits  % 5.78E-02 5.82E-02 B. Iodines
1. Total Iodine-131 Ci' 6.53E-06 4.60E-05
2. Average release rate for period uCi/sec 8.21E-07 6.14E-06
3. Percent of Technical Specification Limits  % 6.53E-04 4.60E-03 C. Particulate
1. Particulate with half-lives > 8 days Ci 0.00E+00 2.38E-05
2. Average release rate for period uCi/sec 0.00E+00 2.99E-06
3. Percent of Technical Specification Limits  % 0.00E+00 3.03E-03
4. Gross Alpha radioactivity Ci 0.00E+00 0.00E+00 D. Tritium
1. Total Release Ci 3.03E+01 4.34E+00
2. Average release rate for period uCi/sec 4.09E+00 5.66E-01
3. Percent of Technical Specification Limits  % 2.88E-01 4.12E-02 Ths parcent of Technical Specification Limits for fission and activation gases is calculated using the following methodology-l

% of Technical Specification Limit . (Quarterly Total Gamma Airdose)(100) 5 mrad The parcent of Technical Specification Limits for Iodine is calculated using the following j methodology:

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% of Technical Specification Limit . (Total Curies of Iodine-131)(100)

I curie 1

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Page 7 of 27

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Enclosure to WM 89-0056 The percent of Technical Specification Limits for particulate is calculated using the follow'ing methodology:

% of Technical Specification Limit = (Highest Organ Dose due to Particulate)(100) 7.5 mrem The percent of Technical Specification Limits for tritium is calculated using the following methodology:

% of Technical Specification Limit . (Highest Organ Dose due to H-3)(100) 7.5 mrem This type of methodology is used since the Wolf Creek Technical Specifications tie releases to doses rather than Curie release rates.

Page 8 of 27

Enc 1coura toiWM 89-0056 Year 1988

.1 *-

GASEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED ' Unit 3 4 3 4-

1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 1.24E-01 6.17E-03 Kr-85 Ci 0.00E+00 0.00E+00 3.06E-01 -7.11E-01 Kr-85M Ci 0.00E+00 0.00E+00 1.12E 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 2.82E-04 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 8.83E-04 0.00E+00 Xe-l'31M Ci 0.00E+00 0.00E+00 1.12E-01 3.01E-02 Xe-133 Ci 1.15E+02 8.34E+01 2.16E+00 3.35E+01 Xe-133M Ci 0.00E+00 0.00E+00 1.17E-02 0.00E+00 i

Xe-135 Ci 6.38E+00 1.81E-01 1.46E-02 4.16E-02 Xe-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00-Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total -Ci 1.21E+02 8.36E+01 2.73E+00 3.43E+01

2. Halogens (Gaseous) 1-131 Ci 6.53E-06 3.03E-05 <1.00E-07 1.57E-05 I-133 Ci <3.00E-02 <3.00E-02 <1.00E-05 <4.78E-03 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 6.53E-06 3.03E-05 0.0CE+00 1.57E-05 Note: Less than values are calculated using the lower limit of detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter.

l Page 9 of 27

Enclosure to WM 39-0056 Year 1988 GASEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4

3. Particulate Ci 3.02E+01 3.50E+00 2.59E-02 8.43E-01

_ H-3 C0-58 Ci <3.00E-03 7.72E-06 <1.00E-06 <4.78E-04 Co-60 Ci <3.00E-03 1.61E-05 <1.00E-06 <4.78E-04 Mn-54 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04,__

Fe-59 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Zn-65 Ci <3.00E-03 <3.00E-03 <1.00E-06 (4.78E-04 Mo-99 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Cs-134 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Cs-137 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Ce-141 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Ce-144 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Sr-89 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Sr-90 Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Gross Alpha Ci <3.00E-03 <3.00E-03 <1.00E-06 <4.78E-04 Note: Less than values are calculated using the lower limit of detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter.

Page 10 of 27

, , Yasr- 1988 Enc 1: sura tn WM 89-0056 GASEOUS CUMULATIVE DOSE

SUMMARY

F T*? *

. Table 1 TECHNICAL I

SPECIFICATION  % OF

} . QUARTER 110F 1988 LIMIT . LIMIT I : DOSE .FROM RADIO 70 DINES, PARTICULATE, AND TRITIUM AT CONTROLLING LOCATION:

LTOTAL DOSE (MREM):FOR BONE 7.65E 7.50E+00 1.03E-04 TOTAL' DOSE- (MREM) .FOR LIVER 1.08E-02 7.50E+00 1.44E 3 TOTAL DOSE (MREM) FOR TOTAL BODY 1.08E-02 7.50E+00- 1.44E-01

. TOTAL DOSE '(MREM) FOR' THYROID 1.31E-02 7.50E+00 1.75E-01' TOTAL DOSE (MREM) FCR KIDNEY 1.08E-02 7.50E+00 1.44E-01 TOTAL DOSE (MREM) FOR LUNG 1.08E-02 7.50E+00 1.44E-01 TOTAL DOSE'(MREM) FOR GI-LLI 1.08E-02 7.50E+00 1.44E-01.

QUARTER 2 0F 1988

DOSE- FROM RADIOIODINES, PARTICULATE, AND. TRITIUM AT CONTROLLING LOCATION:

TOTAL DOSE-(MRIM) FOR BONE F 0.00E+00 7.50E+00 0.00E+00 TOTAL DOSE (MREM) FOR LIVER 6.86E-02 7.50E+00 :9.15E-01 TOTAL DOSE (MREM) FOR TOTAL BODY 6.86E-02 7.50E+00- 9.15E-01 TOTAL DOSE (MREM) FOR THYROID 6.86E-02 7.50E+00 -9.15E-01 TOTAL DOSE (MREM) FOR KIDNEY 6.86E-02 7.50E+00 9.15E-01 TOTAL DOSE (MREM) .FOR LUNG 6.86E-02 7.50E+00- 9.15E-01

. TOTAL DOSE (MREM) FOR GI-LLI 6.86E-02 7.50E+00 9.15E-01

-QUARTER 3 0F 1988 DOSE FROM RAD 1010 DINES, PARTICULATE, AND TRITIUM AT CONTROLLING LOCATION:

