Text

Semiannual Radioactive Effluent Release Rept,Jan-June 1984, North Anna Power Station
	ML20113C217
Person / Time
Site:	North Anna
Issue date:	06/30/1984
From:	Stafford A, Stewart W, Tarantino C; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	James O'Reilly; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
	521, NUDOCS 8504110577
	Download: ML20113C217 (36)
	v • d • e

, , ' l -' 97 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION January 1, 1984 to June 30, 1984 PREPARED BY: c EV C. A. Tarantino Health Physicist REVIEWED BY:

M A. H. S)6ffford Supervisor Health Physics APPROVED BY:

E.Waynefarrell [

Station Manager A 8#

', 'y Page l' FORWARD This report is submitted as required by Appendix A to Operating License No. NPF-4, Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-338, 50-339, Section 6.9.1.12.

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RADIOACTIVE EFFLUENT REIZASE REPORT 4

FOR THE NORTH ANNA POWER STATIN

JANUARY 1,1984 to JUNE 30,1984 l MMX .

, Section~No. Subject Pyue 1 Purpose and Scope . . . . . . . . . . . . 1 2 Data Collection and Analysis -

. . . . ... 2-5 3 Supplemental Information .. . . . . . . 5-7 Appendix A - Effluent Release Data j.

Appendix B -' Offsite Dose Calculation Manual Revisions i

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', 't 1.C PURPOSE AND SCOPE 1.1 This report documents the release of radioactivity from the site for the previous semi-annual period with the dilution and dispersion of the liquid and gaseous radioactive effluents with the environs of the site.

1.2 The report includes summaries of the quantities of radioactive liquid )

J and gaseous effluents and solid waste released from the station as out- l lined in Regulatory Guide 1.21 " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants."

The radioactive liquid and gaseious effluent data are summarized on a quarterly basis for all liquid and continuous gaseous releases. Inter-mittent gaseous releases are summarized separately.

1.3 This report includes a list of unplanned releases from the site to the unrestricted areas of radioactive materials in gaseous and liquid effluents made during the previous 6 month period.

1.4 The report documents the changes made to the Offsite Dose Calculation Manual (ODCM), provides the justification for the ODCM revisions, and gives a list of the new sample locations for the environmental monitoring program which became operational stations during the previous 6 month period.

2.0 DATA COLLECTICN ' AND ANALYSIS 2.1 Effluent Releases The radioactive effluents released to the environment from the station during this report period were sampled and analyzed for radioactivity in accordance with North Anna Technical Specifications, Section 3/4.11.

Sumnaries of the quantities of radioactive materials in liquid and gaseous effluents released to the environment are included in Tables I A, IB,'2A, and 2B.1 The reported quantities of radioactive materials are measured levels. . Table 5 gives the Minimum Detectable Activity (MDA)

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levels for specific nuclides for liquid and gaseous effluents.

2.2 Basis for Calculation of Percent Technical Specification Limit

a. Fission and Activation Products. Tritium, and Dissolved and Entrained Gases in liquid effluents. Tech. Spec. 3.11.1.1.

1. Fission and Activation Products - 10CFR20, Appendix B, Table

! II, Column 2.'

2. Dissolved and Entrained Cases - 2.0 E-4 pCi/ml.

b. Fission and Activation Products in Gaseous effluents-Total Body and Skin-Tech. Spec. 3.11.2.1.a.

1. Total' Body - 500 mrem / year

2. Skin - 1500 mrem / year

c. Iodine, Particulates (Th>8 days) and Tritium in gaseous effluents Tech. Spec. 3.11.2.1.b.

1. Critical Organ - 1500 mrem / year

d. The percent Technical Specification limit is calculated for each quarter and is an independent, i.e. non-additive, percentaof the annual instantaneous dose rate limit.

2.3 Solid k'aste and Irradiated Fuel Shipments A summary of solid waste and/or ' irradiated fuel shipments from the station during this report period is provided in Table 3.

.2.4 Batch and Abnormal Releases Table 4A contains a listing of each abnormal liquid release. and _ the Curies discharged.

There were no liquid batch releases during the. previous six month period.

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A list of the batch and abnormal releases for the gaseous effluente is found in Table 4B and 4C respectively. Table 4B contains a summary of the number of batch releases, the total time period for the releases, the maximum and minimum time period for a release, the average time period for the releases, and the total activity released. Table 4C contains a listing of each abnormal gaseous release and the Curies discharged.

3.3 SUPPLEMENTAL INFORMATION 3.1 List of New Sample Locations a) Station 14-Broadleaf vegetation-end of Rt. 713 near the Lake Anna Marina, approximately 1.7 miles west from intersection of Rt. 713 and Rt. 601.

b) Station 15-Broadleaf vegetation-end of Rt. 613, approximately 1.5 miles west from intersection of Rt. 614 and Rt. 601.

c) Station 16-Broadleaf vegetation-intersection of Rt. 522 and Rt.

208.

3.2 On November 15, 1983, it was determined that milk sample location 14A was no longer available to deliver samples due to the dairy's termination .of business. The unavailability of the sample required the addition of two edible broadleaf vegetation and one control sample in accordance with Technical Specification 3.12.1, Table 4.12-1, item 4c. A review of the meteorological data used in developing the North Anna Offsite Dose Calculation Manual -(ODCM)' determined the broadleaf vegetation sample loca-tions specified in 3.1. Two different locations of highest predicted historical annual average ground level D/Q are at site boundary of sectors NNE and ESE. Samples of an edible broad-leaf vegetation grown nearest to these locations as well as a

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, 'r control broadleaf vegetation sanple grown approximately 15-30 km.

in the NW sector are obtained in accordance with North Anna's ODCM and Radiological Environmental Monitoring Manual (REMM). Section 13 of the ODm was revised and is included in Appendix B of this report.

l' 3.3 An investigation of the ODCM, section 4.2.1, liquid effluent dose calculations, was performed upon determination that the equation used

to calculate the site related dose factor, A g, presented for total body and critical organ in the ODCM, Table 4.0, was overly conservative, The ODCM equation for Ag was modified to include a dilution factor for the fish pathway. In addition, the potable water pathway dilution i factor was modified to include the dilution effects of North Anna's Waste Heat Treatment Facility and the North Anna Reservior. The corporate evaluation and appropriate changes to section 4 of the ODCM are given in Appendix B of this report.

