ML20092M896

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Radioactive Effluent Release Rept for North Anna Power Station, for Jul-Dec 1991
ML20092M896
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 12/31/1991
From: Stafford A
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20092M848 List:
References
NUDOCS 9202280219
Download: ML20092M896 (26)
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Text

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RADIOACTIVE EFFLUENT RELEASE REPORT NORTil ANNA POWER STATION

t. J ULY 01, 1991 TO DECEMBER 31, 1991)

I PREPARED BY h k/FlV

,mz-S ervisor Radiological Analysis REVIEWED BY:_

Supervisor Technical Services APPROVED BY: _,

/C _

Superintentient Radiological Protection 9202280219 DR 920221 ADOCK 05000338 PDR

I .

F0RWARD This report is submitted as required by Appendix A to operating License i

Nos. NPP-4 and NPF-7, Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nes.

50-338, 50-339, Section 6.9.1.9.

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RADIOACTIVE EFFLUENT RELEASE REPORT l

POR TiiE

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. NORTil ANNA POWER STATION JULY 01, 1991 TO DECEMBER 31, 1991 J

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I NDEX l

_Section No. Subject Page 1 PURPOSE AND SCOPE........................ 1 -2 2 DISCUSSION............................... 2-4 3 SUPPnEMENTAL INFORMATION................. 5 Attachment 1 -

Effluent Release Data.................... 6 httachmert 2 -

Annual and Quarterly Doses............... 7 Attachment 3 -

Revisions to Offsite Dose Calculation Manual (OD'M)............................

C 8

~ Attachment 4 -

Major changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems.................................. 9 Attachment 5 -

Inope ability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation.......................... 10 Attachment 6 -

Unplanned Releases....................... 11 Attachment 7 -

Lower Limits of Detection (LLD) for Effluent Sample Analysis................. 12 - 13

Page 1 1.0 PURPOSE AND SCOPE The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined 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", Revision 1, June 1974, with data summarized on a quarterly basis following the format-of Tabler 1, 2 and 3 of Appendix B thereof. The report submitted within 60 days after January 1 of each year includes an assessment of radiation doses to the maxinum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. *he report also includes a list of unplanned releases during the reporting period, in Attachment 6.

As required by Technical Specification 6.15, changes to the Offsite Dose Calculation. Manual (CDCM) for the time period covered by this report are included in Attachment 3.

Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.6.2. Information to support the reaso.(s) for the change (s) and a summary of the 10 CPR 50.59 evaluation are included. In lieu of reporting major change in this report, major changes to the radioactive waste treatment systems may be submitted a part of the annual FSAR update.

Page 3 1.0: -PURPOSE AND SCOPE - (cont.)

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this report, in Attachment 5.

2.0 DISCUSSION The basis for the calculation of the percent of technical specification for the critical organ in Table 1A of Attachment 1 is the ODCM. The ODCM, Section 6.3.1 requires that the dose rate for Iodine-131, for Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem /yr to the critical organ at or beyond the site boundary. The critical organ is the child's thyroid; inhalation pathway.

The basis for the calculation of percent of technical specification

-for the total - body and skin in Table 1A of Attachmer.t- 1 is the ODCM. The ODCM, Section 6.3.1, requires that the dose rate for l noble gases to areas at or beyond site boundary - shall be less than or equal to 500 mrem /yr to the total body and less than or

equal'to 3000 mrem /yr to the skin.

l l The basis for the calculation of the percent of technical i

! specification in Table 2A of Attachment 1 is the ODCM. The ODCM, Section 6.2.1, states that the concentrations of radioactive

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

Page 3 i

2.0 DISCUSSION (cont.)

material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CPR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. I'o r dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 microcuries/ml.

Percent of technical . ;ification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were calculated accordir.g to the methodology presented in the ODCM.

The beta and gamma air doses due to nou ; gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases of airborne Iodine 131, Tritiuni and all radionuclides in particulate form with halflives greater than 8 days, is defined as an infant, exposed through the grass-cow milk pathway, with the critical organ being the thyroid. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestriced areas is defined as an c.d u l t , exposed by either the invertebrate or fish pathway, with the critical organ being the liver. The total body dose was also determined for this individual.