. TOTAL DOSE (MREM) FOR BONE 1.13E-05 7.50E+00' 1.51E-04 TOTAL DOSE (MREM) FOR LIVER 2.16E-02 7.50E+00 2.88E-01 TOTAL DOSE (MREM) FOR TOTAL BODY 2.15E-02 7.50E+00 2.87E-01 TOTAL-DOSE (MREM) FOR THYROID 2.53E-02 7.50E+00 3.37E-01 TOTAL DOSE (MREM) FOR KIDNEY 2.16E-02 7.50E400 2.88E-01 TOTAL' DOSE (MREM) FOR LUNG 2.15E-02 7.50E+00 2.87E '

TOTAL. DOSE (MREM) FOR GI-LLI 2.15E-02 7.50E+00 2.87E-01; QUARTER'4 0F 1988 3 DOSE FROM RADIOIODINES, PARTICULATE, AND TRITIUM AT CONTROLLING LOCATION:

TOTAL DOSE (MREM)'FOR BONE 2.79E-04 7.50E+00 3.72E TOTAL. DOSE (MREM) FOR LIVER 3.38E-03 7.50E+00 4.51E-02 TOTAL DOSE (MREM) FOR TOTAL BODY 3.36E-03 7.50E+00 4.48E-02 TOTAL DOSE (NREM) FOR THYROID 2.96E-02 7.50E+00 3.95E-01

. TOTAL DOSE (MREM) FOR KIDNEY 3.43E-03 7.50E+00 4.57E-02 TOTAL DOSE (MREM) FOR LUNG 3.30E-03 7.50E+00 4.40E-02 TOTAL DOSE (MREM) FOR GI-LLI 3.33E-03 7.50E+00 4.44E-02 TOTALS FOR 1988 DOSE FROM RADIOIODINES, PARTICULATE, AND TRITIUM AT CONTROLLING LOCATION:

TOTAL DOSE (MREM) FOR BONE 2.98E-04 1.50E+01 1.99E-03

TOTAL DOSE (MREM) FOR LIVER 1.04E-01 ~1.50E+01 6.93E-01

' TOTAL DOSE (MREM) FOR TOTAL BODY 1.04E-01 1.50E+01 6.93E-01 TOTAL DOSE (MREM) FOR THYROID 1.37E-01 1.50E+01 9.13E-01 TOTAL' DOSE (MREM) FOR KIDNEY 1.04E-01 1.50E+01 6.93E-01 TOTAL DOSE (MREM) FOR LUNG 1.04E-01 1.50E+01 6.93E-01 TOTAL DOSE (MREM) FOR GI-LLI 1.04E-01 1.50E+01 6.93E-01

1. - Based on Wolf Creek Technical Specification 3.11.2.3 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.

Page 11 of 27

i Enclesuro.to WM 89-0056 Year ~ 1988

.* CASEOUS CUMULATIVE' DOSE

SUMMARY

TABLE 2 l l

A. Fission & Activation Gases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total. I l

1. Total Release (Ci) 4.44E+02 1.06E+02 1.24E+02 1.18E+02 7.92E+02
2. Total Gamma Airdose (mrad)- 1.13E-02-+ - 6.16E 03 2.89E-03 .2.91E-03 2.33E-02l 3.-' Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 1
4.  % of Limit 2.26E-01 1.23E-01 5.78E-02 5.82E-02 2.33E-01 '

F. . Particulate

1. Total Particulate (C1) 3.18E-06 0.00E+00 0.00E+00 2.38E-05 2.70E-05 l
2. Maximum Organ Dose (mrem) 1.68E-06 0.00E-00 0.00E+00 2.27E-04 2.29E-04
3. Organ Dose Limit (arem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E 01 I
4.  % of Limit 2.24E-05 0.00E+00 0.00E+00 3.03E-03 1.52E-03 C. Tritium _ _ _ _

1.. Total Release (Ci) 1.51E+01 9.62E+01 3.03E+01 4.34E+00 1.46E+02 1 1

2. Maximum Organ Dose (mrem) 1.08E-02 6.86E-02 2.16E-02 3.09E-03 1.04E-01 !
3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 e7.50E+00 7.50E+00 1.50E+01 '
4.  % of Limit 1.44E-01 9.15E-01 2.88E-01 4.12E-02 6.94E-01 i I

D. ' Iodine ,

'I

1. Total I-131 (Ci) 4.04E-06 0.00E+00 6.53E-06 4.60E-05 5.66E-05' 1
2. Maximum Organ Dose (mrem) 2.31E-03 0.00E+00 '3.74E-03 2.63E-02 3.24E-02 I
3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 1
4.  % of Limit 3.08E-02 0.00E+00 4.99E-02 3.51E-01 2.16E-01 These values differ from the " Report of Radioactive Effluents: Airborne" table since this value is based on dose and not one (1) curie.

This table is included to show the correlation between curies released and the associated j calculated maximum organ dose. c.e maximum organ dose is calculated using Wolf Creek ODCM methodology which assumes that an individual actually resides at the release point. Technical Specification 3.11.2.3 organ dose limits are used. 1 i

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Page 12 of 27 ,

_ _ _ _ _ ._ ._____-___-_______b

" Enclesura to WM'89-0056 SECTION II Supplemental Information Facility: Wolf Creek Generating ~ Station License Number:- NPF-42

1. Regulatory 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 10lCFR Part 20, Appendix B,. Table II,, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained ngble gases, the concentration shall be limited to 2 x 10 microcurie /m1' 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 and 133, for tritium, and for all radionuclides in particulate form with' half-lives greater than 8 days: Less than or , qual to 1500 mrems/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 mrads for beta radiation, and
b. During any calendar year Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

.. Page 13 of 27 l

c: ,

p

.. . . r :'

.', ' ,e I ...

+

("  ; Elncirura ta WM 89-0056

( y ..

C

~

'B.3 The. dose from Iodine-131 and.133, tritium, and all radionuclides

- in particulate form with half-lives greater than 8 days in,

-> gaseous effluents released,- from.each unit, to areas at and-

.beyond the SITE BOUNDARY shall be limited to the following:

a. During- any calendar quarteie: Less-than or equal'to-

-7.5 mrems to any organ, and'

b. 'During any calendar year: Less than or. equel to 15 mrems'to any organ.