3.4 The liquid effluent composite samples, which require quarterly Sr-89, 4

Sr-90 and Fe-55 analyses per Technical Specifications 4.11.1.1.1,

Table 4.11-1 for continuous and batch releases,were lost for the first quarter of 1984. In order to properly assess the activity of Sr-89, Sr-90 and Fe-55'in liquid effluents for this time interval (January 1-l March 31, 1984) an estimate of the isotopic activity wac determined i

based on a comparison of the liquid composite sample analytical results. for the 4th quarter,1983 and 2nd quarter,1984 in conjunction

with plant' operating conditions. Review of this data indicated less than Minimum _ Detectable Activity (MDA) for--Sr-89, Sr-90 and.Fe-55.in.

liquid effluents during the 4th quarter 1983 and less than MDA for l Sr-90 and Fe-55 during the ' 2nd quarter,1984. Sr-89 activity in-

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liquid effluents during the 2nd quarter,1984' was reported at 3.46 E-3 Curies. Based upon this assessment, the Sr-90 and Fe-55 activity in-liqiud effluents during the 1st quarter,1984 was estimated as less

' 8 Pags 7 than MDA. In order to estimate the Sr-89 activity during the 1st quarter, 1984, the concentration, in uC1/ml, of Sr-89 was calculated for the 2nd quarter,'1984, using the reported Sr-89 activity and total volume of liquid waste released during the 2nd quarter. This Sr-89 concentration, in uCi/ml, was then multiplied by the volume of liquid waste released during the 1st quarter, 1984. The result was 4.19 E-3 C uries of Sr-89.

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. *s APPENDIX A RADI0 ACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 1,1984 to JUNE 30, 1984 EFFLUENT RELEASE DATA TABLE 1A GASEOUS EFFLUENTS - SUMMATION TABLE IB GASEOUS EFFLUENTS TABLE 2A LIQUID EFFLUENTS - SUMMATION TABLE 2B LIQUID EFFLUENTS TABLE 3 , SOLID WASTE SHIPMENTS TABLE 4A LIQUID EFFLUENTS - ABNORMAL RELEASES TABLE 4B GASEOUS EFFLUENTS - BATCH RELEASES TABLE 4C GASEOUS EFFLUENTS - ABNORMAL RELEASES TABLE 5 MINIMUM DETECTABLE ACTIVITY IEVELS i

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TAJLE LA EFFLUENT AND WASTE DISPOSAL 0! N AUNUAL REPORT (1984 ) .-

CASEOUS EFFl.UENTS-SUIDiAT1013 ilF AI.L RELEASES NORTil ANNA POWEh STATION ,

DOCKET # 50-338, 50-339 -

UNITS lst QUARTER 2nd QUARTER

% ERROR A. Fission & Activation gases:

1. Total Release Activity. Ci 3.99 E+3 3.87 E+3 1.5 E+1

2. Average Release Rate for Period. uC1/sec 5.07 E+2 4.92 E+2

3. Percent of Technical Specification Limit (Total Body). %' 6.46 E-2 6.94 E-2

4. Percent of Technical Specification Limit (Skin). % 2.31 E-2 2.29 E-2 B. Iodines & Particulates(Th) 8 days) & Tritium: -

1. Iodines: ,

a. Total Iodine-131 Activity. Ci 153 E-2 6 . 41 E-2 1.5 E+1

b. Average Release Rate for Period. uCi/sec 1.95 E-3 8.14 E-3

2. Particulates (Th> 8 days): '

a. Total Particulates (T > 8 days) Activity. C1 1.24 E-3 2.58 E-3 1.5 E+1

b. Average Release Rate for Period. uCi/sec 1.58 E-4 3.28 E-4

c. Cross Alpha Radioactivity. Ci 1.87 E-5 8.50 E-5

3. Tritium: ;

a. Total Release Activity. Ci 5.36 E-1 2.02 E+0 1.5 E+1

b. Average Release Rate for Period. uCi/sec 6.82 E-2 2.57 E-1

4. Percent of Technical Specification Limit for I-131, Particulates(T > 8 days), Tritium. 1.81 E-2 8.20 E-2 N ,.

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TABLE IB EFFLUENT AND WASTE DTSPOSAL SEMI-ANNUAL REPORT (1984 ) -Page 1 of 2 ,

CASEOUS EFFLUENTS NORTil ANNA POWER STATION DOCKET # 50-338, #50-339 ,-

CONTINUOUS MODE BATCII HODE NUCLIDES REl. EASED UNITS lst QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER FISSION & ACTIVATION CASES :

Krypton-85 (Kr-85) Ci 6.08 E+0 4.96 E+0 6.08 E+0 Krypton-85m (Kr-85m) Ci 9.97 E+0 1.83 E+1 8.14 E-1 Krypton-87 (Kr-87) Ci 1.09 E+1 1.60 E+1 5.08 E-2 Krypton-88 (Kr-88) Ci 1.93 E+1 3.45 E+1 1.47 E-1 Xenon-131m (Xe-131m) Ci 1.14 E-1 4.88 E+0 1.16 E+1 3.37 E+0 X non-133 (Xe-133) Ci 1.55 E+3 2.53 E+3 2.02 E+3 1.08 E+3 Xcnon-133m (Xc-133m) C1 4.97 E+0 2.23 E+1 3.90 E+1 1.67 E+0 Xenon-135 (Xc-135) Ci 2.61 E+2 5.86 E+1 2.43 E+1 7.79 E-1 X:non-135m (Xc-135m) Ci 2.08 2+1 6.06 E+1 1.26 E-1 1_15 F-7 Xenon-138 (Xe-138) Ci 9.35 E+0 2.82 E+1 l_20 E-5 others (specify) --- --- _--

