ML20238C530

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Semiannual Radiological Effluent Release Rept 5,Jan-June 1987
ML20238C530
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/30/1987
From: Palmer C, Withers B
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
WM-87-0222, WM-87-222, NUDOCS 8709100176
Download: ML20238C530 (23)
v • d • e


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1 Attachment to WM 87-0222 l

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i Wolf Creek Generating Station Docket No:

50-482 Facility Operating License Ib: IPF-42 SIMIANNUAL RADIOLOGICAL EFETEINP RELEASE RL'PORP Report tb:

5 Reporting Period: January 1,1987 through Junc 30, 1987 Prepared by:

Curt Palmer, Chemistry Supervisor Subnitted by:

j Wolf Creek Nuclear Operating Corporation 4

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g"%BiaST*J2 sx R

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Attachment to WM 87-0222 Iy_RODUCTIOlj 1his Semiannual Radiological Effluent Release Report covers the period of January 1,1987, through June 30, 1987, and satisfies the requirements specified in Technical Specification 6.9.1.7.

Section I provides a summary of the quantities of radioactive liquid and caseous effluents for this reporting period. The format is similar to that provided in Regulatory Guide 1.21, Revision 1.

An elevated release pathway daes not exist at Wolf Creek Generating Station. Therefore, all airborne releases are considered to be ground level releases. A conservative error of thirty percent has been estimated in effluent data. Meteorological data for the period of January 1, 1987, through June 30, 1987, is available on site for review and inspection. There were seven shipments of solid waste during this reporting period.

3 Section II provides Supplemental Information as described in Regulatory Guide 1.21, Revision 1.

Section III provides additional information required by Technical Specification 6.9.1.7.

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Attachment to WM 87-0222 SECTION I Year 1987 REPORT OF RADIOACTIVE EFFLUENTS:

LIQUID Quarter Quar ter Unit 1

2 A.

Fission and Activation Products 1.

Total Release (not including tritium, gases, alpha)

Ci 1.07E-02 1.05E-02 2.

Average _ diluted concentration during period uCi/ml 4.68E-09 3.12E-09

3. _P_ercent_ of Aiplicable Limit 2.14E-01( )

2.10E-01

_B_*__.T[i_t_i_um l.

Total Release Ci 8.85E+01 1.15E+02 2.

Average diluted concentration duringperiod uCi/ml 3.21E-05 3.21E-05

3. _Percen_t_of_ Applicable Limit l.07E+00( )

1.07E+00 C.

Dissolved and Entrained Gases 1.

Total Release Ci 5.99E-02 9.52E-02 2.

Average diluted concentration during period uCi/ml 2.19E-08 3.14E-08 3.

Percent of Applicable Limit 1.10E-02(3) 1.57E-02

_D_ _ _.C o_s_s_31pla_ _ Rad _ipac t i e i ty E

l.

Total Release Ci 0.00E+00 0.00E+00

_E1__Vol_um_e _of_ waste released liters 2.37E+06 2.51E+06

_F.__V_o_lume_ of _ dilution water used liters 9.84E+09 1.30E+10 1.

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 =

(Avgrage diluted concentration) (100)

(2 x 10 'from Techn1Tal Specification 3.11.1.1)

Page 1 of 19 l

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i Year 1987 LIQUID EFFLUENTS I

Continuous Mode Batch Mode

~~NUCLIDES Quarter Quarter Quar ter Quarter RELEASED Unit 1

2 1

2 H-3 Ci 0__. 00E+ 00 0.00E+00 8.85E+01 1.,15E+02 Na-24 Ci 0.00E+00

0. 00E+00 2.63E-05 4.98E-05 Cr-51 Ci 0.00E+00 0.00E+00 i 2.70E-04 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 1.02E-03 1.17E-03 Fe-59 i