-2. . Maximum Permissible Concentrations Water - covered in section'1.A.

g Air - covered in se; ni m 1.B.

3. Average energy of E sqion and activation gaseous effluents is nott applicable.

O

..f-9 Page 14 of 27

Enc 1 ;ura to WM 89-0056

~

l' 4. Measurements and Approximations of Total Radioactivity l

A. Liquid Effluents LIQUID RELEASE SAMPLING METHOD OF TYPE OF ACTIVITY TYPE FREQUENCY ANALYSIS ANALYSIS l

1. Batch Waste 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 Waste Each Batch Monitor S.A.C. Gross Alpha Tank P 0.S.L. Sr-89, Sr-90 Each Batch 0.S.L. Fe-55
2. Continous P.H.A. Principa Releases Daily Emitters {3 gamma Grab Sample P.H.A. 1-131 Steam M Dissolved and Generator Grab Sample P.H.A. Entrained Gases Blowdown (Gamma Emitters)

Daily L . S ., H-3 Grab Sample S.A.C. Gross Alpha Daily 0.S.L. Sr-89, Sr-90 Grab Sample 0.S.L. Fe-55 P = prior to each batch S.A.C. = Scintillation alpha counter M = monthly 0.S.L. = performed by an Offsite Labratory P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector.

Page 15 of 27

~

Enclosure to WM 89-0056

~

B. Gaseous Waste Effluents SAMPLING METHOD OF TYPE 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)

Principal Gamma Unit Vent M P.H.A. Emitters Grab Sample Gas Bubbler and L.S. H-3 (oxide)

Radwaste Building M _

P.H.A. Principal Gamma Vent Grab Sample Emitters All Release Types I-131 as listed above Continuous P.H.A.

I-133 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 Particulate Sample C. A conservative error of +30% has been estimated. This includes volumetric measurement device, flow measurement device and analytical errors.

Page 16 of 27 i

L. .

, Enclosura to WM'89'-00564 i

~

e 5. Batch Releases There were thirty-five (35)' gaseous batch releases'during the report

. period. The-longest gaseous batch release took 167 hours0.00193 days <br />0.0464 hours <br />2.761243e-4 weeks <br />6.35435e-5 months <br />, the shortest occurred over a forty (40) minute interval. 'The average release took 56.Y"Edu'rs' with a' total gaseous ' batch . release time of.1967 hours0.0228 days <br />0.546 hours <br />0.00325 weeks <br />7.484435e-4 months <br />.

There were 84 liquid batch releases during the report period. The longest liquid batch release 1 cook-185 minutes while the shortest took only 40 minutes. The average release time for the liquid batch releases was 98.7 minutes. Total release time for all.84 liquid batch releases was 138.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

6. Continuous R'e leases There were no radioactive continuous liquid releases during the third quarter of 1988. On October 7, 1988,Jthe plant was.taken off-line as scheduled for a refueling outage. Subsequent _to the reactor shutdown, very low levels of activity were noted in the Steam Generators. During the course of the' outage various portions of the Steam Generator Blowdown System were drained to support maintenance activities. This resulted in.very small quantities-of radioactive material being-discharged to Wolf Creek Cooling Lake (WCCL).

=On November 7, 1988, the Steam Generator Surge Tank was sampled for.

release to WCCL. Tritium was detected in the sample and the_-

distribution of isotopes present' indicated that a radioactive liquid batch release had backed up into the Steam Generator Surge Tank. Both the Steam Generator Blowdown System and the' discharge line for radioactive liquid batch releases drain to a common discharge. Liquid release permit 88193 was issued for the- release of the Steam Generator

-Surge Tank. This release was' documented as a continuous release since it was discharged through the Steam Generator Blowdown pathway.

7. Abnormal Releases There were no abnormal liquid or gaseous releases for this report

-period.

Page 17 of 27

_----_-________-________________-_-_L

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.; Enc 1ssurd ts.Mi 89-0056'

,, . EFFLUENT AND WASTE DISPOSAL' SEMIANNUAL REPORT (1988)

SOLID WASTE SHIPMENTS A. SOLID WASTE SHIPPED ~ 0FFSITE FOR BURIAL. OR DISPOSAL (Not' irradiated fuel) l 1. Type of waste- Unit '6-month Est. Total Period Error %

a. Spent resins, filter sludges, m3* 0.00E+00 evaporator bottoms, etc.- Ci 0.00E+00 0.00E+00
b. Dry compressible waste, m3* 9.84E+01

-contaminated equip. etc. 'Ci 1._4 8E+00 2.50E+01

c. Irradiated components, m3* 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00
d. Other (describe) m3* 0.00E+00 Ci 0.00E+00 0.00E+00 m3* = cubic meters
2. Estimate of major nuclide composition (by type of waste)
a. none
b. Co-58  % 3.88E+01 Fe-55  % 2.59E+01 Co-60  % 1.65E+01 '

Cr-51  % 7.88E+00 Fe-59  % 4.42E+00 Mn-54  % 3.87E+00 Co-57  % 2.58E+00 C-14  % 5.70E-02

c. none
d. none
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Truck Barnwell, South Carolina
4. Class of Solid Waste a._ Not applicable
b. Class A
c. Not applicable
d. Not applicable Page 18 of 27
5. Type of Container
a. Not appliable
b. LSA (Strong, tight)
c. Not applicable
d. Not applicable
6. Solidification Agent
a. Not applicable
b. Not applicable
c. Not applicable
d. Not applicable B. IRIMDIATED FUEL SHIPMENTS (Disposition)

There were no irradiated fuel shipments during this reporting period.

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Page 19 of 27

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

i

,, Enc 1ssura to ifM 89-0056' SECTION III.

HOURS AT EACH WIND SPEED AND DIRECTION All gaseous releases at the Wolf. Creek Generating. Station are ground level releases. The meteorological. data. supplied in these tables cover the period from January 1, 1988, through December 31,.1988, and indicate the number of' hours at each' wind speed and direction for'each stability class.