Arnon-41 (Ar-41) C1 3.38 E+0 5.17 E+0 4_17 F-2 1_16 F 5 Ci Unidentified C1 --- --- ---

Total For Period Ci 1.89 E+3 2.78 E+3 2.10 E+3 1.09 E+3

10 DINES:

lodine-131 (I-131) Ci . 1.35 E-2 6.24 E-2 1.82 E-3 1.74 E-3 lodine-132 (1-132) C1 4.05 E-5 3.05 E-5 6.17 E-6 5.89 E-4 Iodine-133 (I-133) Ci 1.60 E-2 1.91 E-2 9.78 E-5 1.48 E-3 Iodine-134 (1-134) Ci 1.33 E-6 4.17 E-4 Icdine-135 (I-135) C1 6.23 E-5 5.52 E-6 3.21 E-6 2.63 E-2 Total for Period C1 2.96 E-2 8.85 E-1 1.93 E-3 3.05 E-2 PARTICULATES: -

Strontium-89 (Sr-89) Ci 1.55 E-Il 8 1.62 E-11 Strontium-90 (Sr-90) Ci 1.24 E-12 '

Cealum-134 (Cs-134) Ci 1.40 E-4 5.43 E-6 1.2 3 E-4 3.45 E-4 Ceolum-137 (Cs-137) C1' 3.44 E-4 1.53 E-4 1.22 E-4 5. 78 E-4 8:rium-140 (Ba-140) Ci

7.91 E-9 Lanthanum-140 (La-140) Ci 4.77 E-8 Oth rs (specify)

Chromium-51 (Cr-51) Ci 2.58 E-8 Manganese-54 (Mn-54) C1 2.44 E-7 =

Iron-55 (Fe-55) Ci 3.29 E-10 .

Sodium-24 (Na-24) C1 2.12 E-7 2.69 E-5 Unidsntified Ci Total for Period Ci 1.98 E-1 3.24 E-1 3.03 E-2 3.10 E-1

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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1984) ~

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES -

NORTil ANNA POWER STATION DOCKET #50-338 . #50-339 -

UNITS Ist QUARTER 2nd QUARTER '

ER A. Fission & Activation products :

1. Total release (not including tritium, gases, alpha). Ci .

1.4 E+0 1.88 E+0 1.5 E+1 i

2. Average diluted concentration during period. uCi/ml 1.96 E-9 3.1 E-9

3. Percent of applicable limit (T.S.) % 8.2 E-2 5.36 E-1 B. Tritium :

1. Total release activity. Ci 2.16 E+2 2.12 E+2 1.5 E+1

2. Average diluted concentration during period. uCi/ml 3.03 E-7 3.49 E-7

3. Percent of applicable limit (T.S.) % l.01 E-2 1.16 E-2 C. Dissolved and entrained gases :

1. Total release activity. C1 4.02 E+0 1.08 E+1 1.5 E+1

2. Average diluted concentration during period. uCi/ml 5.56 E-9 1.78 E-8

3. Percent of applicable limit (T.S.) % 2.83 E-3 8.90 E-3 D. Cross Alpha radioactivity :

1. Total release activity. Ci

_l.5 E+1 E. Volume of waste released (prior t dilution). -

Liters 7.89 E+7 6.52 E+7 2.0 E+0 F. Volume of dilution water used during period.

1.iters 7.12 E+11 6.07 E+11 2.0 E+0 j

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EFFLUENT AND WASTE DCPOSAL SEMI-ANNUAL REPORT (1984 ) .

LIQUIL EFFLUENTS NORTH ANNA POWER STATION.

DOCKET # 50-338. #50-339 -

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CONTINUOUS MODE BATCll MODE NUCLIDES RELEASED UNITS lst QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER.

FISSION & ACTIVATION PRODUCTS Strontium-89 (Sr-89) Ci 4.19 E-3 3.46 E-3 Strontium-90 (Sr-90) Ci ~

Cssium-134 (Cs-134) Ci 3.99 E-1 3.17 E-1 9.31 E-5 3.67 E-5 Ceslum-137 (Cs-137) Ci 6.50 E-1 5.27 E-1 1.93 E-4 8.43 E-5 Iodine-131 (I-131) Ci 1.27 E-1 3.96 E-2 3.66 E-4 3.7 E-5 lodine-133 (I-133) Ci 7.27 E-2 1.32 E-3 2.01 E-4 4.59 E-5 lodine-135 (I-135) Ci 1.40 E-2 8.81 E-5 2.94 E-5 Cobalt-58 (Co-58) C1 2.14 E-2 2.04 E-2 5.7 E-6 9.46 E-7 Cobalt-60 (Co-60) Ci 1.64 E-2 9.18 E-3 3.44 E-7 1.92 E-6 Iron-59 (Fe-59) Ci Zinc-65 (Zn-65) C1 Chromium-SI (Cr-SI) Ci Manganese-54 (Mn-54) Ci 1.05 E-3 6.18 E-4 4.56 E-7 Niobium-95 (Nb-95) Cl Zirconium-45 (Zr-95) Ci Molybdenum-99 (Pfo-99) Ci Tcchnetlum-99 (Tc-99) C1 Barium-140 (Ba-140) Ci 1.33 E-5 Lrnthanum-140 (La-140) Ci 1.45 E-3 2.75 E-3 3.82 E-6 Carium-141 (Ce-141) Ci Oth:r (s'pecify) ---

Sodium-24 (Na-24) C1 3.65 E-3 2.41 E-3 2.55 E-6 1.07 E-6 Rubidium-88 (Rb-88) Ci 1.35 E-2 IInidentified C1 --- --- -- -__

Total For Period (Pages 1&2) Ci 1.38 E+O 9.67 E-1 1.88 E-2 2.67 E-4 DISSOLVED AND ENTRAINED GASES ---