Ci 0.00E+00 0.00E+00 9.60E-05 8.42E-05 00-58 Ci 0.00E+00 1 0.00E+00 5.14E-03 3.23E-03 Co-60 Ci 0.00E+00 0.00E+00 1 2.34E-03 3.16E-03 O.00E+00 2.71E-t 6.06E-05 Zn-65 Ci 0.00E+00 Zr-95 Ci 0.00E+00 1 0.00E+00 1.84E-04 5.56E-05 Nb-95 Ci 0.00E+00 0.00E+00 4.71E-04 1.83E-04 Mo-99 Ci 0.00E+00

0. 00E+ 00 8.94E-04
2. 09E-33 I-131 Ci 0.00E+00 0.00E+00

<2.37E-03

4. 21E- 06 I-133 Ci 0.00E+00 0.00E+00 4.28E-06 0.00E+00 C_s-134 Ci 0.00E+00 0.00E+00 8.70E-06 3.44E-05 Cs-137 Ci 0.00E+00 0.00C+00

<l.19E-03 2.10E-05 Cs-138 Ci 0.00E+00 0.00E+00 3.91E-06 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 1.94E-04 3.09E-04 Np-239 Ci

0. 0 0C+00__

0.00E+00 0.00E+00 5.81E-06 Sn-ll3 Ci 0.00E+00 0.00E+00 2.04E-05 2.33E-06_

Page 2 of 19

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Year 1987 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter

(

Quarter Quarter RELEASED Unit 1

2 1

2 Hf-181 Ci 0.00E+00 0.00E+00 1.67E-05 0.00E+00 00-57 Ci 0.00E+00 0.00E+00 2.35E-05 3.02E-05__

Sb-125 Ci 0.00E+00 O.00E+00 1.86E-06 0.00E+00 Kr-85M Ci 0.00E+00 0.00E+00 0.00E+00 1.70E-05

__ Kr-85 Ci 0.00E+00 0.00E+00 5.67E-02 6.llE-02 Xe-131M Ci 0.00E+00 0.00E+00 1.81E-04 3.00E-04 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 5.60E-04 Xe-133 Ci 0.00E+00 0.00E+00 2.44E-03 3.03E-02

__ Xe-135 Ci 1 0.00E+00 0.00E+00 5.92E-04

2. 85E-03 O.00E+00 7.74E-06 0.00E+00 l

Ar-41 Ci 1

0. 00E +00 Sr-89 Ci 0.00E+00 0.00E+00

<1.19E-04

<l.26E-04 St-90 Ci 0.00E+00 0.00E+00

<l.19E-04

<1.26E-04 1

___Fe-55 Ci 0.00E+00 0.00E+00

<2.38E-03

<2.51E-03 Gross supha Ci 0.00E+00 0.00E+00 1<2.38E-04

<2.51E-04 l

1.

Subsequent to the filing of the last semi-annual report, data was received which indicated the presence of Fe-55 in the 4th quarter,1986 composite. The value reported last period was an LLD value. The correct value is 5.18E-04 curies. The resulting dose from this activity is negligible to the total dose reported.

Note: Less than values are calculated using the lower limit of detection (LLD) values obtained at the Wolf Creek Generating Station multiplied by the volume of waste discharged during the respective quarter.

