ML20114B764

Radioactive Effluent Release Rept,North Anna Power Station, Jan-June 1992

ML20114B764
Person / Time
Site:	North Anna
Issue date:	06/30/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-568, NUDOCS 9208310214
Download: ML20114B764 (156)

Text

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Y!140lNI A N1.1:0T141(' ANil POWI:lt ('Ohll%NY H ICitMeaNip,VIHO!NIA UllV6i August 26, 1992 U.S. Nuclear Regulatory Commission Serial No.

92 568 Attention: Document Control Desk NAPS /JHL/EJW Washington, D. C. 20555 Docket Nos.

50 338 50 339 License Nos. NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY

(( ORTH ANNA POWi1R STATION UNIT NOS.1 AND 2 RADlQACTIVE EFFLUENT RELEASE REPOFIT-Pursuant to Techolcal Specification 6.9.1.9, enclosed is the Radioactive Effluent Release Report for North Anna Power Station Unit Nos.1 and 2 for the reporting period of January 1,1992 to June 30,1992. A replacement page for the report covering July 1,1990 to December 31,1990 is also attached. The original page incorrect'y reported ;he thulium 170 isotope as tellurium-170. This change also affects the half li' nd the totals for third quarter gaseous effluent release.

if you have any questions or require additionalinformation, please contact us.

Very truly yours,

/.

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dth W. L. Stewart Sen;or Vice President - Nuclear Attachments 310010 TE+lf 920B310214 920630 PDR ADOCK 05000338 R

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U. S. Nuclear Regulatory Commission Region ll 101 Marietta Sioet, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station I

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t I-ATTACHMENT ONE RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JANUARY 1,.1992 - JUNE 30,1992 l

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j NORTil AdNA POWER FTATION (JANUARY 01, 1992 TO JUNE 30, 1992)

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PREPAREDBL-V Supervisor Radiological Analysis l

REVIEWEDBY:

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APPROVEDBY:__

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I l'_0_JLM_A._lLD This report is submitted as required by Appendix A to Operating Licenso Nos. NPF +4 and NPF-7, Technical Specifications for North Anna Power Station, l

Units 1 and 2, Virginia Electric and Power Company, Cocket Nos. 50-338, 50-339, Section 6.9.1.9.

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RADIOACTIVE EFPLUENT RELEASE REPORT PCR THE NORTH ANNA POWER STATION JANUARY 01, 1992 TO JUNE 30, 1992 I_N D E K Section__Nei subject

_Engq__

1 PURPOSE AND SCOPE.....................

1 2

2 DISCUSSION............................

2 4

3 SUPPLEMENTAL INFORMATION..............-

5 Effluent Release Data.................

6 Annual and Quarterly Doses............

7 Revisions to Offsite Dose Calculation Manual (ODCM).........................

8 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems...............................

9 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation.......................

10 Unplanned Releases....................

11 Lower Limits of Detection (LLD) for l

Effluent Sample Analysis..............

12

- 13

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 Wasten and Releases of I

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 Tables 1, 2 and i of Appendix B thereof.

The report submitted within 60-days after January 1 of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year.

The report submitted within 60 days af ter July 1 of each year has the same sections except for the assessment of radiation doses.

The 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 Of fsite Dose Calculation Manual (ODCM) 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,fSection 6.6.2.

Information to support the reason (s) for the change (s) and a summary of the 10 CFR 50.59 evaluation are included.-

In lieu of reporting major changes in this report, major changes to the radioactive waste. treatment systems may be submitted as part of the annual:: FSAR update.

1 1

1.0 EUREODR_ 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.

2.0 DISCUSftLON 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 doce 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 cryan is the child's thyroid via the inhalation pathway.

The basis for the calculation of percent of technical specification for the total body and skin in Table 1A of Attachment 1 is the ODCH.

The ODCM, Section 6.3.1, requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mREU/yr to the total body and less than or equal to 3000 mRom/yr to the skin.

The basis for the calculation of the percent of technical specification 1

in Table 2A in Attachment 1 is the ODCM.

The ODCM, Section

6. 2.1, states that the concentrations of radioactive material released in 2

l

,,-____,_,__.______1

2.0 DISCUSSION (cont).

liquid offluente to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 11, Column 2 for radiunuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 microcurieE/ml.

l Percent of technical specification calculations are based -. the total gaseous or liquid effluents released for that respective quarter.

d

~

doses, as reported in Attachment 2,

were The annual and quarterly calculated according to the methodology presented in the ODCM.

The beta and gamma air doses due to noble gases released from the site were calculated at site boundary.

The maximum exposed member of the public f rom the releases of airborne Iodine-131, Tritium and all radionuclides in particulate form with half-lives greater than 8 days, is defined as an inf ant, 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 unrestricted areas is b

defined as an adult, 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.

3 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 9

respectively.

T

a.O DISQlSSION (cont).

The typical LoWar Limit of Detector (LLD) capabilities of the radioactive offluont analysis instrumentation are presented in These LLD values are based upon conservative conditions (i.e., minimum sample volume and maximum delay time prior to analysis).

Actual LLD values may be lower.

If a radioisotope is not detected when j

analyzing effluent samples, then 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 releaso mode are less than LLD.

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3.0 SUPFLEMENTAh _INFORMATION As required by the ODCM, evaluation of the Land Use Census is to be made for identifying the new location (s) for the environmental monitoring program pursuunt to the ODCM, Section 6,5.2 requirements.