Presented in Attachment 6 is a list of unplanned gaseous and liquid releases exceeding the ODCM limits of sections 6.3.1 and 6.2.1 respectively.

Page 4 2.0 DISCUSSION (cont.)

The typical Lower Limit of Detection (LLD) capabilities of the

< radioactive offluent analysis instrumentation are presented in Attr.chment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volume and naximum delay time prior to analysis). Actual LLD ve'ues may be lower. If a ra oisotope is not detected when analyzing effluent samples, the the activity of that radioisotope will be reported as Not _

Detectable (N/D) on Attachment 1 of this report. On Attachment 1, an entry of "N/A". not applicable, indicates that no analysis is performed for that isotope. When used in conjunction with totals, such an entry indicates that all radioisotopes for that particular quarter and release mode are less than LLD.

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-._____a_ _ _ _ _ _ _ __ _ _ _ _ a _a _ _ , _ , _ , , _ , _ _ _ _ _ _ _ _ _ _ ________ ___ _ __

Page 5 3.0 SUPPLP. MENTAL INFORMATION As required by the ODCM, evaluation of the Land Use Census -is  !

to be made for identi f yinc, the new location (s) for the environmental monitoring program pursuant to the ODCM, Section 6.5.2 requirements. Evaluation of the Land Use Census conducced in 1991 identified one new sample location for the Environmental )

Monitoring Program. The location of the broad leaf vegetation I

sampling station number 15 was changed, due to higher calculated-deposition source strength (D/Q) values at the new sample location.

The ' Environmental Monitoring Program procedure, ll P - 3 0 S l . 1 0 , was revised to include the change in sample location. No changes to the ODCM airborne effluent dose factors were necessary.

As required by the ODCM, the identification of the causes of-the unavailability of milk or leafy vegetation samples, required by the ODCM, Section 6.5 and Attachment 21, and the identification of the new location (s) for obtaining replacement samples are listed. Milk samples, as required by the ODCM, Section 6.5 and Attachment 21, were available during the time period covered by this report. The leafy vegetation samples for vegetation sta t.i ons 14, 15, 16, 21 and 23 were not collected for the months of November i

and December 1991 due to seasonal unavailability. All other samples were obtained . and analyzed as required during the time period covered by this report, i

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ATTACilMENT 1 EFFLUENT RELEASE DATA (07/91 -

12/91)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21, Appendix B.

TABLE lA NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR 1991 3rd 4th ESTIMATED TOTAL-UNITS QUARTER QUARTER PERCENT ERROR (%)

. A. Fission and Activation Gases:

, 1. Total Release. Curies 6.66E+2 5.15E+2 1.80E+1

2. Average Release Rate'for Period. uCi/sec 8.38E+1 6.48E+1
B. Iodines
1. Total Iodine-131 Release. Curies 6.17E-4 1.16E-3 2.80E+1
2. Average Release Rate for Period. pCi/sec 7.76E-5 1.46E-4 i

C. Particulates (T > 8 days):

i

1. Total Particulate (T > 8 days) Release. Curies 4.91E-5 1.58E-5 2.80E+1

)

2. Average Release Rate for Period. pCi/sec 6.18E-6 1.99E-6

{

3. Gross Alpha Radioactivity Release Curies N/D N/D l

) D. Tritium:

1 4 1. Total Release. Curies 5.99E+0 9.90E+0 3.10E+1 f 2. Average Release Rate for Period. pCi/sec 7.54E-1 1.25E+0 E. Percentage of Technicial Specification Limits:

}

1. Total Body Dose Rate.  % 3.21E-2 2.50E-2 j 2. Skin Dose Rate.  % 1.19E-2 8.02E-3 4 3. Critical Organ Dose Rate.  % 1.27E-3 2.30E-3 N/D is Not Detectable & N/A is Not Applicable i

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TABLE- IB

. NORTil ANNA POWER ' STATION i SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

! MIXED MODE GASEOUS EFFLUENT RELEASES FOR 1991 Page 1=of 2 l

CONTINUOUS MODE DATCII MODE

, 3rd 4th 3rd '4th i NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER i Fission and Activation Gasen: ,