' STABILITY CLASS: A- ELEVATION: GROUND WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 '19-24 >24 TOTAL-N 7 21 39 51 14 0 132 NNE 4 12- 29 25 10- 5 85 NE O 2' 5 0 0 0 7-ENE O 0 0 0 0 0 0 E O O O 0 0 0 0 ESE 0 0 0 1 0 0 1 SE 0 0 21 2 ~0- 0 23 SSE l' 1 16 2 0 0- 20 S- 0 1 63 66 8 1 139 SSW 0- 1 22 92' 8 0 123 SW. 0 0 1 0 0 0 1 WSW 0 0 0 1 0 0 1

-W 0 1 0 0 0 0 .1 WNW 0 0 0 1 0 0 1 NW 0 1 0 0 0 0 1 NNW 0 5 4 7 2 0 18 TOTAL 12 45 200 248 42' 6 553

' Periods of Calm (Hours): 0 Page 20 of 27 1_ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i

1 Encicsura t3 WM 89-0056 ,

~

w  ;

STABILITY CLASS: B ELEVATION: GROUND WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 5 10 27 6 0 49 NNE 2 9 17 12 3 0 43 NE 0 1 9 1 0 1 12 ENE O O 3 0 0 0 3 E 1 1 0 0 0 0 2 ESE 1 1 3 6 0 0 11 SE 0 4 27 5 0 0 36 SSE 0 3 19 4 0 0 26 S 0 7 46 31 13 1 98

'SSW 0 2 26 31 7 0 66 SW 0 1 2 3 0 0 6 WSW 0 1 0 1 0 0 2 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 .0 NW 1 1 0 1 0 0 3 NNW 1 7 12 10 1 0 31 TOTAL 7 43 174 132 30 2 388 Periods of Calm (Hours): 0 STABILITY CLASS: C ELEVATION: GROUND WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 11 11 30 7 0 60 NNE 3 14 14 9 8 0 48 NE O 11 8 1 0 0 20 ENE 1 0 4 0 0 0 5 E O 0 0 0 0 0 0 ESE O 3 3 5 0 0 11 SE O 7 18 3 0 0 28 SSE 1 7 21 16 2 1 48 S 3 13 48 28 6 2 100 SSW 1 2 27 41 7 0 78 SW 1 2 11 3 0 0 17 WSW 0 1 4 0 0 0 5 W 0 1 0 0 0 0 1 WNW 0 0 0 0 3 3 6 NW 0 1 0 0 0 0 1 NNW 1 6 10 16 2 1 36 TOTAL 12 79 179 152 35 7 464 Periods of Calm (Hours): O p

l

b- Enc 10 sura tb WM 89-0056

., STABILITY CLASS: D ELEVATION: GROUND WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 11 38 67 65 19 2 202 NNE 9 50 70 66 25 3 223 NE 33 91 53 17 10 0 204 ENE 34 61 48 5 0 0 148 E 11 21 38 8 3 0 81' ESE 6 36 40 10 1 0 93 SE 3 23 52 22 6 1 107 SSE 3 71 146 75 17 4 316 S 15 84 248 208 94 7 656 SSW 21 59 132 104 36 6 358 SW 3 44 46 12 1 1 107 WSW 4 32 50 28 15 3 132 W 2 25 33 18 12 8 98 WNW 0 16 45 51 28 13 153 NW 9 17 42 94 44 23 229 NNW 11 29 56 100 36 13 245 TOTAL 175 697 1166 883 347 84 3352 Periods of Calm (Honrs): 4 STABILITY CLASS: E ELEVATION: GROUND WIND SPEED (MPP)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 11 54 39 4 0 0 108 NNE 7 54 24 7 2 0 94 NE 21 35 14 5 0 0 75 ENE 23 82 19 2 0 0 126

- - - _ - - - - - - - - ---==__ =_-----

E 13 54 43 5 1 0 116 ESE 7 63 37 3 0 0 110 SE 3 104 89 17 1 0 214 SSE 5 108 171 73 7 0 364 S 11 48 167 114 76 24 440 SSW 14 49 72 31 22 13 201 SW 7 63 30 8 3 0 111 WSW 12 52 34 4 6 2 110 W 4 53 28 6 6 0 97 WNW 5 35 59 11 2 0 112 NW 8 26 84 48 9 1 176 NNW 7 29 45 10 1 0 92 TOTAL 158 909 955 348 136 40 2546 1

Periods of Calm (Hours): 2 L Page 22 of 27

, Enc 1 sura t:) WM 89-0056

.. STABILITY CLASS: F ELEVATION: GROUND WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 21 23 3 0 0 51 NNE 9 35 24 1 0 0 69 NE 7 47 7 0 0 0 61 ENE 17 57 5 0 0 0 79 E 8 45 13 0 0 0 66 ESE 8 60 14 0 0 0 82 SE 12 97 21 1 0 0 131 SSE 9 76 36 4 0 0 125

-- -_ - - - - - _ _ =- .

SSW 4 30 42 9 1 0 86 SW 6 26 7 0 0 0 39 WSW 5 25 7 1 0 0 38 W 2 15 3 0 0 0 20 WNW 5 15 15 0 0 0 35 NW 16 22 17 0 0 0 55 NNW 9 27 13 0 0 0 49 TOTAL 130 637 279 35 2 0 1083 Periods of Calm (Hours): 5 STABILITY CLASS: G ELEVATION: GROUND WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 10 3 0 0 0 14 NNE 1 16 5 0 0 0 22 NE 4 20 3 0 0 0 27 ENE 5 15 2 0 0 0 22 E 4 13 8 0 0 0 25 ESE O 21 2 0 0 0 23 SE 2 33 0 0 0 0 35 SSE 7 24 9 0 0 0 40

=.