Evaluation of the Land Use Consus conducted in 1991 identified one new sample location for the Environmental Monitoring Program.

The location of the broad leaf vegetation sampling station number 15 was changed, due to higher calculated deposition source strength (D/Q) values at the new cample location.

The Environmental Monitoring Program procedure, HP-3051.10, 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 station 14, 15, 16, 21 and 23 were not collected for the months of January, February and March 1992 due to seasonal unavailability.

All other samples were obtained and analyzed as required during the time period covered by this report.

5 l

3 ATTACIIMENT 1

EEfLUENT__RELEASH_ DATA OEd21 101D 2 This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guido 1.21, Appendix B.

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SEMI-ANKUAL RADIORCPIVE EFFIJ 2NT RELEASE REPORT

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MIXED MODE GASEOUS EFFLUENT REL.*c5E' FOR 01/92 - 06/92 Page 1 of 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd I

NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER i

i Fission and Activation Gases:

Krypton - 85 Ci N/D N/D 8.63E+0 1.39E+0 Krypton - 85m Ci 8.llE-3 N/D 2.10E-2 1.64E-3 Krypton - 87 Ci N/D N/D N/D N/D l

-Krypton - 98 Ci N/D N/D N/D N/D Xenon - 131m Ci 2.65E-1 N/D

9. ] OE+0 1.25E-1 b

Xenon - 133 Ci 1.28E+2 1.64E+1 4.47E+2 7.43E+0 Xenon - 133m Ci 7.78E-2 N/D 3.22E+0 7.70E-2 Xenon - 135 Ci 6.03E-1 3.82E-2 1.93E+0 7.91E-2 Xenon - 135m Ci N/D N/D 5.14E-1 N/D Xenon - 138 Ci N/D N/D N/D N/D l

Other (Specify) l Argon - 41 Ci N/D N/D 4.40E-3 N/D Total for Period Ci 1.29E+2 1.64E+1 4.70E+2 9.10E+0 1

I Iodines:

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Iodine - 130 Ci N/D N/D N/A N/A Iodine - 131 Ci 9.32E-6 1.78E-6 N/A N/A Iodine - 132 Ci N/D N/D N/A N/A

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j Iodine - 133 Ci 2.09E-6 1.98E-6 N/A N/A l

Iodine - 134 Ci N/D N/D N/A N/A l

Iodine - 135 Ci N/D N/D N/A N/A i

I Total for Period Ci 1.14E-5 3.76E-6 N/A N/A i

Particulates:

-Manganese - 54 Ci N/D N/D N/A N/A Iron - 55 Ci 8.70E-8 2.09E-7 N/A N/A l

1 Cobalt - 58 Ci 1.02E-8 N/D N/A N/A Iron - 59 Ci N/D N/D N/A N/A Cobalt - 60 Ci 4.02E-7 8.53E-7 N/A N/A Zine - 65 Ci N/D N/D N/A N/A Stror"ium - 89 Ci N/D

• /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 h

l N/D is Not Detectable 5

N/A is Not Applicable

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NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 01/92 - 06/92 Page 1 of 2 s

CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd NUCLIDES RELEASED UNITS QUARTER QUARTEI-QUARTER QUARTER 1

Fission and Activation Gases:

i Krypton - 85 Ci 2.59E-1 2.72E-1 1.38E+1 N/D Krypton - 85m Ci 2.52E-2 7.04E-2 3.87E-2 N/D Krypton - 87 Ci 2.10E-2 6.15E-2 N/D

_ _1/D Krypton - 38 Ci 5.11E-2 1.38E-1 7.12E-2 N/D Xenon - 131m Ci N/D N/D 2.48E-2 N/D Xenon - 133 Ci 2.40E+2 4.78E+G 1.28E+2 N/D Xenon - 133m Ci N/D 2.99E-2

-.!SE-1 N/D Xenon - 135 Ci 4.31E+0 2.33E+0 1.71E-1 6.60E-7 Xenon - 135m Ci 7.21E-2 1.32E-1 1.27E-2 8.53E-6 Xenon - 138 Ci 6.57E-3 N/D N/D N/D Other (Specify)

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Argon - 41 Ci 2.16E-1 4.26E+0 2.71E-1 N/D i

Total for Period Ci 2.45E+2 1.21E+1 1.43E+2 9.19E+0 1.

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~~ Iodines:

Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci 1.31E-2 2.00E-4 6.15E-8 9.34E-8 Iodine - 132 Ci N/D N/D 1.06E-6 7.llE-8 1

Iodine - 133 Ci 2.75E-4 2.06E-4 4.77E-8 1.91E-7 i

Iodine - 134 Ci N/D N/D 4.54E-9 2.49E-8 Iodine - 135 Ci N/D N/D 1.53E-8 1.72E-7 Total for Period Ci 1.34E-2 4.06E-4 1.19E-6 5.53E-7 1i t

Particulates:

s Manganese - 54 Ci N/D N/D N/D N/D Iron - 55 Ci 1.79E-5 N/D N/D N/D Cobalt - 58 Ci 4.70E-5 6._8 8 E-6 8.62E-9 5.33E-10

)

Iron - 59 Ci N/D N/D N/D N/D I

Cobalt - 60 Ci N/D 4.49E-6 3.04E-7 5.18E-10 t

Zine - 65 Ci N/D N/D N/D N/D i

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

i Strontium - 90 Ci N/D N/D 3.96E-12 N/D 1

Silver - 110m Ci N/D N/D N/D N/D i

Cesium - 134 Ci N/D N/D 1.46E-7 9.19E-8 l

Cesium - 136 Ci N/D N/v N/D N/D N/D is Not Detectable N/A is Not Applicable

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4

TABLE 2A NORTH ANNA POWER STATION SEMI-AN..M L RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS-SUMMATION OF ALI RELEASES FOR 01/92 - 06/92 1st 2nd ESTIMATED TOTAL UNITS QUARTER QUARTER "J'RCENT ERROR (%) _

A. Fission acd Activation Products:

1.