I. Krypton - 85 Ci N/D j

N/D 1.62E-1 4.26E+0 Krypton - 65m Ci N/D N/D 3.05E-2

} Krypton - 87 N/D I

Ci N/D 6.87E-2 N/D N/D Krypton - 88 C1 N/D 9.97E-2 2.70E-2 Xenon - 131m N/D j Ci 5.55E-1 4.71E-1 1.16E+0 2.17E+0 l Xenon - 133 Ci 2.90E+2 1.82E+2 1.05E+2 2.07E+2 j Xenon - 133m Ci 6.87E-1 3.38E-1 8.20E-1 1.43E+0 Xenon - 135 Ci 1.68E+0 1.54E+0 6.08E-1 2.46E-1 Xenon - 135m Ci N/D N/D N/D Xenon - 138 N/D Ci N/D N/D N/D N/D 4 Other (Specify)

{ Argon - 41 Ci 9.50E-3 2.02E+0 1.33E-2 N/D

[

l Total for Period Ci 2.93E+2 1.87E+2 1.0HE+2 2.15E+2 i

. Iodines:

j Iodine - 130 Ci N/D N/D N/A N/A j Iodine - 131 Ci 1.33E-5 2.~5E-5 N/A Iodine - 132 N/A i Ci N/D N, 0 N/A N/A l Iodine - 133 Ci 2.61E-6 5.99E-6 N/A Iodine - 134 N/A j Ci N/D N/D N/A N/A j Iodine - 135 Ci N/D N/D N/A T A Total for Period Ci 1.59E-5 2.65E-5 N/A N/A j Particulates:

Manganese - 54 Ci N/D N/D i

N/A N/A i

Iron - 55 Ci 4.45E-7 2.92E-7 N/7 N/A i CobaIt - 58 Ci N/D N/D N/A N/A

{' Iron - 59 Ci N/D N/D N/A N/A Cobalt - 60 Ci 1.61E-6 8.87E-7 N/A N/A l Zine - 65 Ci N/D N/D N/A N/A l Strontium - 89 Ci N/D N/D N/A N/A

! Strontium - 90 Ci N/D N/D N/A N/A l Silver - 110m Ci N/D N/D N/A N/A N/D is Not Detectable & N/A is Not Applicable

TABLE IB NORTil ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR 1991 Page 2.of 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER- _

Particulates (cont.):

Cesium - 134 Ci 5.23E-7 2.77E-7 N/A N/A Cesium - 136 Ci N/D N/D N/A N/A Cesium - 137 Ci 3.13E-6 1.59E-6 N/A N/A Barium - 140 Ci N/D N/D N/A N/A' Cerium - 141 Ci N/D N/D N/A N/A Cerium - 144 Ci N/D N/D N/A N/A Other (Specify)

Sodium - 24 (T < 8 days) Ci N/D N/D N/A N/A T_hidium - 88 tT < 8 uays) Ci N/D N/D N/A N/A

~ oidium - 89 (TS < 8 days) Ci N/D N/D N/A N/A Molybdenum - 99 (T < 8 days) Ci N/D N/D N/A N/A Technetium - 99m (T < 8 days) Ci N/D N/D N/A N/A Antimony - 122 (T < 8 days) Ci N/D N/D N/A N/A Antimony - 124 Ci 1.09E-8 N/D 'N/A N/A Tellurium - 131m (T\ < 8 days) Ci N/D N/D . '/ A N/A Cesium - 138 (T < 8 days) Ci N/D N/D N/A N/A Lanthanum - 140 Ci N/D N/D N/A N/A Total for Period (T > 8 days) Ci 5.72E_-b 3.04E-6 N/A N/A Total for Period (T < 8 days) Ci PA N/A N/A N/A Total for Period Ci 5.72E-6 3.04E-6 N/A N/A GROSS ALPIIA: Ci N/D N/D N/A N/A TRITIUM: Ci 3.65E-1 3.39E-1 1.14E-3 1.07E-3 i

l l N/D is Not Detectable & N/A is Not Applicable i

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1 TABLE 1C NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1991 Page 1 of 2