Xenon-131m (Xe-132m) Ci 7.08 E-3 8.93 E-2 7.08 E-5 Xenon-133 (Xe-133) Ci 3.63 E+0 1.06 E+1 3.96 E-3 5.31 5:-6 Xenon-133m (Xe-133m) Ci 1.8 E-2 6.59 E-2 Xenon-135 3.07 E-1 (Xe-135) C1 7.43 E-2 2.05 E-3 1.02 E-5 Xenon-135m (Xe-135m) C1 3.71 E-2 1.61 E-3 8.48 E-5 Other (specify) --- ---

tinidentifled C1 ---

Total For Period (Pages 1&2) Ci 4.01 E+0 1.08 E+1 6.42 E-3 Triilum 2.I6 E+2 [ 1.5_5_E-5 (11-11). Ci ,

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1/84-6/84)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

'A. . S_07.ID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH EST. TOTAL

1. Type of Waste UNIT PERIOD ERROR, %

a. Spent resins, filter sludges, evaporator m3 1.07 E +2 + 1 .0 E +1 bottoms, etc. Ci 9.03 E +1 + 1 .0 E +1

b. Dry compressible waste, contaminated m3 1,38 E +2 11.0 E +1 equipment, etc. C1 1.13 E +1 il.0 E +1

c. Irradiated components, control m3 0. E . E rods, etc. Ci 0. E. . E

d. Other (describe) m 0. E . E Ci 0. E . E

2. Estimate of major nuclide compositon (by type of waste)

a. Cr-51 % 1.4 E -1 Mn 54 % 1.14 E + 0 Co 58 .

% 4.94 E + 0 Co_60 % 1.45 E +1 Sb 122 % 1.53 E +0 I-131 % 4,86 E + 0 Nb-95 % 8.3 E -1 Cs-134 % 1.44 E +1 Cs-137 .

% 2.94 E +1 Ba-140 % 6.2 E -1

-La-140 % 6.5 E -1 Sr-90 % 1.8 E -1 Tc -99 % 4.0 E -3 I 129 % 3 .0 E -4 v C 14 % 1.4 E +1 ~

H -3 % 9.84 E+0 Ni-63 % 2.63 E+0 Pu-241 % 4 .6 E -1 Cm-242 % 2 .0 E -2 Pu-238 % - 2 .0 E -3 Pu-239 % 3 .0 E -3 Pu-242 % 2 .0 E -4 Am-241 % 1.0 E -3

! Cm-244 % 1.0 E -3 i

b. Mn-54 % 1.89 E+0 t

Co-57 % 4 .0 E -2 Co-58 % 3.42 E+0

}f Co-60 % 2.89 E +1 l S b-122 % 1 .24 E+0 Ce-144 % 1.06 E +0 1 Nb-95 % 4.8 E1 1-131. % 9 .0 E1 Cs -134 % 8.98 E +0 Cs -137 % 2.48 E+1 -

Sr -90 % 1 .94 E+0 '

Tc -99 % 2 .3 E -1 I-129 % 2 .0 E -3 C -14 %- 1 .36 E+1 4

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TADIE 3-CONTINUED

PAGE 2 -

R. Estimatia of anjor nuclide composition (by typa of wasta) 4

b. H-3 % 4.83 r +0

Ni-63 Y 5.61 r +0 Pu-241 1 1.8 r40 Cm-242 Y 3.0 v'-2 Pu- 2 38 2 2.0 r -3 Pu- 239 Y 4.0 v -3 '

Pt>-242 I- 20 E -4 Am-241 % 10 E _3 i Cm-244 % 1.0 E _3 -

% . E

. % . E E

c. % .

E

% . E E

, % . E

% . E

% . E .

% . E

% . E-

% . E

% . E

% . E

3. Solid Waste Disposition NUM3ER OF SHIPMENTS MODE OF TRANSPORTATION , DESTINATIm 28 Private Vehicle Barnwell, SC

1. 1RRADIATED TUEL SHIPMENTS -(Disposition)

NUMBER 0F SHIPMENTS _ MODE OF TRESPORTATIW DESTINATIm

Page 1 of 1 TABLE 4A Abnormal Releasea For Liquid Effluenta-lat and 2nd Quarters,1984 f

LIST OF RELEASES CURIES REIZASED 84-ATD-1 2.39 E-2 84- ATR-2 3.82 E-4 84- ATR-3 1.2 E-5 84-Arn-4 1.3 E-2

, 84-ALR-5 9.46 E-2 84-ALR-6 , 1.3 E-6 84-AT:R-7 2.69 E-5 84-ALR-8 never issued '

84-ALR-9 6.73 E-7 84-ALR-10 1.03 E-3 84-ALR-11 2.12-E 84-ALR-12 2.35 E-4 84-ALR-13 8.5 E-7 84-ALR-14 2.32 E-2 84-ALR-15 6.38 E-6 1

l i

i NOTE: 84-ALR-# is the identification for Abnormal Liquid Release forms.

t I

,.e --

k- Y_ ,--

Page 1 of 3

)

. . TABLE 4B

Batch Releases ;

For Gaseous Effluents-1st and 2nd Quarters,1984 Duration of Release '

' List'of' Releases Minutes 84-GW-1 655 84-GW-2 319 84-GW-3 711 84-GW-4 485

, 84-GW-5 2446 84-GW-6 1445 84-GW-7 1189 84-GW-8 899 j- 84-GW-9 644 84-GW-10 863 84-GW-11 876 84-GW-12 950

. 84-GW-13 1050 84-GW 544 84-GW-15 420 84-GW-16 487' 84-GW-17 334 84-GW-18 1055 84-GW-19 489 84-GW-20 1488 i

84-GW-21 745 84-GW-22 403 i 84-GW-23 737 84-GW-24 795 84-GW-25 570 GW-26 866 84-GW-27 1161

1 Purge (01/11) . 951

1 Purge (01/15) 963

2 Purge (03/31) 261

1 Purge (05/13) 1451 84-RxR 216 84-RxR-8 240 84-RxR-12 200 Summary of Gaseous. Batch Releases:

Total number of batch releases 34

, Total time period for batch releases 26908 mins.

Maximum time period for a batch release 2446 mins.-

Average - time period for batch releases '791 mins.

Minimum time period for a' batch release -200 mins.

The total activity due to batch releases is recorded in Table 13.