Page 3 of 19

Year 1987 j

LIQUID CUMUIATIVE DOSE SIM4ARY TABIE 1

=

ODCM TECHNICAL CALCULATED SPECIFICATION

% OF DOSE LIMIT LIMIT UNIT 1, QUARTER 1 OF 1987 7UTAL DOSE (MREM) IDR BONE 4.32E-05 5.00E+00 8.65E-04 TOTAL DOSE (MREM) FOR LIVER 9.16E-03 5.00E+00 1.83E-01 TUTAL DOSE (MREM) FOR TOTAL BODY 9.llE-03 1.50E+00 6.07E-01 7UTAL DOSE (MREM) FOR TilYROID 8.98E-03 5.00E+00 1.80E-01 7UTAL DOSE (MREM) FOR KIDNEY 9.04E-03 5.00E+00 1.81E-01 TOTAL DOSE (MREM) FOR LUNG 8.99E-03 5.00E+00 1.80E-01 7UTAL DOSE (MREM) FOR GI-LLI 1.76E-02 5.00E+00 3.52C-01 UNIT 1, QUARTER 2 OF 1987 20TAL DOSE (MRS4) FOR BONE 1.64E-04 5.00E+00 3.28E-03 IUIAL DOSE (MREM) FOR LIVER 8.96E-03 5.00E+00 1.79E-01 TUTAL DOSE (MREM) FOR TUTAL BODY

8. 85E--03 1.50E+00 5.90E-01 7DTAL DOSE (MREM) FOR THYROID 8.57E-03 5.00E+00 1.71E-01 1UTAL DOSE (MREM) FOR KIDNEY 8.72E-03 5.00E+00 1.74E-01 7UTAL DOSE (MREM) FOR LUNG 8.59E-03 5.00E+0A 1.72E-01 TUfAL DOSE (MREN) FOR GI-LLI 1.14E-02 5.0 6 00 2.28E-01 UNIT 1, 70TALS FOR QUARTERS 1 Ato 2 7UfAL DOSE (MREM) FOR BONE 4.17E-04 1.00E+01 4.17E-03 TCTAL DOSE (MREM) FOR LIVER 2.03C-02 1.00E+01 2.03E-01 7UTAL DOSE (MREM) FOR TOTAL BODY 2.00E-02 3.00E+00 6.67E-01 7UTAL DOSE (MREM) FOR THYROID 1.92L-02 1.00E+01 1.92E-01 TUTAL DOSE (MREM) POR KIDNEY 1.96E-02 1.00E+01 1.96E-01 TOTAL DOSE (MREM) FOR LUNG 1.93E-02 1.00E+01 1.93E-01 70TAL DOSE (MREM) FOR GI-LLI 3.42E-02 1.00E+01 3.42E-01 i

1.

Based on Technical Specification 3.11.1.2 which restricts dose to the whole body to q

less than or equal to 1.5 mrem per quarter and 3.d mrem per year. Doce restriction to any organ is less than or equal to 5 mrem per quarter and 10 mrem per year.

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s Year 1987 LIQUID CUMULATIVE DOSE SUbNARY TABLE 2 A.