! CONTINUOUS MODE BATCH MODE'

3rd 4th 3rd 4th ,

NUCLIDES RELEASED ' UNITS QUARTER QUARTER QUARTER QUARTER i Fission and Activation Gases: '

1 Krypton - 85 Ci N/D N/D N/D N/D

, Krypton - 85m Ci 3.46E-2 9.85E-2 N/D 5.89E-5 -

Krypton - 87 Ci 3.18E-2 1.14E-1 N/D 7.13E-5 Krypton - 88 Ci 6.7GE-2 1.93E-1 N/D N/D (

f Xenon - 131m Ci N/D 1.70E-2 N/D N/D t 1

Xenon - 133 Ci 2.16E+2 9.42E+1 2.82E+1 7.43E+0 i Xenon - 133m Ci N/D N/D 3.45E-1 N/D i i

Xenon - 135 Ci 1.90E+1 5.44E+0 4.38E-2 4.11E-2 Xenon - 135m Ci 2.38E-1 4.02E-1 4.26E N/D l

, Xenon - 138 Ci 5.10E-2 1.13E-1 N/D N/D I Other (Specify) i j Argon - 41 Ci 1.45E+0 4.89E+0 N/D 7.65E-5 l 4

l Total for Period Ci 2.37E+2 1.05E+2 2.86E+1 7.47E+0 i i Iodines: i

! lodine - 130 Ci N/D N/D 6/D N/D  :

l Iodine - 131 Ci 5.45E-4 1.08E-3 5.97E-5 5.78E-5

Iodine - 132 Ci N/D N/D 1.66E-5 2.94E-1 [

! Iodine - 133 Ci 4.17E-4 1.19E-3 5.69E-5 2.91E-6

! Iodine - 134 Ci N/D N/D 6.64E-6 1.71E-7 l Iodine - 135 Ci N/D N/D 3.92E-5 8.05E-7 l Total for Period Ci 9.62E-4 2.28E-3 1.79E-4 6 20E-5

^ '

Particulates:

Manganese - 54 Ci N/D N/D N/D 4.38E-10 ,

Iron - 55 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D 1.07E-5 N/D 8.03E-10 Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 N/D N/D 9.64E-7 N/D Ci Zine - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D

, Silver - Il0m Ci N/D N/D N/D N/D l Cesium - 134 Ci N/D N/D 1.26E 5 1.49E-8

Cesium - 136 Ci N/D N/D 8.94E-10 3.21E-9 i N/D is Not Detectable & N/A is Not Applicable N

} TABLE IC i NORTII ANNA POWER ' STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

{ GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1991 Page 2 of 2 1

4 CONTINUOUS MODE BATCli MODE 3rd 4th 3rd ~4th NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates (cont.):

l Cesium - 137 Ci 4.79E-6 1.94E-6 2.50E-5 2.15E-8 i Barium - 140 Ci N/D N/D N/D 'N/D Cerium - 141 Ci N/D N/D N/D N/D l Cerium - 144 Ci N/D N/D N/D N/D l Other (Specify)

Sodium - 24 (T < 8 days) Ci N/D N/D 1.96E-5 5.51E-9

Bromine - 84 (T < 8 days) Ci N/D N/D N/D N/D i Rubidium - 88 (Th < 8 days) Ci N/D N/D N/D 1.43E-7

} Rubidium - 89 (T < 8 days) Ci N/D N/D N/D N/D j Molybdenum .99 (Th < 8 days) Ci N/D N/D N/D N/D 4

Technetium - 99m (T < 8 days) Ci N/D N/D N/D N/D Ruthenium - 106 Ci N/D N/D N/D 9.52E-9 i Antimony - 122 (T < 8 days) Ci N/D N/D 4.44E-10 N/D Tellurium - 131m (T .< 8 dayst Ci N/D N/D N/D N/D .

Cesium - 138 (T < 8 days) Ci- N/D N/D N/D 2.49E-7 Cerium - 143 (T < 8 days) Ci N/D N/D 2.36E-6 N/D.