NOTE:,

, 84-GW-# is- the identification.for Waste Gas Decayitank release forms

1 or #2 Purge -(date) is the identification for Purge Data.

84-RxR-# -is the identification for Hogging Data -

A >-. - - , , - - , . . , ---

Pcga 2 of 3

. . TABE 4C Abnormel Ralsests For Gaseous Effluents-Ist and 2nd Quarters, 1984 LIST OF REI. EASES CURIES REIIASED 94-ACR-1 4.37 E 4 84-ACR-2 2.91 E-4 84- ACR-3 5.1 E-1 84-ACR-4 never issued ;

84-ACR-5 <MDA l 84-ACR-6 ~

1.46 E-3 84-ACR-7 '7.93 E-3 84-AGR-8 2.04 E 4 84-AGR-9 1.3 E-3 84- AGR-10 1.19 E-3 84- AGR-11 7.58 E-3 84- AGR-12 5.31 E-6 84- AGR-13 6.78 E-6 84- AGR-14 <MDA 84- AGR-15 1.16 E-1 84-AGR-16 <MDA 8 4- AGR-17 1.05 E+3 8 4- AGR-18 1.29 E+0 84- AG R-19 7.32 E l 84-ACR-20 7.46 E-4 84 aco-21 5.62 E-3 84 ARR-22 2.54 E+1 84-ACR-23 9.8 E-1 84-ACR-24 1.15 E'O 84-ACR-25 2.81 E-1 84-ACR-26 2.91 E-1 84-AGR-27 8.66 E-2 84-AGR-28 1.34 E-2 84-AGR-29 3.06 E-5 84-SGR-30 6.88 E+0 84-AGR-31 1.23 E+0 84-AGR-32 <MDA 84-AGR-33 1.02 E-4 84- AGR-34 2.25 E-3 8 4- AGR- 35 1.23 E-2 84-AGR-36 1.66 E-3 84- AGR-37 3.21 E-6 7

84-AGR-38 <MDA l

84-AGR-39 2.03 E+0 84- ACR-40 never issued i 8L 1CR-41 <'mA 84- ACR-4 2 3.22 E-3 84-ACR-43 3.41 E-1 84-ACR-44 1.33 E-1 84- ACR-4 5 <MDA __

84-ACR-46 2.2 E-3 84- ACR-4 7 <WA 84- AGR-48 1.44 E-1 84-AGR-49 1.31 E-3 84- AG R-50 2.36 E-2 84- ACR-51 1.63 E-2

Page 3 of 3 TABLE 4C Abnormal Releases For Gaseous Effluents-1st and 2nd Ouarters, 1984

)

LIST OF RELEASES CURIES RE!. EASED 84- AGR-52 8.04 E-2 84-AGR-53 4.86 E-2 84-AGR-54 never issued 84-AGR-54A 4.54 E-3 84-AGR-54E 1.19 E-3 84-AGR-54C ~

6.37 E-3 84-AGR-55 <MDA 84-ACR-56 3.65 E+2 84-ACR-57 1.82 E-1 84-ACR-58 1.44 EA2

( 84-ACR-59 8.23 E-1 i 84-ACR-60 6.31 E-6 84-SCR-61 8.26 E-2 84-AGR-62 <MDA 84-AGR-63 1.65 E-5 84-AGR-64 5.42 E-6 84-AGR-65 1.24 E-4 S4-AGR-66 2.56 E-1 84-AGR-67 <MDA 84-ACR-68 2.50 Ea0 i

i l

t 1

j-NOTE: 84-AGR-# is the identification for abnormal gaseous release forms.

4 e

. , . , _ , , _ . c. , . , _ . _ _ . ._ --

TABLE 5 MINIMAL DETECIABLE ACTIVITY LEVELS (uCi/ml)

NUCLIDE GASEOUS EFFIDENTS LIQUID EFFLUENTS Ar-41 3.80 E-7 Kr-85m 5.65 E-5 Kr-85 1.43 E-4 Kr-87 1.28 E-6 Kr-88 1.57 E-6 Xe-131m 1.76 E-5 2.81 E-6 s XI-133 1.12 E-6 2.02 E-7 X:-133m 3.94'E-6 5.41 E-7 X2-135 5.59 E-7 6.28 E-8 Xs-135m 2.85 E-6 1.33 E-7 Xs-138 9.63 E-6 I-131 1.73 E-13 6.61 E-8 I-132 .

1.75 E-13 5.08 E-8 I-133 1.40 E-13 5.78 E-8 I-134 2.89 E-13 I-135 9.33 E-13 2.77 E-7 Co-58 1.18 E-13 5.27 E-8 Co-60 1.33 E-13 7.28 E-8 .

Co-134 1.26-E-13 Ca-137 1.56 E-13 Cs-138 3.11 E-13 Mn-54 1.09 E-13 5.82 E-8 Zn-65 3.53 E-13 Nb-95 1.20 E-13 5.17 E-8 Rb-88 1.36 E-12 Nc-24 1.82 E-13 4.91-E-8 Sb-122 1.97 E-13 8.34 E-8 Tc-131m 3.41 E-13 1.31 E-7 La-142 2.47 E-13 H-3 1.02 E-9 3.21 E-6 Fc-59 2.22~E-13 8.60 E-8 Mo-99 6.26 E-13 4.14 E-7 Ce-141 1.97 E-13 1.15 E-7 l Ce-144 7.54 E-13 5.24 E-7 '- _ _ _

Alpha 2.75'E-15 8.88 E-9 l.

l

8 9 e 8 APPENDIX B 0FFSITE DOSE CALCIILATION MANUAL REVISIONS I

f i

t

l l

NAPS ODCM Section 4.2.1 Calculations and Recommended Revisions

. I. Problem: Modify NUREG-0133 Section 4.3.1 equation for Ag to allow utilization of a dilution factor for the fish consumption pathway. Recalculate ODCM 4.0 values for the liquid ingestion pathway dose factors for the total body and critical organ.