Fission & Activation Gases Quarter 1 Quarter 2 Total (not including 11-3,

~~~

1.

Total Release - gases _, alpha) Ci 1.07E-02 1

1.05E-02 2.12E-02 2.

Maximum Organ Dose (mrem) 9.55E-03 2.85E-03 1.24E-02 i

5.00E+00 5.00E+00 1

1.00E+01 3.

Organ Dose Limit (mrem) 1 4.

% of Limit 1.91E-01 5.70E-02 1.24E-01 B.

Tritium

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Total Release Ci 8.85E+01 1.15E+02-2.04E+02

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Maximum Orlan Ibse (mrem) 8.05E-03 8.55E-03 1.66E 3.

Organ _ Ibse Limit (mrem) 5.00E+00 5.00E+00 1.00E+01 4.

% of Limit 1.61E-01 1.71E-01 1.66E-01 This table is included to show the correlation between curies released and the associated.

calculated maximum organ dose. Wolf Creek CDCM methodology is used to calculate the maximum organ dose which assumes that an individual drinks the water and eats fish fran the discharge point. Technical Specification 3.11.1.2 organ dose limits are used.

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Year _ 1987 REPORT OF RADIOAC_TIVE EFFLUEtTI'S: AIRBORNE Quarter Quarter Unit 1

2 3

4 Fission & Activation Gases

_A.,___

i 1.

To_t_a_l Release Ci 1.33E+01 1.75E+01

_2. Average release rate for period uCi/sec 9.07E+00 9.95E+00 l

3.

Percent of Techni_c_al Specification Limits 9.48E-03 2.25E-02

{

B.

Iodines J

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_To_tal__ Iodine-131 Ci 4.69E-07 0.00E+00

{

2.

Average _ release rate for period uCi/sec 6.04E-08 0.00E+00 j

3.

Perce_nt_of_ Technical Specification Limits 4.69E-05 0.00E+00 1

_,C_._,_ Par _t_i_gula tes__

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Particulate with half-lives > 8 days Ci 1.14E-04 1.20E-05 1

2.

Average release rate for period uC1/sec 1.47E-05 1.53E-06 3.

Percent of Technical Specification Limits 3.39E-03 5.07E-04 _

4.

Gross Alpha radioactivity Ci 0.00E+00 0.00E+00 D.

Tritium l

__1_._ 'Ibta_l _ Release Ci 1.66E+01 4_._69E+01 2.

Average _ release rate for_ period uCi/sec 2.32E+00 6.62F+DO 1__ Percent of Technical Sgc_ification Limits 1.57E-01 4.45E-01

)

The percent of Technical Specification Limits for fission and activation gases is calculated using the following methodology:

% of Technical Specification. Limit = (Quarterly 'Ibtal Gamma Airdose) (100) 5 mrad i

The percent of Technical Specification Limits for Iodine is calculated using the following methodology:

% of Technical Spec fication Limit = (Total Curies of Iodi,ne - 131)(100) j 1 curie i

Page 6 of 19

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%e percent of Technical Specification Limits for particulate is calculated using the following methodology:

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

% of Technical Specification Limit = Eli hest Organ Dose due to 11-3)(100)

S 7.5 mrem This type of methodology is used since the Wolf Creek Technical Specifications tie releases to doses rather than Curie release rates.

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__-_-__-__- _ - _ A

o Year 1987 GASEOUS EFFLUENTS Continuous Mode Batch Mode

________NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1

2 1

2 1.

Fission and Activation Gases Ar-41 Ci i

_0.00E+00 0.00E+00 2.20E-01 3.44E-01 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85M Ci 0.00E+00 0.00E+00 2.33E-04 2.08E-03

__ Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

Kr-88 Ci 0.00E+00, 0.00E+00 0.00E+00 0.00E+00 l

l Xe-131M Ci 0.00E+00 0.00E+00 6.08E-04 0.00E+00 l

__ _Xe-133 Ci i 1.26E+01 1.20E+01 4.40E-01 7.31E-01 Xe-133M Ci 0.00E+00 0.00E+00 4.llE-04 0.00E+00 Xe-135 Ci 6.01E-02 4.34E+00 1 2.30E-02 6.58E-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 Tbtal Ci 1.27E+01 1.63Et01 6.85E-01 1.14E+00

_ _. _ _))al_ogens (Gaseous) 2 I-131 Ci 4.69E-07