Lanthanum - 140 Ci N/D N/D N/D N/D i Total for Period (T > 8 days) Ci 4.79U-6 1.27E-5 3.86E-5 5.04E-8 Total for Period (T < 8 days) Ci N/A N/A 2.20E-5 3.97E-7 i

Total for Period Ci 4.79E-6 1.27E-5 6.06E-5 4.48E-7 L

GROSS ALPIIA: Ci N/D N/D N/D N/D 4

TRITIUM: Ci 5.48E+0 S.52E+0 1.34E-1 4.02E-2 i

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N/D is Not Detectable & N/A is Not Applicable i

TABLE 2A' NORTH ' ANNA POWER STATION

SEMI-ANNUAL RADIOACTIVE EPPLUENT RELEASE REPORT LIQUID EFPLUENTS-SUMMATION OF ALL RELEASES FOR (1991) 3rd 4th ESTIMATED TOTAL UNITS QUARTER QUARTER - PERCENT ERROR (%)

A. Pission and Activation Products:

1. Total release(not' including tritium, noble' gases, and gross alpha). Curies 8.51E-2 7.38E-2 2.00E+1
2. Average diluted concentration Curing q che period. pCi/ml 9.95E-ll 1.07E-10 i
3. Percent of applicable limit (T.S.).  % 5.78E-3 1.20E-2 i

B. Tritium:

l

1. Total release activity. Curies 3.49E+2 2.65E+2 2.00E+1
2. Average diluted concentration during 3

the period. uCi/ml 4.08E-7 3.82E-7 4

l

3. Percent of applicable limit (T.S.).  % 1.36E-2 1.27E-2

! C. Dissolved and Entrained Gases:

1

1. Total release activity. Curies 7.90E-1 1.45E+0 2.00E+1 l

! 2. Average diluted concentration during the period. uCi/ml 9.23E-10 2.09E-9 j 3. Percent of applicable limit (T.S.).  % 4.62E-4 1.05E-3

, D. Gross Alpha Radioactivity:

1. Total release activity. Curies N/D N/D 2.00E+1 i

E. Volume of waste released: (prior to 3 dilution). Liters 8.25E+7 8.44E+7 3.00E+0 P. Volume of dilution water used during period. Liters' 8.55E+11 6.93E+11 3.00E*0

, N/D is Not Detectable & N/A is Not Applicable i

_ . . _ _ _ ________.___________..__.______.m _ - - _ . _

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TABLE 2B NORTH ANNA POWER. STATION

, SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR 1991 Page 1 of 2 I

j

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CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th NUCLIDES RELEASED' UNITS QUARTER QUARTER QUARTER QUARTER Fission and Activation Products:

i j Manganese - 54 Ci 5.46E-4 7.04E-5 N/D N/D

] Iron - 55 Ci N/D N/D N/D N/D I Cobalt - 58 Ci 6.27E-3 8.00E-3 N/D N/D

, Cobalt - 60 Ci 2.94E-2 1.50E-2 N/D' N/D Zine - 65 Ci N/D N/D N/D N/D l

Strontium - 89 Ci N/D N/D N/D N/D

Strontium - 90 Ci N/D N/D N/D N/D l Silver - llGm Ci 1.63E-2 6.57E-3 N/D N/D l Iodine - 131 Ci 4 . 3E-3 1.96E-2 1.67E-3 N/D l Iodine - 132 Ci 7.86E-5 N/D N/D N/D l Iodine - 133 Ci 9.06E-3 1.70E-2 3.10E-4 N/D

{ Iodine - 134 Ci N/D N/D N/D N/D l Iodine - 135 Ci N/D N/D N/D N/D

Cesium - 134 Ci 1.46E-3 7.35E-4 2.78E-4 N/D j Cesium - 136 Ci 2.30E-4 N/D 7.75E-5 N/D j Cesium - 137 Ci 4.01E-3 2.08E-3 2.68E-4 1.64E-5 l Barium - 140 Ci 9.60E-5 N/D N/D N/D-i Cerium - 141 N/D N/D Ci N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (specify)