II. References

1. North Anna Power Station ~Offsite Dose Calculation Manual Units 1 and 2, 12/21/83.

2. NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants ,'.' October 1978.

3. USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man From

, Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Rev.1, October 1977.

4. North Anna Power Station Units 1 and 2, Updated Final Safety Analysis Report, Sections 11.2.7 and 11.2.8.

5. Letter to Mr. W. W. Cameron from NUS with revised writeup of the input to the North Ann'a ODCM, January 15, 1979.

III. Methodology

1. NUREG-0133, Section 4.3.1, pp. 16-17.

a) According to NUREG-0133, the following equation should be used to determine the dose factors related to liquid effluents for fresh water sites: A =1.14E+05(730/D g y+ 21BF g) DF g where:

A g = composite dose parameter for the total body or critical organ of an adult for nuclide,1, for all appropriate pathways , mrem /hr per uCi/ml.

1.14E+05 = units' conversion factor, 1E+06pci/uC1 x 1E+03 ml/Kg

8760 hr/yr.

~

730 = adult water consumption,'Kg/yr.

D y= Dilution factor from the near field area within one-quarter mile of i

.tha reisesa' point to tha potable water intaka for the adult water consumption.

BFg = Bioaccumulation factor for nuclide, i, in fish, pCi/kg per pCi/1, l

from Table A-1 of Regulatory Guide 1.109.

21 = Adult fish consumption, kg/yr.

' DFg

= Dose conversion factor for nuclide, i, for adults in pre-selected organ, r, in mrem /pCi, 'from Table E-11 of Regulatory Guide 1.109.

This equation is used in the North Anna ODCM Section 4.2.1. The dilution factor, Dy , value of 1.37 was obtained from the NUS input to the North Anna ODCM and was calculated to be the ratio of the average flow at the U.S.G.S. gauging station at Doswell (302 cfs) to the average release rate at the North Anna Dam (220 cfs). This dilution factor is overly

conservative as it does not include the dilutional effects of the waste t

heat treatment facility and Lake Anna.

b) The NUREG-0133 dose factor is essentially a combination of the potable and aquatic foods (fish) pathways.

t 2 .- Regulatory Guide 1.109, Rev. 1, p. 1.109-12 a) According to R.G. 1.109, the following equation should be used to determine

the dose to an individual from the potable water pathway

Rapj = 1100 Mp Uap I Q1 D,g 3 exp(-Ag tp)

-F i where:

1100 = the' factor to convert from (Ci/yr)/(f t /sec) to pC1/1 Mp =.The mixing' ratio (reciprocal ~ of the dilution factor) at the point of exposure -(or the point of withdrawal of drinking water of point of harvest of aquatic ' food), dimensionless.

Uap = the usage factor that specifies the exposure time or intake rate

-for an individual of age group a associated.with pathway- p, in.

t . .

hr/yr,.1/yr, or'kg/yr.

1

,e+- T

, - . L. ' ,

'F = the flow rate of the liquid effluent ft /sec.

Q = the release rate of nuclide 1, Ci/yr.

1 Daipj = the dose factor, age group a, nuclide i, pathway p, organ j, in mrem /pci.

exp(-Ag tp) = radioactive decay for nuclide i, with transit time tp.

This equation is analagous to the NUREG-0133 equation page 15 and the equation for Ag . The R. G. equation allows the use of the mixing ratio which is essentially the reciprocal of the NUREG-0133 dilution factor i used in the ODCM. Note that the R. G. Mp mixing ratio should be deter-mined at the point of withdrawal of drinking water. The NUS value.for the~0DCM D, dilution factor does not include the dilution contributions of the WTF or the Lake, only from the North Anna dam to Doswell.

Therefore, using the following dilution factors from the NAPS UFSAR, Section 11.2.7, a new potable water Dy mixing ratio can be calculated.

WHTF dilution factor = 0.66

-l Lake Anna dilution factor = 0.63

! Dam to Doswell dilution factor = 220 cfs = 0.73 302 cfs D, (mixing ratio) = 1

= 3.29 0.66 x 0.63 x 0.73 It is recommended that this D,value be used rather than the-NUS value of 1

1.37.

b) According to R. G. 1.109, the following equation should be used_to 1

determine the dose to an individual from the aquatic foods pathway:

l Rapj = 1100Uap Mp I Qg Bg p Daipj exp(-Atp) l F i l

. .where : -

B gp

= the equilibrum bioaccumulation factor for nuclide i in pathway p.

The- remaining parameters have previously been defined. This equation is

~

again analagous to the NUREG-0133 equations with the following exception:

the equation for A gin the NUREG does not incorporate a dilution factor.

The UFSAR Section 11.2.8 calculates doses to the maximum exposed individual from liquid effluents based on the estimated equilibrium activity concentrations utilizing the WHTF and Lake Anna dilution factors. It is recommended that the UFSAR Section 11.2.7 WHTF facility dilution factor of 0.66 be used with the aquatic (fish) pathway. The NUREG-0133 equation forf A should be revised as follows for incorporation into the ODCM:

Ag = 1.14E+05(730/Dy + 21BFf /D,) DF f where:

Dy = 3.29 defined above.

D, = 1 = 1.52 0.66 Using the above equation for A and the new values for Dy and D,, . Table f

4.0 can be recalculated as stated on the'following page.