S 1 7 13 0 0 0 21 SSW 2 14 3 1 0 0 20 SW 3 4 0 0 0 0 7 WSW 0 4 0 1 0 0 5 W 4 9 1 0 0 0 14 WNW 4 5 0 0 0 0 9 NW 6 8 1 0 0 0 15 NNW 4 10 2 0 0 0 16 TOTAL 48 213 52 2 0 0 315  ;

Periods of Calm (Hours): 0 i Page 23 of 27

. _ _ . ___-_-__________-_A

Encl: sura t3 WM 89-0056

,, STABILITY CLASS: All ELEVATION: GROUND WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N .36 160 192 180 46 2 616 NNE 35 190 183 120 48 8 584 NE 65 207 99 24 10- 1 406 ENE 80 215 81 7 0 0 383 E 37 134 102 13 4 0 290 ESE 22 184 99 25 1 0 331 SE 20 268 228 50 7 1 574 SSE 26 290 418 174 -26 5 939 S 39 199 617 463 198 35 1551 SSW 42 157 324 309 81 19 932 SW 20 140 97 26 4 1 288 WSW 21 115 95 36 21 5 293 W 12 104 65 24 18 8 231 WNW 14 71 119 63 33 16 316 NW 40 76 144 143 53 24 480 NNW 33 113 142 143 42 14 487 TOTAL 542 2623 3005 1800 592 139 8701 Periods of Calm (Hours): 11 Hours of Missing Data: 72 Ihe computer that supplies the wind speed and direction data for Wolf Creek Generating Station does not report hours unless there are three 15 minute intervals of good data per hour. The 72 missing hours of data are due to this criteria. In most cases there is at least one good fifteen minute interval for each hour. This data is available for review at the Wolf Creek site.

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Page 24 of 27 l

.., SECTION IV ,

'l Additional Information.

1. Unplanned. Releases L

There were no unplanned' releases'during.this report; period.

L 2. Process' Control Program '(PCP)

E There were no' changes to the PCP during this report period.

I:

1-

3. Offsit'e Dose: Calculation Manual (ODCM)

The ODCM was revised with' Plant Safety ' Review Committee approval' on .

November 3,l1988.L This was Revision 4 to the ODCM. The changes'to the-

j. ODCM involve three major areas:

A. The deletion of Radiation Monitors GL-RE-60 (Auxiliary Ventilation Exhaust) and GK-RE-41 (Access Control Ventilation). A copy of the

~

justification for this change is included in Attachment 7.

  • B. The1 addition of Radiation Monitor HF-RE-95 (Waste Water Treatment) '

to monitor the discharge of Condensate Polisher Regeneration Wastes

.to the'new Waste Water Treatment < Facility.. Its setpoint description is identical to that'of the Turbine Building Sump Monitor, LE-RE-

'59. This radiation monitor was added to prevent accidental i

4 contamination of the Waste Water Treatment System.

C. Changes to Section 4, " RADIOLOGICAL ENVIRONMENTAL MONITORING - 'i PROGRAM". These changes involve descriptions of sampling locations and improvements to the maps. . Justification for changes-to section I 4 are:

Fage 33: Changes "KG&E" to "WCNOC"; correct Figure references.

Page 34: Clarify location descriptions and correct Figure references.

, Page 35: Clarify location descriptions and correct Figure references.

Page 36: (a. milk) - revised to list the only identified milk sampling locations within five miles of WCGS.

(c. Food Products) - revised to conform with Technical Specification Table 3.12-1 which requires only one downstream sampling of irrigated crops.

Other changes to clarify location descriptions and correct Figure references.

Page 25 of 27

________________________o

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EncicsursitsWM-89-0056.

+

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-Page 37:- Revised to incorporate _ sampling locations'for additional pathways.'

l- g

-Page 38 ' All maps were revised :to improve legibility incorporate

4_1,: location modifications, and correspond. to: Table 4.1 format. (These changes! increase the total number of maps from four (4)'to five (5).-

1.

A, copy of the pages from the-0DCM that have'been revised are included -

with this; report as Attachment I. Revisions are denoted 'by a l revision bar in the right-hand margin of each page. l 1

I 4.- Major' Changes to Liquid, Gaseous or Solid Radwaste' Systems There were no major changes to radwaste systems during this report period.

5. = Land Use Census There were no new locations for dose calculations identified during this report period.
6. Radioactive Shipments Ttiere were five shipments of Radioactive radwaste during this report period. All five shipments were to:Barnwell, South Carolina.
7. Inoperability of Airborne Effluent Monitoring Instrumentation - ll As-reported ~previously in Semiannual Radioactive Effluent Release ~

Report Number 7, on. July'1, 1988, the Unit Vent System Noble Gas Radiation Monitor, GT-RE-21B, had been out of service for thirty-days. Therefore, the following information is included in accordance j with Technical Specification (T/S) 3.3.3.11.

On June 1, 1988, at approximately 0840 CDT, GT-RE-21B was removed f rom service for scheduled maintenance activities. The licensed operations personnel entered T/S 3.3.3.11, Action Statement b, and ,

inititiated 12-hour grab samples as required for.GT-RE-21B. On June i' 2, 1988, the scheduled maintenance activities were completed, but because GT-R21B failed its retest, the monitor was not returned to service.

'1 l

l Page 26 of 27

_ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ __ _ _ __ ________ _ _ _ _ _ _ _ _ _ o

Encicsura t0 %Di 89-0056 As a result of the retest failure, troubleshooting activities were conducted on June 3, 1988. Diagnostics on GT-RE-21B indicated a programmable read-only memory (PROM) chip failore. A spare set of PROM chips were installed but indicated a different PROM chip failure. Additional troubleshooting was then conducted to verify that the failure was in the PROM chips. Because additional spare sets of PROM chips were not available on site, a purchase order was initiated on June 9, 1988, to obtain the PROM chips from the vendor.

The vendor was contacted to expedite the shipment of the replacement chips needed to restore GT-RE-21B to operable status. Following receipt of the PROM chips, maintenance and testing were completed and GT-RE-21B was returned to service on July 8, 1988.

8. 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, respectively.

Page 27 of 27

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ATTACHMENT I l

~l 0FFSITE DOSE CALCULATION MANUAL J

1 1

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OFFSITE DOSE CALCULATION MANUAL.

for-Wolf' Creek Nuclear Operating Corporation Wolf Creek Generating Station l

Revision.4 i

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APPROVEDBh. '

4 .t Y DATE: Ph SITE CMEMIST V. j APPROVED BY MMMM PSRC' DATE: //- J".I [-

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l L. ____ ___ _______ _ _-- ___ _ _ --

4 NG7 CREEK NUCIEAR SAFEPY EVAURTIN CHBCELIST

., S.E. No.88-SE-053 (1) DOCUMENP APPLICAB2 'IO: ODCM Rev. 3 (2) ***** *****

PART A 10 CER 50.59/DNIRO#IENmL APPLICABILITY REVIN The procedure, procedure revision or change, or modification to which this evaluation is applicables (2.1) Yes No Does this change the facility or procedures fr m their description in the USAR? _. _ ; _.