{ Sodium - 24 (T < 8 days) Ci 1.46E-4 N/D N/D N/D Chromium - 51 Ci N/D N/D N/D N/D

! Cobalt - 57' Ci N/D N/D N/D N/D

! Iron - 59 Ci N/D N/D N/D N/D j Rubidium - 88 (T < 8 days) Ci N/D N/D F/D N/D j Strontium 85 Ci 1.60E-4 N/D N/D N/D j Zirconium -:95 Ci N/D N/D N/D N/D

! Niobium - 95 (T < 8 days) Ci 2.34E-3 8.85E-4 N/D N/D Molybdenum - 99 (T <=8' days) Ci N/D N/D N/D N/D

, Technetium - 99m (T < 8 days) Ci N/D N/D N/D N/D l Cadmium - 109 Ci N/D N/D N/D N/D j Antimony - 122 (Th < 8 days) Ci N/D N/D 1.87E-5 N/D l Antimony - 124 Ci 3.19E-4 N/D N/D N/D i Antimony - 125 Ci 2.38E-3 3.58E-3 N/D N/D N/D is Not Detectable & N/A is Not' Applicable a

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_ d e N_

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a a N n d d D o d e E i 8 8 e l S t n b A a < < i a E v a t L i \ d r d c E t T T 0 o t ) o e R c ( ( 4 i n y i t A 1 r E f m r e 8 9 e m m m i 5 5 e D S d 3 3 - P & 1 3 3 5 5 c 8 8 P A E n 1 1 3 3 3 3 3 e 1 I I t D a m r d 1 1 1 1 1 p 4 - - r P o I - - u o e s o L N L n n f v - - - - - ( - n n f M A C o m m a l o o U s U i u u h l o n n n n n r n t t l I S i N s

_ i i t a s o o o o o e o p p a T S s s r n t s n n n n n h g y y t I O D i e a a o i e e e e e t r r r o R R /

F C B L T D X X X X X O A K K T T G N

T TABLE 3 NORTil ANNA POWER- STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADI ATED FUEL SillPMENTS FOR 07-01-91 TIIROUGil 12-31-91 Page 1 of 2 A. SOLID WASTE SilIPPED OFFSITE FOR BURI AL OR DISPOSAL (NOT-IRRADIATED FUEL) 6-MON'Eli ESTIMATED TOTAL

1. Type of Waste UNIT PERIOD PERCENT ERROR

(%)

a. Spent resins, filter m' 4,79E+1 2.50E+1 sludges, ovaporator Ci 1.40E+2 2.50E+1 bottoms, etc.
b. Dry compressible waste, m' l.09E+2* 2.50E+1 contaminated equipment, Ci 9.84E-2 2.50E+1 etc.
c. Irradiated components, m' O.00E+0 0.00E+0 control rods, etc. Ci 0.00E+0 0.00E+0
d. Other (describe) m' O.00E+0 0.00E+0 ri 0.00E+0 0.00E+0
2. Estimate of major nuclide composition (by type of waste)
a. C-14  % 1.78E+0 2.50E+1 Mn-54  % 1.34E+0 2.50E+1 Fe-55  % 1.10E+1 2.50E+1 Co-58  % 1.60E+0 2.50E+1 Co-60  % 3.50E+1 2.50E+1 Ni-63  % 3.85E+1 2.50E+1 Cs-134  % 3.14E+0 2.50E+1 Cs-137  % 6.99E+0 2.50E+1
b. Fe-55  % 4.07E+1 2.50E+1 Co-58  % 9.94E+0 2.50E+1 Co-60  % 2.37E+1 2.50E+1 Ni-63  % 9.09E+0 2.50E+1 Sb-125  % 1.01E+0 2.50E+1 Zr-95  % 2.81E+0 2.50E41 Nb-95  % 5.83E+0 2.50E+1 Cs-134  % 1.27E+0 2.50E+1 Cs-137  % 3.39E+0 2.50E+1

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

TABLE 3 NORTil ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EPPLUENT HELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SilIPMENTS FOR 07-01-91 TliROUGli 12-31-91 Page 2 of 2

2. Estimate of major 6-MONTil ESTIMATED TOTAL nuclide composition UNIT PERIOD PERCENT ERROR (by type of waste) (%)

(cont.)

c. NONE

~

d. NONE
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 7 Truck Barnwell,S.C.