4 1

e a

w w

. Liquid Ingnetion Pcthwry Don Fsctor for North Anne Power Station Unit Nos. 1 and 2 Total Body A t Critical Organ *A g mrem /hr mrem /hr RADIONUCLIDES uCi/ml uCi/ml H-3 2.80 E+00 2.80 E+00 Na-24 3.11 E+02 3.11 E+02 Cr-51 9.05 E-01 ND Mn-54 5.71 E+02 2.99 E+03 Fe-55 8.10 E+01 3.47 E+02 Fe-59 7.15 E+02 1.86 E+03 Co-58 1.74 E+02 7.75 E+01 Co-60 4.91 E+02 2.23 E+02 Zn-65 2.21 E+04 4.89 E+04 Rb-86 3.12 E+04 6.70 E+04 Sr-89 6.41 E+02 ND Sr-90 1.35 E+05 ND Y-91 2.44 E-01 ND Zr-95 2.01 E-01 2.97 E-01 Zr-97 4.73 E-03 1.03 E-02 Nb-95 8.79 E+01 1.64 E+02 Mo-99 3.37 E+01 1.77 E+02 Ru-103 3.27 E+00 ND -

Ru-10 6 1.43 E+01 ND Ag-110m* 2.54 E+00 4.28 E+00 Sb-124* 2.98 E+01 1.42 E+00 Sb-125* 1.14 E+01 5.37 E-01 Te-125m 2.35 E+02 6.36 E+02 Te-127m 5.41 E+02 1.59 E+03 Te-129m 1.19 E+03 2.81 E+03 Te-131m 4.62 E+02 5.54 E+02 Te-132 1.00 E+03 1.07 E+03 I-131 1.67 E+02 2.91 E+02 I-132 9.29 E+00 2.66 E+01 1-133 3.68 E+01 1.21 E+02 I-134 5.04 E+00 1.41 E+01 I-135 2.09 E+01 5.67 E+01 Cs-134 3.84 E+05 4.70 E+05 Cs-136 5.87 E+04 8.16 E+04 Cs-137 2.27 E+05 3.46 E+05 Cs-138 1.71 E+02 3.46 E+02 Ba-140 4.20 E+01 8.06 E-01 Ia-140 2.15 E-02 8.15 E-02 Ce-141' 1.93 E-02 1.70 E-01 Ce-143 3.63 E-03 3.28 E+01 Ce-144 7.04 E-01 5.48 E+00

( Np-239 2.65 E-03 4.80 E-03

Bioaccumulation factors for Ag-110m, Sb-124, and Sb-125 were obtained from WASH-1258,

" Final Environmental Statement Concerning Proposed Rule Making Action: Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the &iterion" As Low As Practicable "for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents", Vol. 2, July 1973. Dose factors for Sb-124 and Sb-125 were obtained from NUREG/CR-1276, " Users Manual for LADTAP II- A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid

' Effluents", May 1980.

Excerpts from HP-0DcH-4 with revisions

_, H.P.-0DCM-4

* *

Page 2 of 5 05-03-84

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.1.2 requires that: "The dose or dose l commitment to the maximt.m exposed MEMBER OF THE PU3LIC from radioactive mate rials in liquid efficents released from each reactor unit, to l

)

UNRESTRICTED AREAS (see Figure 5.1-1) shall be limited: '

a. During any calendar quarter to less than or equal to 1.5. mrem to the total body and to less than or equal to 5 mrem to the critical organ, and -

1

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to the critical organ".

2. CALCULATION 2.1 Dose contribution shall be calculated for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS based on the follcwing expressions:

D = t F I C.*A

! i v.

q '4here.:

D= the cumulative dose commitment to the total body or critical organ, from the liquid effluents for the time period t, in mrem; t= the length of the time period over which C.*and I are averaged for all liquid releases, hours;

-F = the near field average dilution factor for C. during any liquid effluent relehse. Defined as the ratih of the average undiluted liquid vaste flow during release to the average flow from the site discharge structure to UNRESTRICTED AREAS; Cg = the average concentration of . radionuc.. ide , i, in undiluted liquid effluent during time period, t, from any liquid releases, in pCi/ml; Ag '= the site related ingestion dose commitment factor to the total

' body or critical organ of an adult for each identified principal gamma and beta emitter listed in Table 4.0, in mrem-al per hr-pCi; Ag = 1.14E+05 (730/D ,+ 213Fg/Da) DFg where: -

! }i 1.14Et05 = II+06 pCi/pci x 12+03 ml/kg + 8760 hr/yr, units conversion factor;

, , , . , H.P.-CDCM-4 Page 3 of 5 05-03-84 730 = adult water consumption, kg/yr from FnEG-0133; Dy = dilution factor from the near field area within one quarter mile of the release point to the potable water intake for the adult water consumption. Dw includes the dilution contributions

" from the North Anna Dam to Doswell (0.73), the Waste Heat Treatment Facility (0.66), and Lake Anna (0.63). The potable water mixing ratio was calculated as 1/0.66 X 0.63 X 0.73 = 3.29.

EF g= the bioaccumulation factor for nuclide, i, in fish, pCi/kg '

per pCi/1, from Table A-1 Regulatory Guide 1.109; Da = dilution factor for the fish pathway, calculated as 1/0.66 = 1.52.

The North Anna UFSAR dilution factor for the Waste Treatment Facility is 0.66.

DFg = the critical organ dose conversion factor for nuclide, i, for adults, in mrem /pci, from Table E-11 of Regulatory Guide 1.109, Rev. 1.

3. EXAMPLE 3.1 Compilation of data from release records .for a 31 day period g provides the following information:

Total Volume of Undiluted Liquid Effluent Released = 2.00E+10 ml

, Total Volume of Dilution Water Used During Period = 1.59E+14 al Average Concentration of Radi'onuclides in Undiluted Liquid Effluent Cs-134 = 6.23E-08 pCi/ml Cs-137 = 2.13E-07 pCi/ml I-131 = , 5.17E-07 pCi/ml

1 Co-58 '= 1.53E-07 pCi/ml Co-60 = 7.27E-07 pCi/ml H-3 = 4.62E-03 pCi/ml 3.2 31 Day Total Body Calculation:

D=tFIC A g g

, i Obtain total body Agvalues from Table 4.0 ,

t = 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />.