Total release (not including tritium, noble gases, and gross alpha).

Curies 1.21E-1 1.70E-1 2.00E*1 l

2. Average diluted concentration during the period.

pCi/ml 3.36E-10 2.52E-10 3.

Percent of applicable limit (T.S.).

1.04E-2 4.76E-3 B. Tritium:

l 1.

Total release activity.

Curies 1.53E+2 1.21E+2 2.00E+1 i

2. Average diluted concentration during the period.

pCi/ml 4.25E-7 1.78E-7 3.

Percent of applicable limit (T.S.).

1.41E-2 5.98E-3 C. Dissolved and Entrained Gases:

i 1

1.

Total release activity.

Curies 1.05E-1 9.28E-3 2.00E+1

2. Average diluted concentration during the period.

pCi/ml 2.91E-10 1.37E-11 3.

Percent of applicable limit (T.S.).

1.46E-4 6.83E-6 D. Gross Alpha Radioactivity:

1.

Total re?anse activity.

Curies N/D N/D 2.00E+1 E. Volume of waste released: (prior to dilution).

Liters 4.73E+7 6.21E+7 3.00E+0 F. Volume of dilution water used during period.

Liters 3.60E+11 6.78E+11 3.00E+0 N/D is Not Detectable N/A is Not Applicable J

w..

TABLE 2B l

NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR 01/92 - 06/92 Page 1 of 2 CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission and Activation Products:

Manganese - 54 Ci 1.42E-4 5.92E-4 N/D N/D

-Iron - 55 Ci N/D N/D N/D N/D Cobalt - 58 Ci 3.83E-2 5.17E-2 2.20E-9 2.02E-8 Cobalt - 60 Ci 1.23E-2 1.82E-2 1.08E-5 3.05E-6 Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver - llom Ci 1.09E-2 2.05E-2 N/D N/D Iodine - 131 Ci 1.01E-2 6.60E-3 5.58E-6 1.llE-8 Iodine - 132 Ci N/D N/D 2.42E-7 4.70E-9 Iodine - 133 Ci 1.83E-3 7.40E-3 2.47E-6 2.91E-8 Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D_

l.49E-4 4.40E-7 N/D Cesium - 134 Ci 1.83E--3 1.15E-3 3.78E-6 9.91E-6 Cesium - 136 Ci 1.47E-4 N/D 1.52E-7 N/D Cesium - 137 Ci 4.24E-3 4.14E-3 6.43E-6 4.51E-5 Barium - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 143 (T

< 8 days)

Ci 8.52E-5 N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (specify) l Sodium - 24 (T

< 8 days)

Ci 2.69E-5 N/D 3.79E-9 1.85E-9 l

Chromium - 51 Ci 7.78E-3 8_.54E-3 N/D N/D Iron - 59 Ci 2.06E-3 5,44E-4 N/D N/D Bromine - 84 (T

< 8 days)

Ci 5.89E-5 N/D N/D N/D Niobium - 95 Ci 2.86E-3 8.79E-3 N/D N/D Zironium - 95 Ci 6.17E-5 2.14E-3 N/D N/D Technetium - 99m (T

< 8 days)

Ci N/D N/D N/D N/D Ruthenium - 103 Ci 1.78E-5 1.23E-4 N/D N/D-Rhodium-Ruthenium-106 Ci N/D 1.37E-3 N/D N/D A11timony - 122 (T

< 8 days)

Ci N/D N/D 2.40E-7 N/D Antimony - 124 Ci 8.74E-4 3.78E-4 N/D N/D Antimony - 125 Ci 2.72E-2 3.81E-2 N/D N/D Tellurium - 129m Ci N/D N/D N/D N/D

)

N/D is Not Detectable N/A is Not Applicable l.

.. j

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TABLE 3

NORTl!

ANNA POWER STATIO2)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SIIIPMENTS FOR 01-01-92 THROUGil 06-30-92 Page 1 of 2 A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTl?

ESTIMATED TOTAL 1.

Type of Waste UNIT PERIOD ERROR PERCENT

(%)

a.

Spent resins, filter m'

9.55E+1

• 2.50E+1 sludges, evaporator Ci 3.31E+2 2.50E+1 bottoms, etc.

5.

Dry compressible waste, m'

7.26E+2 **

2.50E+1 contaminated equipment, Ci 1.065E+1 2.50E+1 etc.

c.

Irradiated components, m'

O.00E+0 9.00E+0 control rods, etc.

Ci 0.00E+0 0.00E+0 d.

Waste Oil m'

6.98E+0 ***

2.50E+1 Ci 1.90E-1 2.50E+1 2.

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

C-14 1.50E+0 2.50E+1 Fe-55 1.70E+1 2.50E+1 Co-58 5.53Et0 2.50E+1 Co-60 3.37E+1 2.50E+1 Ni-63 3.58E+1 2.50E+1 Cs-134 1.44E+0 2.50E+1 Cs-137 3.67E+0 2.50E+1 b.