3 Truck Oak Ridge,T.N.

(SEG)

D. IRRADIATED FUEL SIIIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A P, A 3 shipments of Dry Active Waste were shipped from North Anna to a licensed waste processor for volume reduction. Therefore, the volume as listed for this type is not representative of the actual volume buried. The total volume buried for this reporting _ period was 31.8 m'.

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

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

Page 7 t

ATTACl! MENT 2 ANNUAL AND QUARTERI.Y DOSES i

An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway is made pursuant '

to the ODCM, Section 6.6.2 t equirements.  ;

Liquid Effluents: ,

1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 1.24E-l 9.53E-2 1.91E-1 1.17E-1 5.27E-1 Critical Organ ,

Dose (mrem) 1.56E-1 1.00E-1 2.33E-1 1.37E-1 6.26E-1 Gaceous Effluents:

1st 2nd 3rd 4th- Annual Quarter Quarter Quarter Quarter Total

-Noble Gas

-Gamma Dose (mrad) 1.03E-2 5.89E-2 4.65E-2 3.51E-2 1.51E-1 Noble Gas Beta Dose (mrad) 2.94E-2 1.43E-1 1.08E-1 5.76E-2 3.38E-1 r

Critical Organ l- Dose for 1-131, l H-3, Particulates 1.94E-2 1.75E-2 2.84E-2 5.36E-2 1.19E l with Th > 8-days l - ( mrem )-

L l

Page 8 ATTACl! MENT 3 REVISIONS TO OPFSITH DOSE CALCULATION MANUAL (ODCM)

(07]91 -

12/91)

As required by Technical Specification 6.15, revisions to the ODCM, effective for the time period covered by this report, are synopsized in this attachment.

Revision 1 to the Virginia Power offsite Dose Calculation Manual was effective July 01, 1991.

Revision 2 to the Virginia Power Offsite Dose Calculation Manual was effective September 01, 1991.

A copy of Revision 2 of the Offsite Dose Calculaticn M r.ual is attached.

Changes made effective with Revision 1 and Revision 2 are indicated by marking the borders of the revised areas with the offective date of the change. All changes marked "Rev. 1" were effective July 01, 1991. All changes marked "Rev. 2" were effective September 01, 1991.

Additionally, changes were made in the presentation of text. Effective with Revision 1, formulas or equations within the ODCM were assigned a-number. Future references to the equation are made via this equation number. Also effective with Revision 1, words or phrases that were capitalized in Revision 0, if they were defined by Technical Specifications, were un-capitalized.

Punctuation, spelling and other grammatical errors were corrected in Revision 1 and Revision 2. These minor changes are not specifically identified, as they do not affect the text content. Page numbers were changed as required, to reflect the relocation of text by Revision 1 and Revision 2.

Page 9 ATTACllMENT 4 MAJOR CllANGES TO RADIOACTIVE I.IQUI D , GASI:OUS , AND SOLID WASTE TREATMENT SYSTEMS (07/91 -

12/91)

As required by the ODCM, Section 6.6.2, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting _

information as to the reason (s) for the change (s) and a summary of the 10 CFR 50.59 evaluation are included, as applicable.

No major changes to the radioactive liquid, gaseous and solid waste treatment systems were made for the time period covered by this report.

Page 10 ATTACllMENT 5 I NOPERAB11,I TY OF RADIOACTIVE LIQUID AND GASEOUS EPFLUENT MONITORING INSTRUMENTATION (07/91 -

12/91),

As required by the ODCM, Sections 6.2.2.b 2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment. __

No extended periods of inoperability occurred with any of the Liquid or Gaseous Effluent Monitoring Instrumentaiton for the time period covered by this report.

Page 11 c

ATTACilMENT 6 UNPLANNED RELEASES (07/91 -

12/91)

As required by the ODCM, Section 6.6.2, a list of unplanned releases, from the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.