' mrem-ml mrem A

Nuclide i (pCi/ml) X i uCi-br = .hr Cs-134 6.23E-08 X 5.87E-05 = 3.66E-02 ;

Cs-137 2.13E-07 X 3.46Evo5 = 7.37E-02 j

'% I-131 5.17E-07 X 3.29E-+2 = 1.70E-04 i

,/_ :Co-58 1.53E-07 X 3.01E+02 = '4.61E-05 j Co'-60 7.27E-07 X S.51E*02 = 6.19E-04 E-3 4.62E-03 I 6.59E+00 = 3.04E .* IC A,* =. 1.42E-01 g :l' i

. H.P.-0DC.M-4

~

Page 5 of 5 05-03-84 s")

, l TABLE 4.0 LIQUID INGESTION PATHWAY DOSE FACTCR FOR NORTH ANNA POW.R STATION UNIT NOS. 1 AND 2 Total Body A g Critical Organx A g Radionuclide mrem /hr mrem /hr uCi/ml uCi/ml H-3 2.80E+00 2.80E+00 Na-24 3.11E+02 3.11Et02 Cr-51 9.05E-01 -

Mn-54 5.71E+02 2.99E+03 Fe-55 8.10E+01 3.47E+02 Fe-59 7.15E+02 1.86E+03 Co-58 1.74E+02 7.75E+01 Co-60 4.91E+02 2.23Et02 Zn-65 2.21E+04 4.89Ev04 Rb-86 3.11E+04 6.70Et04 Sr-87 6.41E+02 -

x, 'Sr-90 1.35E+05 -

Y-91 2.44E-01 .-

J Zr-95 2.01E-01 2.97E-01 Zr-97 4.73E-03 1.03E-02 Nb-95 8.79E+01 1.64E+02 Mo-99 3.37E+01 1.77E+02 Ru-103 3.27E+00 -

Ru-106 1.43E+01 -

Ag-110m 2.54E+00 4.28E+00 Sb-124 _

2.98E+01 1. 42E+00 Sb-125 1.14E+01 5.37E-01 Te-125m 2.35E+02 6.36E+02

~

Te-127m 5.41E+02 1.59E+03 Te-129m 1.19E+03 2.81E+03 Te-131m 4.62E+02 5.54E+02 Te-132 1.00E+03 1.07E+03 I-131 1.67E+02 2.91E+02 I-232 9.29Ee00 2.66E+01 I-133 3.68E+01 1.21E+02 I-134 5.04E-00 1.41E+Q1 I-135 2.09E+01 5.67E+01 Cs-134 3.84E+05 4.70E+05 Cs-136 5.87E+04 8.16E-04 Cs-137 2.27E-05 3.46E+05 Cs-138 1.71E+02 '3.E46-02 h 3a-140 4.20E+01 3.06E-01 La-140 2.15E-02 S.15E-02 Ce-141 1.93E-02 1.70E-01

~~'

Ce-143 3.63E-03 3.2SE-01 Ce-144 -

7.04Et01 5.48E+00 No-239 2.65E-03 4.80E-03

? Critical Organ is definec in EP-CDCM-A2, Page 2 of 2.

o.... .

Excerpts from HP-0DCM-13 with revisions

g -A a y a . . e

- E.P.-0DCM-13 Page 8 of 10 05-03-84 Exposure Pathway Sample and/or Samole Location (Station) Number Aquatic:

Sediment 8,9,11 Previously Identified ,

Ingection:

a. Milk 12 milk sample from the farm of

~ Mr. R. C. Goodwin, approx.

0.5 miles East on Rt. 612

^ off Rt. 522 13 milk sample from the farm of 4 Mr. Terrel, approx. 0.5 miles West on Rt. 618 past.-

Fredericks Hall, on gravel road across railroad tracks

b. Fish 8,9 Previously Identified

c. Food Products 21,23 Previously Identified 14 Broadleaf vegetation sample obtained at the end of Rt.

713 near Lake Anna Marina, approx. 1.7 miles EAST from the intersection of Rt. 713 and Rt. 601.

15 Broadleaf vegetation sample obtained at the end of Rt.

614, approximately 1.5 miles EAST from the intersection of Rt. 614 and Rt. 601.

16 I

Control broadleaf vegetation sample obtained near the

intersection of. Rt. ~522 and Rt. 629, approximately 10.2 miles NORTH fros ' the inter-section of Rt. 522 and 208.

l l

ll.P.-0DCH-13 Page 9'of 10 -r 05-03-84 *=

.e 2.0 ' SAMPLING STATION IDENTIFICATION AND RELATIVE POSITON TO EFFI.UENT RELEASE POINT' STATION DISTANCE DEGREES AND NUHBER LOCATION HILES COMPASS DIRECTION REMARKS 1 On Site 0.2 42 NE 3 Mineral 7.1 243 WSW 4 Warcs Crossroads 5.1 287 WNW 5 Good llope Church 4.2 ,

20 NNE 6 Levy 4.7 115 ESE i 7 Bumpass 7.3 167 SSE 8 Discharge Lagoons 1.1 148 SSE 9 Lake Anna, upstream 2.2 320 NW Control 11 North Anna River, downstream 5.8 128 SSE 12 llolladay Dairy 8.3 310 NW-13 Fredericks llall 5.6 205 SSW 14 Route 713 1.2 43 NNE 15 Route 614 1.7 133 ESE 16 Route 629/522 12.6 314 NW Control 21 Route 685 1.0 301 WNW .

22 Route 700 1.0 242 WSW 23 Aspen Ililla 0.9 158 SSE I

p-NO4TGoM 64p 4 j- 74 _onn VIRGINIA ELECTHIC AND PowEn COMPANY RIcunown,VIROINIA 202G1 7 n AJJ,: 19g w.L.srnwaar 34 SEfugust Vacs Paassomwr Nuctuan Oramattown Mr. James P. O'Reilly Serial No. 521 Regional Administrator N0/JHL:acu U. S. Nuclear Regulatory Commission Docket Nos Region II -339 101 Marietta Street, Suite 2900 License Nos. NPF-4 Atlanta, Georgia 30323 NPF-7

Dear Mr. O'Reilly:

Enclosed is the Radioactive Effluent Release Report for North Anna Power Station for the period January 1, 1984 to June 30, 1984.

ry truly yours, W.'L.' Stewart Enclosure (2 copies) cc: Mr. R. C. DeYoung, Director Office of Inspection and Enforcement Attn: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. M. W. Branch N C Resident Inspector North Anna Power Station ZEag 'l TV-/>

ML20113C217

Text

Dear Mr. O'Reilly:

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