Cr-51 1.27E+0 2.50E+1 Fe-55 2.06E+1 2.50E+1 Co-58 1.83E+1 2.50E+1 Co-60 1.17E+1 2.50E+1 Ni-63 3.56E+0 2.50E+1 Zr-95 1.28E+1 2.50E+1 Nb-95 2.46E+1 2.50E+1 Cu-137 2.91E+0 2.50E+1 Ce-144 1.10E+0 2.50E+1

TABLE 3

NORTH ANNA POKER STATION SEMT-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-92 THROUGH 06-30-92 Page 2 of 2 2.

Estimate of major 6-MONTH ESTIMATED TOTAL nuclide composition UNIT PERIOD ERROR PERCENT (by type of waste)

(t)

(cont.)

c.

NONE d.

Fe-55 4.69E+1 2.50E+1 Co-58 5.02E+0 2.50E+1 Co-60 5.68E+0 2.50E+1 Ni-63 2.23E+1 2.50E+1 Ag-110 a 1.87E+1 2.50E+1 3.

Solid Waste Disposition Number of Shipments Mode of Transportation Destination 14 Truck Barnwell,S.C.

14 Truck Oak Ridge,T.N.

(SEG) 1 Truck Oak Ridge,T.N.

(Quadrex) 1 Truck Wampum,PA (Alaron)

B.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0

N/A N/A 2 shipments of resin were shipped from North Anna to_a licensed waste processor for volume reductio 1.

Therefore, the volume listed for this type is not representativa of actual volume buried.

The total volume buried for this report.ng period was 78.8 cubic meters.

13 shipments of dry compressible waste / contaminated equipment were shipped from North Anna to a licensed waste processor for volume reduction.

Therefore, the volume listed for this type is not representative of the acutal volume buried.

The total volume buried for this reporting period was 83.6 cubic meters.

o**:

1 shipment of waste oil was shipped from North Anna to a licensed waste processor for incineration.

Therefore, the volume buried for this reporting period was 0 cubic meters.

ATTACliMENT 2

AMNUAL_.JdD_ QUARTER _IJ DOS)$S Lh1492 06/321 An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous ef fluents released from the site for each calendar quarter, along with an annual total of each effluent pathway, will be made pursuant to the ODCM, Section 6.6.2 requirements in the report submitted within 60 days after January 1, 1993.

7

ATTACHMENT 3

REYLS10NS TO OPEElTE_RQSE__CALCUIATlDH_. MANUAL i

LQDCML LQ1/92 06/921 i

As required by Technical Specification 6.15, revisions to the ODCM i

effective for the time period covered by this report, are synopsized in this attachment.

i l

Revision 3 of the Virginia Power Offsite Dose Calculation Manual was effective June 01, 1992.

A copy of Revision 3 of the Offsite Dose Calculation Manual is attached.

Changes made effective with Revision 3 are indicated by marking the borders of the revised areas with the effective date of the change.

All changes i

marked "Rev.

3" were effective June 01, 1992.

In addition to the changes noted in the revision summary of the cover sheet l

of the Offsite Dose Calculation Manual, the revisions marked in Attachment 25, Detection Capabilities for North Anna Environmental Sample Analysis, page 1 of 2, are noted for listing Zr-95, Nb-95, Ba-140 arid La-140 separately with their corresponding Lower. Limits of Detection in accordance with the Radiological Assessment Branch Technical Position on Environmental Monitoring, November, 1979, Revision 1.

Punctuation, spelling and other minor wording and text presentation changes were corrected in Revision 3.

These minor changes are not specifically identified, as they do not effect the text content.

8

..~..

ATTACEMENT 4

MAJJQR CHANGES TO RADLOACTIVE 1,1QQ1D m GASE_QUS.

AND__SOLlQ WASTE TREATM C SYSTEMS LQ1/92 06/_9%.

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 gaseous and solid waste treatinent systems were made for the time period covered by this report.

The Clarifier Liquid Effluent Proportional Sampling Tank, 1-LW-TK-20, was removed and replaced with a larger volume tank.

Tank capacity was increased from 250 liters to 1000 liters.

The sampling valve that provides flow to the tank, 1-LW-1130, is now adjusted to provide a proportional sample at a rate of at least 0.5 milliliters per-gallon of waste discharged.

No major changes to the radioactive liquid waste treatment system were involved.

f f

n 9

l

ATTACIIMENT 5

IRQfERABILITY OF RMALQACTIVE LIQUID ___AND_ GASEQUS E M UENT MONITORING INSTRUMENTATION f01/92 06MJ,1 As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended 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 Caseous Effluent Monitoring Instrumentation specified in the

ODCM, Attachments 2 and 15, for the time period covered by this report.

4 10

MTACIIMERT 6

UNPLANjiED RELIMSE,S 06/92)

[01/92 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 offluents occurring during the reporting period, is made in this attachment.

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

o 11

_ _ _ _ _ _ _. _. =. _ _ _. _

A2TACHMENT 7

LQWER LIMITS OF DhTECTLQN FOll__ EFFLUENT SAMELE ANALYSIR 06/S21 101492 Gascons EUluenta:

Required L.L.D.

Typical L.L.D.