(2.2) Yes No Does this change involve a test or experinent not described in

-the USAR?----- - ~ ~ ~ ~ ~ ~ ~'

(2.3) Yes No Could this change affect nuclear safety in a way not previously evaluated in the USAR?

Yes

~

(2.4) No Does-this change-reduce-the nargin of safety ~as ' defined in the Technical Specifications?

(2.5) Yes No Ebes an Environmental Question exist (per Step 4.6 of procedure)?

If the answer h any of the above questions (2.1) through (2.4) is "Yes", this Checklist shall be forwardai to the Results Engineering Supervisor for empletion of Section (3). If anly the answer to (2.5) is "Yes", refer to Step 4.2.4. If the answers to all of the above are "No", no Unreviewed Safety or Environmental Question exists.

Prepared By (Originator) Date Reviewed By (Supervisor) Date (3) ***** _ PART_B 10 CER 50.59 MX1 EAR SAFEPY EVAURTIW *****

Results Engineering to ccinplete the Safety Evaluation (Attachment 022-4) Questicns 3.1 through 3.4 and log a- Safety-Evaluation-Numberr ~-

Yes No X Does an Unreviewed Safety Question exist?

Yes No X Does this change irstIve a change to the Technical Specification?

Yes No X Does this change require NRC approval?

Yes No N/A X Does the Environmental Evaluation if applicable, i an Unreviewed Environmental Questicn exits?

Braluating Results Engineer _ ,f _ m - Date F/3f N Results Engineerlag Superv Date 8- 5%'8 7 v <

tr

/

14) ***** FDaL PSRC DETERMINATION *****

Yes No d Unreviemxi Safety and/cr Unreviewed Environmental Question MRC Chairnun, -J ff '

Date // W Attachment 022-1 ADH 01-022 Page 1 of 1 Rev. 15 Page 10 of 19 Page 1 of 5

9 S.E. No. 88-SE-053 RESUllIS PJGINEERDG L ***** PARP B 10 CFR 50.59 NUCLEAR SAFETY EVAURTIN *****

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DOCUMEMP APPLICABLE '10: ODCM Rev. 3 3.0 %e followiry pmeiam the jusHfimtion for the answers given to Questims 3.1 thru 3.4. Use more than ene page if required.

The Offsite Dose Calculation Manual (ODCM) is a part of the USAR and it was included with the subnitted th-witation to the NRC for supporting issuance of our license. Changes to this document fall under the 50.59 rule and require PSRC approval per Technical Specification 6.5.1.6. The changes nede to the ODCM by this revision were subnitted on behalf of the Site Chenist and are corrections to paragraph 3.1.4 to reflect actual plant design and systen features. Paragraph 3.1.4 of the ODCM is descriptively titled " Alert Alann Setpoint Calculations." The first sentence in this paragraph of the ODCM states:

FSAR Table 11.5-4 states that the alert alann for the Plant Unit Vent (O-GT-RE-21), Radwaste Building Exhaust Monitor (0-GI-RE-10),

Auxiliary Ventilation Exhaust Monitor (0-GL-RE-60), and Access Control Area Ventilation Monitor (0-GK-RE-41) is set to alert operators to that average concentration which if naintained for a full year would result in the 10 CFR 50 Appendix I annual dose guidelines being reached.

This statanent is only pardally correct since the Auriliary Ventilation Exhaust, GL-RE-60, and the Access Control Area Ventilation Exhaust, GK-RE-41, Monitors are not Airborne Effluent Radioactivity Monitors (AERM's) nor have they been or currently set as described by this paragraph. %ey have been set in armrdance with the methodology described in ODCM mranraph 3.1.4.2. W ese monitors are Airborne Radioactivity Monitors (AiRM's) and their design and setpoint values are described in USAR Section 12.3.4. %e hi and hi-hi alann setpoints of the AiRM nonitors are listed in USAR 'Inble 12.3-3. The setpoint function of these AiRM nonitors is to nanitor and alann for airborne radioactivity inside the plant for the protection of plant pu.wnuiel in mm1innoe with Regulatory Guide 8.2 and ,

within the limits established by 10 CFR 20, Table I, Column I. AiRM nonitors, GK-RE-41 and GL-RE-60, provide infonnation necessary to ensure that particulate radioactivity dces not exceed 10 FPC hourt in areas occupied by the station personnel. Monitors GK-RE-41 and GL-RE-60 are non IE powered, have an alann function only and are inplant mnitors, located upstream of systen filters. USAR Secticn 12.3.4 teflects this.

The AERM nonitors, however,, (GT-RE-21 and GI-RE-10) per USAR See: tion 11.5 are designed to provide for unrestricted arm protection in accordanco with 10 CER SO Table II, Column 1, and site boundary dose; in excess of 10 CFR 50 Append k I levels. GH-RE-10 alarms auf isolates the vaste gas decay tank I

USAR Section(s) Reviared: 1 L S, 12. 3. 4 USAR Affected Table (3), Fig.(s) or Dwg.(s); 11.5-3 & 4 12.3-3 Attachment 022-2 ADM 01-022 Page 1 of 3 Rev. 15 Page 11 of 19 Page 2 of 5

~

. . S.E. No. 88-SE-053 3.0 (Continued) discharge line. GT-RE-21 has an alann function only. W e AERM's are not considered as inplant monitors, are located downstregm of all system filters j and aie located in the effluent pathway at the last possible point of l radioactive influent. h is is a typical design feature of AERM monitors. '

In Table 3.3-11 of the 'Itchnical Specification, the Radioactive Gaseous l Effluent Manitoring Instrumentation for the plant is listed.. A review of this table will show that nonitors GH-RE-41 and G[r-RE-60 are not listed, but that nonitors GT-RE-21 and GH-RE-10 are listed. %erefore, monitors GH-RE-41 and GL-RE-60 are not considered by the Technical Specification as effluent nonitors either. ne Technical Specification bases for the alann/ trip setpoints of the effluent monitors listed in 'Inble 3.3-11 is to ensure that the dose at any time, at and beyond the Site Boundary, frcxn gaseous effluents will be within the annual dose limits of 10 CER 20 to Unrestricted Areas, which agrees with the USAR document.