<2. 55E-04

<l.04E <1.94E-07 i

I-133 Ci

<2.48E-02

<2.55E-02

<l.04E-05

<l.94E-05 j

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__ I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f

1 Br-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

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Tbtal Ci 4.69E-07 0.00E+00 0.00E+00 0.00E+00 Note: Less than values are calculated using the lower limit of detection (LLD) values obtained at the Wolf Creek Generating Station 1

multiplied by the volume of air discharged durirs the respective l

quarter.

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Year 1987 GASEOUS EFFLUENTS Continuous Mode Batch Mode

~~NUbLIDES

~

Quarter Quarter Quarter Quarter PZLF16ED Unit i

1 2

1 2

3.

Particulate H-3 Ci 1.66E+01 4.68E+01 1.78E-02 9.69E-02

<l.04E-06

<l.94E-06 3.91E-06 6.67E-07 Mn-54 Ci Co-58 Ci 9.58E-05 9.01E-06

<l.04E-06

<l.94E-06 Co-60 Ci 1.44E-05 2.35E-06

<l.04E-06

<l.94E-06 Zn-65 Ci

<2.48C-03

< 2. 5 5E-03

<l.04E-06

<l.94E-06 Mo-99 Ci

<2.48E-03 1 <2. 55E-03

<l.04E-06

<l.94E-06 Ci

<2.48E-03

< 2. 55E-03

<l.04E-06

<l.94E-06 Cs-134 Cs-137 Ci

<2.48E-03

< 2. 55E-03

<l.04E-06

<l.94E-06 Ce-141 Ci

<2.48E-03

<2.55E-03

<l.04E-06

<l.94E-06

___Ce-144 Ci

<2.48E-03

'<2.55E-03

<l.04E-06

<1.94E-06 Fe-59 i

ci

<2.48E-03

< 2. 55E-03

<l.04E-06

<1.94E-06 Sr-89 Ci

<2.48E-03

<2.55E-03

<l.04E-06

<1.94E-06 St-90 Ci I <2.48E-03

<2.55E-03

<l.04E-06

<l.94E-06 Gross Alpha Ci

<2.48E-03

<2.55E-03

<l.04E-06

<l.94E-06 l

1 Note: Less than values are calculated using the lower limit of detection (LLD) values obtained at the Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter.

Page 9 of 19

a Year __ 1987 GASEOUS CUMUIATIVE DOSE SINMARY Table 1

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

TECHNICAL SPECIFICATION

OF QUARTER 1 OF 1987 LIMIT LIMIT DOSE FR04 RADIOIODINES, PARTICULATE, AND TRITIUM AT cot 7fROLLING LOCATION

1 MAL DOSE (MREM) FOR BONE 2.02E-04 7.50E+00 2.69E-03 1 MAL DOSE (MREM) FOR LIVER 1.20E-02 7.50E+00 1.60E-01 TUTAL DOSE (MREM) FOR TOTAL BODY 1.20E-02

7. 50E+00 1.60E-01 7UfAL DOSE (MREM) FOR THYROID 1.23E-02 7.50E+00 1.64E-01 TOTAL DOSE (MREM) FOR KIDNEY 1.20E-02 7.50E+00 1.60E-01 7UTAL DOSE (MREM) FOR LUNG 1.20E-02 7.50E+00 1.60E-01 TOTAL DOSE (MREM) FOR GI-LLI 1.21E-02 7.50E+00 1.61E-01 QUARTER 2 OF 1987 DOSE FRO 4 RADIO 10 DINES, PARTICULATE, AND TRITIUM AT COffrROLLING LOCATION:

TOTAL DOSE (MREM) FOR BOtE 3.13E-05 7.50E+00 4.17E-04 1UPAL DOSE (MRD4) FOR LIVER 3.35E-02 7.50E+00 4.47E-01 7 MAL DOSE (MREM) FOR 70TAL BODY 3.35E-02 7.50E+00 4.47E-01 7UPAL DOSE (MRD4) FOR THYROID 3.35E-02 7.50E+00 4.47E-01 7UTAL DOSE (MREM) FOR KIDNEY 3.35E-02 7.50E+00 4.47E-01 1UfAL DOSE (MREM) FOR LUNG 3.35E-02 7.50E+00 4.47E-01 7UfAL DOSE (MREM) FOR GI-LLI 3.35E-02 7.50E+00 4.47E-01

]

I TUTALS FOR QUAPTERS 1 AND 2

)

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

7UTAL DOSE (MREM) FOR BONE 2.33E-04 1.50E+01 1.55E-03 7 MAL DOSE (MREM) FOR LIVER 4.60E-02 1.50E+01 3.07E-01 TOTAL DOSE (MREM) FOR TOTAL BODY 4.60E-02 1.50E+01 3.07E-01 1UfAL DOSE (MREM) FOR THYROID 4.62E-02 1.50E+01 3.08E-01 7UIAL DOSE (MREM) FOR KIDNEY 4.60E-02 1.50E+01 3.07E-01

'IUfAL DOSE (MREM) FOR LUNG 4.60E-02 1.50E+01 3.07E-01 i

'IUTAL DOSE (MREM) FOR GI-LLI 4.60E-02 1.50E+01 3.07E-01 1.

Based on Wolf Creek Technical Specification 3.11.2.3 which restricts dose during any calendar quarter less than or equal to 7.5 mrem to any organ and during any calendar year less than or equal to 15 mrem to any organ.