Radioisotope f uplfmu (uC1/ml)

Kry_pton - 87 1.00E-4 1.94E-8 4.25E-7

__lrypton - 88 1.00E-4 2.91E-8 5.68E-7 Xenon - 133 1.00E-4 3.71E-8 4.20E-7 Xenon - 133m 1.00E-4 7.06E-8 1.41E-6 Xenon - 135 1 00E-4 8.30E-9 1.67E-7 Xenon - 135m 1.00E-4 3.34E-8 6.72E-7 Xenon - 138 1.00E-4 6.67E-8 1.96E-6 Iodine - 131 1.00E-12 2.53E 14 -

6.51E-14 Manganese - 54 1.00E-11 2.84E 4.29E 14 Cobalt - 58 1.00E-11 2.27E 4.78E-14

__ Iron - 59 1.00E-11 4.62E 9.96E-14 Cobalt - 60 1.00E-11 3.08E 7.14E-14 Zinc - 65 1.00E-11 5.47E 1.19E-13 Strontium - 89 1.00E-11 3.00E 1.00E-11 Strontium - 90 1.00E-11 6.00E 6.h E-12 Molybdenum - 99 1.00E-11 1.31E 3.69E-13 Cesium - 134 1.00E-11 2.52E 4.77E-14 Cesium - 137 1.00E-11 2.85E 5.43E-14 Cerium - 141 1.00E-11 2.11E 6.58E-14 Cerium - 144 1.00E-11 1.08E 2.95E-13 Gr_o_ss AlDha 1.00E-11 9.86E 5.06E-14 Tritium 1.00E-6 1.37E-7 1.46E-7 12

ATTAC1MUNT 7

LQWER__LDilTS_ _._OF DETECTION FOR _ _ EFFLUJH_'L_ SAMPLE ANALYSlit.

101/_92 06/91J Liqu_id_

Effluents:

Required L.L.D.

Typical L.L.D.

__ ram _gisotope.

LyC1/31)

(Jtci/mli Krypton - 87 1.00E-5 2.50E-8 7.09E-8 Kryplon - 88 L OOE-5 4 00E-8 1.94E-7 Xenon - 133 1.00E-5 4 d2E-8 8.2_LE-8 Xenon - 133m 1.00E-5 9.51E-8 2.53E-7

__lquon - 135 1.00E-5 1.11E-8 2.98E-8 XenoJ1 - 135m 1.00E-5 4.29E-8 1.21E-7 Xenon - 138 1.00E-5 8.88E-8 3.62E-7 Iodine - 131 1.00E-6 1.18E-8 2.90E-8 lignaanese - 54 5.00E-7 1.79E-8 2.75E-8 Iron - 55 1.00E-6 5.00E-7 1.00E-6 Cobalt - 58 5.00E-7 1.45E-8 2.91E-8 Iron - 59 5.00E-7 2.70F-8 6.02E-8 Cobalt - 60 5.00E-7 1.71E-8 4.29E-8

, Zinc - 65 5.00E-7 3.17E-8 7.22E-8

_ Stronti_um - 89 5.00E-8 3.00E-8 4.00E-8 Strontium - 90 5.00E-8 5.00E-9 7,00E-9 Molybdenum - 99 5.00E-7 8.54E-8 2.47E-7 Cesium - 1J4 5.00E-7 1.61E-8 3.12E-8 Cesium - 137 5.00E-7 1.91E-8 3.64E-8 Ceriq_m - 141 5.00E-7 1.71E-8 5.02E-8 Cerium - 144 5.00E-7 8.84E-8 2.27E-7 Gross Alpha 1.00E-7 5.68E-9 2.92E-8 Tritiur.

1.00E-5 3.79E-6 4.02E-6 13

LEV!L 2 CONTROLLED Di$TRIEUiiON 13.a nif noj by tNs Departmsnt Do not tornove this documrit for field work Station Administrative A

Procedure VIRGINIA POWiR e 1992 tiy %rFuus Pomer. All Righu Resened

Title:

Offsite Dose Calculation Manual Lead Department: Radiological Protection I

Procedure Number Revision Number Effectis e Date VPAP-2103 3

06/01/92 Revision Summary

. Inec,rporated Suny T 1. His change invo:ved the follow 2ng:

• Remed Subsection 4 2 to add clartfication to the Channel Check defuunon for single channels he third senten.c ci the subsectim represents the new addiunn Remed Subsection 4.5 to add the frequency of Dunng Reicase for a ChannelCheck of flow rate measunng dences since there is no frequency of a daily release Revtsed Attachment 3 to change the ource Check of the Gross Ramoactinty M.3mtars from PR to P and changed the Gannel Oeck

. Incorporated North Anna T I which addressed the concems bsted in NRC Inspection Repon 92 05. This change involved the following:

A ided new Step 11.21 which hsts the N APS modtficaums to the Circulsung Water Sy stem Reused Anachment 6 to correct the flow rate based m LTSAR.Secnon 11.2, by correcting formulas, adding a note to the text. and currectuig the values m the laa table Reused Attachment 7 to cortect salues in the table

. Reused Attachment 11 to add Note 6 for weekly CAE vent and SGRV grab samples Reused Attachment 24 to add a.it term in the LLD defimtion equauon

. Incorporated Surry T 2 which addresses QA Audit No. 92sl3.oDCM/PCP item No. 92-030B04NS Otem 2). The change renses Step 6.5.2 b.2 to spmfy a calculated do.e or dose comrmur.ent of 20 percent for SPS and 25 percent for NAPS. Also added new conumtment Step 3.2.3

• Reused Anachmem 22 to change Ryan's Garden to Lucas's Garden Corrected the numbenng and cross referencirig of the equanons

+

Reused steps 415.ft5.1.b.and 6.5.2.c and added new ster 6 6 4.e to incorporate VPAP-2802 Nottficanons and Repons Uplate references Upgraded sc, current Wnter's Guide Placed procedure tn Frame Maker appbcanon a

Surry Power Station North Anna Power Station A proved by:

Approved by.