Therefore, the USAR, except for USAR Table 11.5-4, and the Technical Specification reflect that nonitors GK-RE-41 and GL-RE-60 are not effluent monitors. he deletion of these nonitors frun paragraph 3.1.4 of the ODCM l will align the ODCM document with actual plant design features and j functions. % e root cause of this discrepancy is the inaccurate referral to i footnotes 7 and 8 of USAR Table 11.5-4 for the setpoint values of these t nonitors. Bis discrepancy is being correctal by USAR Change Request, '

reference safety evaluation 88-SE-050. Changing the ODCM into a nore valid and accurate dev,=mt will improve plant operation. The margin of safety

'g has not been reduced by this ODCH paragraph correction since no nonitor s setpoints, addressed or not by,the Technical Specification, have been changed as a result of this ODCM change.

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Page 3 of 5 i

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, '. S.E. No. b8-SE-053 REsaurs mmesanc

. ***** PART B 10 CFR 50.59 NrrmAR SAFETY EVAIIMPION *****

3.1 Probability Or m%uences irw rmaarl?

A. Yes X No Will the ,nrnhability of occurrence of an mv'iriant previously evaluated in the USAR be int,manal?

Accident prnhnhility has not been increased by the ODCM text changes since the variables of accident occurrence have not been affected.

B. Yes X 2 Will the prnhability of occurrence of elfunctions of equipnent imLuit to safety, previously evaluated in the USAR, be _irw rmned?

Equipnent mlfunction occurrence probability has not been affected by wu.cdng the ODCM document since no equipnent is affected by the change.

)

C. Yes X No Will the cus qwwm of an acririont previously

  • evaluated in the USAR be increased?

Alarm and isolation functions of radiological instruments retrain unaffected by this ODCM change. The parameters and methodology of the ODCM have not been affected.

l D. Yen X 2 Mill the consequences of a mMua. tion of equipnent, inportant to safety, ymviously eraluated in the USAR, be increasod? ,

Equiprent. mlfunction consequences have not been increased by the correction l m de to the CXCM text.

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Attachm.mt 022-2 ADM 01-022 Page 2 of 3 Rev. 15 Page 12 of 19 Page 4 of 5

9-

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S.E. No. '88-SE-053 ,

ImtmS EEGINEERDG

. ***** PAIE B 10 CPR 50.59 IsrYFAR SAFEST EVAURFIGE *****

'3.2 Di.ffeomt type? .

A. Yes I No Is them a possibility that. an arrirbrit of a~

different type any be cmated from any evaluated pmviously in the IEAR?

No different type of accident has been cmated since the monitors provide a :

mitigating function of accident occurrence arxi their setpoints have not been changed nor the COCM calculatil.on' method.of setpoint formulation.

- B. Yes X No Is them. a Irv=aihility that a malfuncti.on of 4

<=in=mt, important to safety, may bra cmated which is of a different type than any' evaluated previously in the IEAR?

No aqui,n=rit has been affected by the eb'wmrit change; therefore, no different type of malfunction possibility is foreseen cmated.-

3.3 Yes X No Will'a ratr+inr1 in the marxJi n of safety, as

  • fined in the bases for any Technical Wification, result?

Monitor setpoint values have not been affected by correcting the'ODCM document. 'Ihe annual dose limits specified by Technical Specification bases 3/4.11.2.1, 2 & 3 are maintained as well as the limits of 10 CER 20 specified by 3/4.3.3.11.

j

h. 3.4 _ Yes X No Wili Lampscy Permvwirma oc Plant Security be rwhmi? .

l Progrants not affected.

Attachment 022-2 ADM 01-022 Page 3 of 3 Rev. 15 Page 13 of 19 Page 5 of 5

!Y 4 i Y ,

2~.1.1 CONTINUOUS' LIQUID EFFLUENT MONITORS- 1

~

heEtNree monitors' associated with continuous liquid releases are T

- listed-below:

Monitor ID Description 0-BM-RE-52 Steam Generator Blowdown Discharge Monitor:

0-LE-RE-59' Turbine Building Drain

. Monitor _

'0-HF-RE-95 Waste Water Treatment Monitor }

'The Steam Generator. Blowdown Discharge. Effluent Monitor continuously monitors the Blowdown Discharge Pump Outlet to. detect excess' Radio-activity.due to System Domineralizar breakthrough orLabnormal-Primary to Secondary Leakage. The Blowdown Discharge Monitor's High Alarm Setpoint initiates CLOSURE of~the Blowdown Isolation

- valves and-the Blowdown' Discharge Valve. Similarly, the High Radiation Alarm on the, Turbine Building Drain Monitor and Waste Water Treatment' Monitor initiates CLOSURE.of the Drain.Line Isolation Valves to prevent the release of Radioactive Effluents.-

- Monitor Setpoints will be conservatively based on I-131, the : most restrictive' Isotope expected to'be present. This is particularly appropriate for the Turbine' Building DrainJLine: Monitor since the most probable. source is the Secondary Steam System which is expected to have negligible activity unless.there is a significant Primary to Secondary. Leak. LDue to changing activities, it will not be possible to select a Radion'uclide Distribution on which to base the Monitor'Setpoint. Additionally, maximum Effluent Flows and minimum Dilution Flows will normally be assumed.

The High Alarm / Trip Satpoint will be set to correspond to the I-131 MPC Limit at the Boundary of the restricted area from-10 CFR Part 20, Appendix B, Table II, Column 2. The Alert Alarm is set one order of magnitude below the High Alarm / Trip Setpoint.- This high Alarm / Trip Setpoint assures the limits of' Specification 3.11.1.1 are not exceeded

- at.the Boundary of the Restricted Area.

In the event that an Alarm is TRIPPED, an evaluation of the system will be made by taking an actual Isotopic and Fl.ow Analysis of the discharge.