1 Page 10 of 19

Year 1987 GASEOUS CUMULATIVE DOSE

SUMMARY

TABLE 2 A.

Fissi_on & Activation Gases Quarter 1 Quarter 2 Total-l 1.

Tota _1 Release (Ci) 1.33E+01 1.75E+01 3.08E+01 2.

Total Gamma Airdose (mrad) 4.74E-04 1.13E-03 1.60E-03 3.

Technical Sg cification Limit (mrad) 5.00E+00 5._00E+00 l.00E+01 j

4.

% of__ Limit 9.48E-03 2.25E-02 1.60E-02 B.

Particulate 1.

Particulate with half-lives >8 days (Ci) 1.14E-04 1.20E-05 1.26E-04

_2_.__ Maximum _0_rgan Dase (mrem) 2.54E-04 3.80E-05 2.92C-04 j

7.50E+00 7.50E+00 1.50E+01 3.

Organ Dose Limit (mrem) 4.

% of Limit 3.39E-03 5.07E-04 1.95E-03_

C.

Trii.ium 1.

Total Release (Ci) 1.66E+01 1

4.69E+01 6.35E+01 2.

Maximum Organ _ Dose (mrem) 1.18E-02 3.34E-02 4.52E-02 1

3.

Organ _ Dose Limi_t_ (mrem) 7.50E+00 7.50E+00 1.50E+01 4.

% of Limit 1.57E-01 4.45E-01 3.01E-01 D.

Iodine 1.

Total I-131 (Ci) 4.69E-07 0.00E+00 4.69E-07 2._

Maximum Organ Dose (mrem) 2.68E-04 0,00E+00 2.68E-04

_3_.

Organ Dose Limit __(mrem) 1 7.50E+00 7.50E+00 1

1.50E+01 1

4.

% of Limit 3.57E-03 0.00E+00 1.79E-03 1.

This value differs from the " Report of Radioactive Effluents: Airborne" table sirice this value is based on dose and not one (1) curie.

'1his 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 ODQ4 methodology which assumes that an individual actually resides at the release point. Technical Specification 3.11.2.3 organ dose limits are used.

Page 11 of 19

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SECTION II Supplemental Information Facility: Wolf Creek Generating _St_a_ tion License Number: NPF-42 1.

Regulatory Limits A.

Fbr liquid waste effluents A.1 The concentration of radioactive material released in liquid effluents -to UNPLSTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble Fordissolvedorengrainednoblegases,theconcentration gases.

- microcurie /ml total activity.

shall be limited to 2 x 10 A.2 The dose or ;ose 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 te 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 BOUtOARY 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 equal to 1500 mrems/yr to any organ.

B.2 The air dose due to noble gases teleased 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 gamna 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.

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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 ef fluents released, trom each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

i a.

During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and b.

During any calendar year: Less than or equal to 15 mrems to any organ.

Page 12 of 19 i

1 2.

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

Air - covered in section 1.B.

3.

Average energy of fission and activation gaseous effluents is not applicable.

4.

Measurements and Approximations of Tbtal Radioactivity I

A.

Liquid Effluents l

I LIQUID RELEASE SAMPLING METHOD OF

~

TYPE OF ACTIVITY TYPE FPEQUEfCY ANALYSIS ANALYSIS

1. Batch Waste P.H.A.

Principal Gamma Dmmiters Release l

P Tanks Each Batch P.H.A.

1-131 l

a. Waste j

Monitor P

Dissolved and i

Tank One Batch /M P.H.A.

I Entrained Gases l

(Gamma Emitters) l

b. Secondary l

Liquid P

L.S.

H-3

)

Waste Each Batch Monitor G.F.P.

Gross Alpha Tank P

1 0.S.L.

Sr-89, Sr-90 Each Batch O.S.L.

Fe-55 p = prior to each batch l

m = monthly P.H. A. = gamma spectrum pulse height analysis using a High Purity j

Germanium detector.

l L.S. = liquid scintillation I

j G.F.P. = Gas Flow' Proportional counting l