~_ n = -l l

0WN

/

JrN5gt' Chairman [/f

.T2.4-9Z -

Datf SNSOC Chairman

' Date l Appro edgyr Approved by:

/)?

&I f

!2 S/27A?1-.

/

/ Ststion Manager

/ Dite StationMana{tr Date 8 M k 9.s[

Approved by:

6_

v

/ ce President-Nuclear Operations Date Vi i

>\\

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 2 OF 125 i

TAllLE OF CONTENTS Section Page 1.0 PURPOSE 5

2.0 SCOPE 5

3.0 REFERENCES

/ COMMITMENT DOCUMENTS 5

4.0 DEFINITIONS 7

5.0 RESPONSIllILITIES 11 6.0 INSTRUCTIONS 12 6.1 Sampling and Monitoring Criteria 12 6.2 Liquid Radioactive Waste Effluents 12 6.2.1 Liquid Effluent Concentration Limitations 12 6.2.2 Liquid Monitoring Instrumentation 13 6.2.3 Liquid Eftluent Dose Limit 17 6.2.4 Liquid Radwaste Treatment 21 6.2.5 Liquid Sampling 22 6.3 Gaseous Radioactive Waste Effluents 22 6.3.1 Gaseous Effluent Dose Rate Limitation 22 6.3.2 Gaseous Monitoring Instrumentation 25-6.3.3 Noble Gas Effluent Air Dose Limit 28 6.3.4 I-131, H-3, and Radionuclides In Particulate Form Effluent Dose Limit 30 6.3.5 Gaseous Radwaste Treatment 33 6.4 Total Dose Limit to Public From Uranium Fuel Cycle Sources 35 6.5 Radiological Environmental Monitoring 36 6.5.1 Monitoring Program 36 l

6.5.2 Land Use Census 38 i

6.5.3 Interlaboratory Comparison Program 39 l

4 1

i VIRGIN 1A VPAP-2103 POWER REVISION 3 4

PAGE 3 OF 125 6.6 Reporting Requirements 40 6.6.1 Annual Radiological Environmental Operating Report 40 6.6.2 Semiannual Ra:iioactive Effluent Release Report 41 l

6.6.3 Annual Meteorological Data 42 6.6.4 Changes to the ODCM 42 7.0 RECORDS 44 A'ITACilMENTS 1 Surry Radioactive Liquid Efiluent Monitoring Instrumentation 45 3

l 2 North Anna Radioactive Liquid Efnuent MonitoringInstrumentation 46 l

3 Surry Radioactive Liquid Emuent Monitoring Instrumentation 48 Suneillance Requirements 4 North Anna Radioactive Liquid Effluent Monitoring Instrumentation 49 Surveillance Requirements j

5 Liquid Ingestion Pathway Dose Factors for Surry Station Units I and 2 51 6 North Anna Liquid Ingestion Pathway Dose Factor Calculation 52 Units 1 and 2 l

7 North Anna Liquid Pathway Dose Commitment Factors for Adults 57 8 Surry Radioactive Liquid Waste Sampling and Analysis Program 58 9 North Anna Radioactive Liquid Waste Sampling and Analysis Program 61 l

10 Surry Radioactive Gaseous Waste Sampling and Analysis Program 64 1

11 North Anna Radioactive Gaseous Waste Sampling and Analysis Program 69

{

12 Gaseous Eifluent Dose Factors for Surry 73 13 Gaseous Effluent Dose Factors for North Anna 76 14 Surry Radioactive Gaseous Ef0uent Montoring Instrumentation 79 i

15 North Anna Radioactive Gaseous Efnuent Montoring Instrumentation 81 16 Surry Radioactive Gaseous Effluent Montoring Instrumentation 83 Surveillance Requirements 17 North Anna Radioactive Gaseous Efiluent Montoring Instrumentation 84 Surveillance Requirements 18 Critical Organ and Inhalation Dose Factors for Surry 86 l

19 Critical Organ Dose Factors for North Anna 88

VIRGINIA VPAP-2103 4

POWER REVISION 3 PAGE 4 OF 125 I

l TAllLE OF CONTENTS (continued) -

l Section Page ATTACIIMENTS (continued) 20 Surry Radiological Environment Monitoring Program 89-21 North Anna Radiological Environmental Monitoring Program 91 i

22 Surry Environmental Sampling Locations 96' 23 North Anna Environmental Sampling Locations 100 24 Detection Capabilities for Surry Environmental Sample Analysis 104 25 Detection Capabilities for North Anna Environmental Sampic 106 Analysis i