The'above continuous Liquid Effluents are not Radioactive Effluents until activity has been detected by the Liquid Effluent Monitor, a Tritium Analysis of the Secsndary Syntas, or a gross Beta Analysis of the Second4ry-System. l Lt that time an. analysis of the effluent will be made to verify activity in the System Effluent. During periods of n time when the above Liquid Effluents are not Radioactive the High Alarm / Trip Set Point may be set to 1.5 times the back ground Count Rate.

ODCM 3 10-26-88

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2.1.1.1 STEAM GENERATOR BLONDOWN DISCHARGE MONITOR

$ETPOINT (uci/ml) = MPC I-131

  • p B

where, MPC I- = Maximum Permissible Concentration of I-131, 3.0 E-7 uCi/ml.

F, = Dilution flow rate.

F = Blowdown flow rate.

B The Setpoint Calculation is based on the Minimum Dilution Flow Rate, the maximum possible Blowdown Flow Rate, and, due to changing conditions, I-131 which is the most Restrictive Isotope expected to be present.

On the event that an alarm is reached, the setpoint will be re-evaluated

.using the Actual Dilution Flow Rate, the Actual Blowdown Flow Rate, and the Actual Isotopic Analysis as outlined in Section 2.1.2. This Evalu-ation will be used to ensure the limit of Specification 3.11.1.1 was not exceeded. The Setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most Restrictive Isotope.

2.1.1.2 TURBINE BUILDING DRAIN MONITOR AND WASTE WATER TREATMENT MONITOR Setpoint (uci/ml) = MPC

T where, MPC = .0 E-7 uCUml.

I-131 F" = Dilution flow rate.

T F = Et' fluent Flow Rate. l The setpoint is based on the minimum Dilution Flow Rate, the maximum t possible Effluent Flow Rate, and the most Restrictive Isotope expected l l

to be present, I-131.

l On the event that an alarm is reached, the release will be evalu-ated to see if the limit of Specification 3.11.1.1 was exceeded by i using the actual Dilution Flow Rate, the actual Effluent Flow Rate, I and the actual Isotopic Analysis as outlined in Section 2.1.2. The Setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most Restrictive Isotope.

OPCM 4. 10-26-88 l

1 l

i The factors SF, AF, c, (X/Q) and Qg are as defined in Section 3'.1.2.

The results of equations (1) and (2) are compared to determine the smaller.setpoint. The actual Monitor Setpoint is the lower of the two values.

A pre-release Isotopic Analysis is performed for batch releases' from Waste Gas Decay Tanks and Containment Building Purges to determine the identity and quantity of the principal radionuclides.

The appropriate Alarm / Trip Setpoint(s) are adjusted accordingly to ensure that the limits of Radiological Technical Specification 3.11.2.1 are not exceeded.

3.1.4 ALERT ALARM SETPOINT CALCULATIONS The Noble Gas Alert Alarm for the Plant Unit Vent (0-GT-RE-21) and Radwaste Building Exhaust Monitor.(0-GT-RE-10), is set to alert operators to that average concentration which if maintained for a full year would result in the 10 CFR 50 Appendix I Annual Dose Guidelines being reached. Technical Specification 3.11.2.2 limits the annual dose due to Noble Gases to < 10 mrads for Gamma Radiation and 5 20 mrads for Beta Radiation. Technical Specification 3.11.2.3 limits the annual dose to a Member of the Public from Iodine-131, Iodine-133, tritium and all radionuclides in particu-late form with half-lives greater than 8 days in gaseous effluents to $ 15 mrem to any organ. These two Technical Specifications contain the annual dose limits due to gaseous releases found in 10 CFR 50 Appendix I.

3.1.4.1 NOBLE GAS ALERT ALARM SETPOINT CALCULATION r The Alert Alarm Setpoint is the lesser of S 1 (SF x AF) xD xR (3) 3 S $ (SF x AF) xD xR (4)

ODCM 16 10-03-88

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4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

-Ta'ble 4.1 gives specific Radiological Environmental sampling pathways, locations and frequencies corresponding to Table 3.12-1 of Wolf Creek Technical Specifications. Maps showing these locations in relation to the Wolf Creek site are shown in Figures 4-1 through 4-5; Table 4.2 lists distances and directions from lj 1 the site to the sampling locations.

4.1 INTERLABORATORY COMPARISON PROGRAM

' Analysis of WCNOC Radiological Environmental samples is presently.

performed by Teledyne Isotopes,'which participates in the EPA Laboratory Intercomparison Program. Results of intercomparisons are then provided to WCNOC in revisions to Teledyne's Quality Control Manual (IWL-0032-361) which is maintained at the WCNOC l Wichita offices.

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ODCM 33 10-03-88

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  • - AIRBORNE PARTICULKfE AND RADIOlODINE Figure 4-1 10-03-88

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ROOTED AQUATIC PLANTS Figure 4-3 l 10-03-88 40 ,

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INGESTION PATHWAY SAMPL. LNG LOCKil_ONS

  • -MILK s-FOOD PRODUCTS E-FISH (WCCL) A-FISH (JRR)

Figure 4-4 10-03-88 41

___-______.._____-_?______.___________L____'----_-- -- *

~ Jj M ~

.:  :[:

LY W6) NUCLEAR LF CREEK. OPERATING COR ,

Bart D. Withers Proeident and chief Executive Omcor '

February 28, ~ 1989'

.WM 89-0056 U. S. Nuclear Regulatory Commission

l. ATTN: Document-Control Desk l Mail Station F1-137- '

' Washington, D. C. 20555 f

Subj ect : Docket No. 50-482: Semiannual Radiological' Effluent.

Release Report Gentlemen:

a Enclosed is fthe Wolf. Creek Generating Station (WCGS) Radiological Effluent Release Report covering' the period f rom. July 1,1988, to . December 31, 1988.

~ ~'

This report. is submitted.. pursuant to section 6.9.1.7 of.the WCGS, . Unit No. 1, Technical. Specifications.

Very truly yours, Bart D. Withers President and Chief Executive Officer BDW/j ad Enclosure cc: 11 . L. Bartlett (NRC), w/a E. J. Holler OTRC), w/a R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a

. Sen 8

i RO. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 An Equal Opportunity Ernployer MF/HGVET  ;

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