O.S.L. = performed by an Offsite Laboratory There we.te no continuous radioactive waste effluents for this reporting aeriod.

i Page 13 of 19

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B.

Gaseous Waste Effluents

)

SAMPLING METHOD OF TYPE OF l

GASEOUS, RELEASE TYPE FREQUEtCY ANALYSIS ACTIVITY ANALYSIS 1

l p

'Each Tank P.H.A.

Principal Gamma-Waste Gas Decay Tank Grab Sample Dnitters I

Prl"n3 pal Gamma P

i Containment Purge or Each PURGE P.H.A.

Emitters Vent Grab Sample Gas Bubbler and L.S.

H-3 (oxide) 1 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 Fmitters All Release Types as I-131 listed above Continuous P.H.A.

I-133 P.H.A.

Continuous Particulate Principal Gamma Sample Emitters G.F.P.

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

Composite Sr-89, St-90 Continuous Particulate Sample C.

A conservative error of +30% has been estimated. This includes volumetric measurement device, flow measurement device and analytical errors.

S.

Batch Releases There were twenty eight (28) gaseous batch releases during the report period. The longest gaseous batch release took 10.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, the shortest occurred over a fif ty-five (55) minute interval. The average release tcok 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with a total gaseous batch release time of 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br />.

There were 150 liquid batch releases during the report period. The longest liquid batch release took 208 minutes while the shortest took only 41 minutes. '1he average release time for the liquid batch releases -

was 83.1 minutes. Total release time for all 150 liquid batch releases was 207.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

6.

Abnormal Releases

'Ihere were no abnormal liquid or gaseous releases for this report period.

Page 14 of 19

EFFLUEtif AND WASTE DISPOSAL SIMIANNUAL REPORT (1987)

SOLID WASTE SHIPMIWPS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

l. Type of waste Unit 6-month Est. 'Ibtal Period Error %

y

a. Spent resins, filter sludges, m

6.19E+01 evaporator bottoms, etc._

C(

5.91E+00 2.50E+01

b. Dry compressible waste, m

1.76E+01 contaminated equip. etc.

C4 2.14E-01 2.50E+01

c. IrracTiated components, m'

O.00E+00

~

C4 0.00E+00 0.00E+00 control rods, etc.

l d-~Dtlbr TcTescribc.)

m' O.M H+00 Dewatered Resin Ci 1 0.00E+00 0.00E+00

2. Estimate of major nuclide composition (by type of waste) a.

Co-58 9.98E+00 H-3 8.46E+01 Co-60 1.20E+00 l

~M 35 2.20E+00 I

lii-63 1.47E+00

- Cr231-3.72L OT -

- T Mn-54 1.32E-01 I

-- B 8.63E-02 C-

'It-99 1.40E-04 l

l b.

Co-58

~

4.08E+01 0

2.82E+01 l

Z fe255 1.91E+01 l

Co-60 _

l

~~ Ti -3 3 3.78E+00 t

Ma-54 8.05E+00

~~ R

7. 00E-0 T-C_-
3. Solid Waste Disposition Number of Shignents Mode of Transportation. Destination 4

Truck Richland, Washington 3

Truck Beatty, Nevada

4. Class of Solid Waste a.

Class A l

b.

Class A c.

Not applicable d.

Not applicable Page 15 of 19

5. Type of Container a.

Strong, tight b.

Strong, tight c.

Not applicable d.

Ibt applicable

6. Solidification Agent a.

Cement b.

Not applicable c.

Ibt applicable d.

Not apr>licable B.

IRRADIATED FUEL SHIPMENTS (Disposition) l There were no irradiated fuel shipnents during this reporting period.

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Page 16 of 19 l

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SDCTION III l

l Additional Information 1.

Unplanned Rele a ses............................................... Pag e 18 2.

Pr oce ss Con t r ol Pr og ram.......................................... Page 18 3.

Of f si te Dose Calculation Manual.................................. Page 18 4.