26 Reporting Levels for Radioactivity Concentrations in Environmental 108 Samples at Surry 27 Reporting Levels for Radioactivity Concentrations in Environmental 109 Samples at North Anna 28 Surry Meteorological, Liquid, and Gaseous Pathway Analysis 110 29 North Anna Meteorological, Liquid,and Gaseous Pathway Awalysis 118 i

n 4

1 I.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 5 OF 125 1.0 Pl]RPOSE The Offsite Dose Calculation Manual (ODCM) establishes the requirements of the Radioactive Effluent and Radiological Environmental Monitoring Programs. Methodology and parameters are provided for calculation of offsite doses resulting from radioactive gaseous and liquid effluents, for gaseous and liquid ef0uent monitoring alarm / trip setpoints, and for conduct of the Environmental Monitoring Program. Requirements are established for the Annual-Radiological Environmental Operating Report and the Semi-Annual Radioactive Effluent Release Report required by Station Technical Specifications. Calculation of offsite doses due to radioactive liquid and gaseous effluents are performed to assure that:

Concentration of radioactive liquid effluents to the unrestricted area will be limited to the levels of 10 CFR 20, Appendix B, Tabie II, column 2, for ractionuclides other than dissolved or entrained noble gases

. Exposure to the maximum exposed member of the public in the unrestricted area from radioactive liquid effluents will not result m doses greater than the liquid dose limits of 10 CFR 50, Appendix i

. Dose rate at and beyond the site boundary from radioactive gaseous effluents will be limited to the annual dose rate limits of 10 CFR 20

. Exposure from radioactive gaseous effluents to the maximum exposed member of the public in the unrestricted area will not result in doses greater than the gaseous dose limits of 10 CFR 50, Appendix 1, and

. Exposure to the maximum exposed member of the public will not exceed 40 CFR 190 dose limits 2.0 SCOPE This procedure applies to the Radioactive Effluent and Environmental Monitoring Programs at Surry and North Anna Stations.

3.0 REFERENCES

/ COMMITMENT DOCUMENTS 3.1 References 3.1.1 10 CFR 20, Standards for Protection Against Radiation 3.1.2 10 CFR 50, Domestic Licensing of Production and Utilization Facilities 3.1.3 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations 3.1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites

_ = _

i VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 6 OF 125 1

1-3.1.5 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, Rev.1, U.S. NRC, June 1974 3.1.6 Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Releases.

of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR 50, j

Appendix 1, Rev,1, U.S. NRC. October 1977 j

3.1.7 Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and j

Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Rev.1. U.S. NRC, July 1977 j

3.1.8 Surry and North Anna Technical Specifications (Units 1 and 2) 3.1.9 NUREG-0324, XOQDOQ, Program for the Meteorological T sluation of Routine j

Effluent Releases at Nuclear Power Stations, U.S. NRC, Ser er 1977 l

3.1.10 NUREG/CR-1276, Users Manual for the LADTAP 11 Program, I;.S. NRC, May,1980 3.1.11 NUREG-0597, User's Guide to GASPAR Code, U.S. NRC, June,1980

)

3.1.12 Radiological Assessment Branch Technical Position on Environmental Monitoring, November,1979, Rev. I 1

3.1.13 NUREG-0133 Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations, October,1978 3.1.14 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 3.1.15 NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, Rev. 3. March 1982 -

3.1.16 Environmental Measurements Laboratory, DOE HASL 300 Manual 3.1.17 NRC Generic Letter 89-01, Imp;ementation of Programmatic Controls for l

Radiologica! Effluent Technaal Specifications (RETS) in the Administrative Controls i-Section of the Technical Specific 4iens and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program t

3.1.18 UFS AR (Srry and North Ann:.)

3.1.19 Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual, IWL-0032-361 3.1.20 VPAP-2802, Notifications and Reports 3.1.21 NAPS Circulating Water System Modifications

a. DC-85-37-1 Unit 1 Rev.3 l

b. DC-85-38-2 Unit 2 i

--,...,,_,_.,.m-.

VIRGINIA VPAP-2103 i

POWER REVISION 3 PAGE 7 OF 125 3.2 Commitment Documents l

3.2.1 Quality Assurance Audit Report Number C 90-22, Management Safety Review Committee, Observation 03C, January 17,1991 l

3.2.2 Quality Assurance Audit Report Number 91-03, Observation 08N 4

3.2.3 Quality Assurance Audit Report Number 92-03, Observation 04NS (ltem 2) l Rev.3 4.0 DEFINITIONS I

4.1 Channel Calibration j

Adjustment, as necessary, of the channel output so it responds with the necessary range and accuracy to known values of the parameter the channel monitors. It encompasses the entire channel including the sensor and alann and/or trip functions, and includes the Channel l

Functional Test. The Channel Calibration can be performed by any series of sequential, overlapping or total channel steps so the entire channel is calibrated.

4.2 Channel Check A qualitative assessment, by observation, of channel behavior during operation. This assessment includes, where possible, comparison of the channel indication and/or status with i

other indications and/or status derived from independent instrumentation channels measuring l

the same parameter. When comparison with other indications is not possible, consistency with l

previous normal indications under sic.ilar operating conditions satisfies the Channel Check Rev.3 L

requirement.

4.3 Channel Functional Test i

There are two types of Channel Functional Tests.

4.3.1 Analog Channels 4

Injection of a simulated signal into a channel as close to the sensor as practicable to 4

venfy Operability, including alarm and/or trip functions.

4 4.3.2 Ilistable Channels Injection of a simulated signal into a sensor to verify Operability, including alarm and/

l or trip functions.

4 J

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VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 8 OF 125 4.4 Dose Equivalent 1 131 That concentration of II3I (microcurie / gram) which alone would produce the same thyroid I3I 134 dose as the quantity and isotopic mixture of I

,1132 g133,3 and II35, actually present.