No unplanned releases, as defined by the criteria presentou in ODCM, Section 6.6.2, occurred during the time period covered by this report.

. = .

Pago 13 ATTACRMENT 7 LOWER LIMITS OF DETECTION FOR F.FPLUENT SAMPLE ANALYSIS (07/91 -

12/91[_

Gaseous Effluents:

Required L.L.D. Typical L.L.D.

Radioisot. ope (pCi/ml) (pCi/ml)

_ Krypton - 87 1.00E-4 4.62E-8 -

4.25E-7 Krypton - 88 1.00E-4 4.36E-8 -

5.68E-7 Xenon - 133 1.00E-4 4.72E-8 -

4.208-7 Xenon -

133m 1.00E-4 1.64E-7 -

1.41E-6 Xenon - 135 1.00E-4 1.93E-8 -

1.67E-7 L

Xenon - 135m 1.00E-4 8 26E-8 -

6.72E-7 Xenon - 138 1.00E-4 2.31E-7 -

1.96E-6 Iodine - 131 1.002-12 5.92E 6.51E-14 Manganese - 54 1.00E-ll 3.98E 4.29E-14 Cobalt - 58 1.00E-11 3.34E-14 -- 4.78E-14 Iron - 59 1.00E-ll 9.09E 9.96E-14 Cobalt - 60 1.00E-Il 6.75E-14 -

7.14E-14 Zinc - 65 1.00E-ll 1.08E -1.19E-13 .

Strontium - 89 1.00E ll 4.00E i.00E-11 Strontium - 90 1.00E-11 8.00E 8.00E-12 _

Molybdenum - 99 1.00E-ll 2.60E 3.692-13 Cesium - 134 1.00E-11 4.24E 4.77E-14 Cesium - 137 1.00E-ll 4.83E 5.43E-14

, Cerium - 141 1.00E-ll 3.94E 6.58E-14 Cerium - 144 1.00E-ll 1.92E 2.95E-13 Gross Alpha 1.00E-11 1.54E 5.06E-14 Tritium 1.00E-6 1.62E-7

Page 13 ATTACllMENT 7 I.OWER LIMITS OF DETECTION FOR EFFLUENT SAMPLH ANALYSIS (07/91 -

12/91)

(cont.)

Liquid Effluents:

~

Required I..L.D. Typical L.L.D.

Radtoinotope (pCi/ml) (pCi/ml)

Krypton - 87 1.00E-5 6.27E-8 -

7.09E-8 Krypton - 88 1.00E-5 7.83E-8 -

1.04E-7

__ Xenon - 133 1.00E-5 6.68E-8 -

8.26E-8 Xenon - 133m 1.00E-5 2.27E-7 -

2.53E-7 Xenon - 135 1.00E-5 2.71E-8 -

2.98E-8 Xenon - 135m 1.00E-5 1.07E-7 -

1.2]E-7 Xenon - 138 1.00E-5 3.22E-7 -

3.62E-7 Iodine - 131 1.00E-6 2.82E-8 -

2.90E-8 Manganese - 54 5.00E-7 2.31E-8 -

2.75E-8 Iron - 55 1.00E-6 3.00E-7 -

1.00E-6 Cobalt - 58 5.00E-7 2.17E-8 -

2.91E-8 Iron - 59 5.00E-7 4.96E-8 -

6.02E-P Cobalt - 60 5.00E-7 3.65E-8 -

4.29E-8 Zinc - 65 5.00E-7 5.99E-8 -

7.22E-8 Strontium - 89 5.uGE-8 2.00E-8 -

5.00E-8 Strontium - 90 5.00E-8 1.00E-8 -

2.00E-8 Molybdenum - 99 5.00E-7 1.86E-7 -

2.47E-7 Cesium - 134 5.00E-7 2.51E-8 -

3.12E-8 Cesium - 137 5.00E-7 3.29E-8 -

3.64E-8 Cerium - 141 5.00E-7 3.43E-8 -

5.02E-8 Cerium - 144 5.00E-7 '.68E-7 -

2.27E-7 Gross Alpha 1.00E-7 8.44E-9 -

2.92E-8 Tritium 1.00E-5 4.45E-6

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