Major Changes to Radwaste Systems................................Page 18 5.

Land U se Ce n s u s.................................................. Pag e 18 6.

Rad i oac t i ve S h i pmen ts............................................ Page 18 l

7.

Inoperability of Liquid Effluent Monitoring Instrumentation......Page 18 l

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)

SECTION III Additional Information 1.

Unplanned Releases There were no unplanned releases during this report period.

2.

Process Control Program There were no changes to the Wolf Creek Process Control Program during this report period.

3.

Offsite Dose Calculation Manual (ODCM)

There were no changes to the OD04 during this report period.

4.

Major Changes to Liquid, Gaseous or Solid Radwaste Systems There were no major changes to the Liquid, Gaseous or Solid R3dwaste Systems implemented in the field during this report period.

5.

Land Use Census j

There were no new locations for dose calculations identified during this report period.

6.

Radioactive Shipments l

There were seven shipments of radioactive radwaste during this report period. Four shipments were to Richland, Washington, and three shipments were to Beatty, Nevada.

7.

Inoperability of Liquid Effluent Monitor On January 8, 1987, the Steam Generator Blowdown Liquid Radiation Monitor BM RE-52 had been out of service for thirty days. The monitor was originally removed from service because of spiking of the monitor, j

which resulted in unnecessary isolations of Steam Generator Blowdown and i

numerous nuisance alarms on the process monitoring system. On January 16, 1987, leads were lifted to defeat the isolation function of this i

monitor and to facilitate troubleshooting efforts.

l The plant is utilizing the Blowdown System on the normal operational I

mode, which is full processing capability with heat recovery, i.e., no discharge to the environment.

If blowdown is realigned to discharge to 1

the environment while this monitor is out of service, grab samples may be obtained to monitor the discharge in accordance with Technical Specification requirements.

I Page 18 of.19 i

L_________________________

Basts' on engineering evaluation of spiking on this monitor, corrective actions have been taken to reduce noise in.the' circuitry associated with

~

this monitor. These actions included removal of the ground. from the high voltage power supply and installation of a new D4I/IFI and spike suppression filter between the power supply and signal microprocessor.

While these actions have reduced the frequency of spurious spikes, the problem has not yet been corrected. Further engineering evaluation of-noise and power grounds has been initiated.

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1

i WQLF CREEK.

NUCLEAR OPERATING CORPORATION

!*.78.'nf.$**

chief Ex.cutiv. officer August 31, 1987 kN 87-0222 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555

Subject:

Docket No. 50-482:

Semiannual Radiological Effluent Release Report Gentlemen:

Attached is the Wol f Creek Generating Station Semiannual Radiological Effluent Release Report covering the period from January 1,

1987, through June 30, 1987.

This report is submitted pursuant to section 6.9.1.7 of the Wolf Creek Generating Station, Unit 1, Technical Specifications.

l Very truly yours, Bart D. Withers President and Chief Executive Officer Attachment BDW/jad cc: P0'Conncr (2)

JCummins RMartin PO. Box 411 i Burlington, KS 66839 / Phone: (316) 364-8831 An Equal Opportunny Emp6yer WFHCNET

!h

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