Thyroid dose conversion factors used for this calculation are listed in Table ill of TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites. Thyroid dose conversion factors from NRC Regulatory Guide 1.109, Revision 1, may be used (Surry).

4.5 Frequency Notations NOTE: Frequencies are allowed a maximum extension of 25 percent.

NOTATION FREQUENCY D - Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W - Weekly At least once per 7 days M - Monthly At least once per 31 days Q - Quarterly At least once per 92 days S A - Semi-annually At least once per 184 days R - Refueling At least once per 18 months S/U - Start-up Pdc-to each reactor start-up P - Prior to release Completed prior to each release N.A. - Not applicable Not applicable DR - During the release At least once during each release l Rev.3 4.6 Gaseous Radwaste Treatment System A system that reduces radioactive gaseous effluents by collecting primary coolant system offgases thm the primary system and provides delay or holdup to reduce total radioactivity prior to release to the environment. The system coraprises the waste gas decay tanks, regenerative heat exchanger, waste gas charcoal filters, process vent blowers, waste gas surge tanks, and waste gas diaphragm compressor (North Anna).

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 9 OF 125 4.7 General Nomenclature x = Chi: concentration at a point at a given instant (curies per cubic meter)

D = Deposition: quantity of deposited radioactive material per unit area (curies per square meter)

Q = Source strength (instantaneous: grams, curies)

= Emission rate (continuous; grams per second, curies per second)

= Emission rate (continuous line source: grams per second per meter) 4.8 Lower Limit of Detection (LLD)

The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95 percent probability with only 5 percert probability of falsely concluding that a blank observation represents a"real" signal.

4.9 Members of the Public Individuals who, by virtue of their occupational status, have no fonnal association with the c

Station. This category includes non-employees of Virginia Power who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with Station functions. This category does not include non-employees such as vending machine seivicemen or postmen who, as part of their formaljot anction, occasionally enter an area that is controlled by Virginia Power for purposes of protection ofindividuals from exposure to radiation and radioactive materials.

4.10 Operable - Operability A system, subsystem, train, component or device is operable or has operability when it is capable of performing its specified functions and all necessary, attendant instrumentation,-

controls, normal and emergency electrical powei w.ces, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its functions are also capable of performing their related support functions.

4.11 Purge. Purging Controlled discharge of air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, so that replacement air or gas is required to purify the confinement.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 10 OF 125 4.12 Rated Thermal Power Total reactor core heat transfer rate to reactor coolant.

+ Surry:

2441 Megawatt Thennal(MWt)

. North Anna:

2893 MWt 4.13 Site lloundary The line beyond which Virginia Power does not own, lease, or otherwise control the land.

4.14 Source Check A qualitative assessment of channel response when the channel sensor is exposed to radiation.

This applies to installed radiation monitoring systems.

4.15 Special Report A report to the NRC to comply with Subsections 6.2,6.3, or 6.4 of this procedure. Also refer Rev.3 to VPAP-2802, Notifications and Reports.

4.16 Thermal Power Total reactor core heat transfer rate to the reactor coolant.

4.17 Unrestricted Area Any area at or beyond the site boundary where access is not controlled by Virginia Power for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or for industrial, commercial, institutional or recreational purposes.

4.18 Ventilation Exhaust Treatment System

.A system that reduces gaseous radiciodine or radioactive material in particulate fami in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and liigh Efficiency Particulate Adsorber (HEPA) filters to remove iodines and particulates from a gaseous exhaust stream prior to release to the environment (such a system is not considered to have any Tect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not Ventilation Exhaust Treatment System components, p~

l I

VIRGINTA

-VPAP-2103 POWER REVISION 3 PAGE 11 OF 125 5.0 RESPONSilllLITIES 5.1 Radiological Protection Radiological Protection is responsible for:

5.1.1 Establishing and maintaining procedures for surveying, sampling, and monitoring radioactive effluents and the environment 5.1.2 Surveying, sampling, and analyzing plant effinents and environmental monitoring, and documenting these activities.

5.1.3 Analyzing plant effluent trends and recommending actions to correct adverse trends.

5.1.4 Preparing Effluent and Environmental Monitoring Program records.

5.2 Operations Department The Operations Department is responsible for requesting samples, analyses, and authorization to release effluents.

l l

l l

)

4.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 12 OF 125 l

6.0 INSTRUCTIONS NOTE: Meteorological, liquid and gaseous pathway analyses are presented in Attachments 28 and 29, Meteorological, Liquid, and Gaseous Pathway Analysis.

6.1 Sampling and Monitoring Criteria 6.1.1 Surveys, sampling, and analyses shall use instruments calibrated for the type and range i

of radiation monitored and the type of discharge monitored.

6.1.2 Installed monitoring systems shall be calibrated for the type and range of radiation or parameter monitored.

6.1.3 A sufficient number of survey points shall be used or samples taken to adequately assess the status of the discharge monitored.

6.1.4 Samples shall be representative of the volume and type of discharge monitored.

6.1.5 Surveys, sampling, analyses, and monitoring records shall be accurately and legibly documented, and sufficiently detailed so that the meaning and intent of the records are clear.

l 6.1.6 Surveys, analyses, and monitoring records shall be reviewed for trends, completeness, and accuracy.

6.2 Liquid Radioactive Waste Effluents 6.2.1 Liquid Effluent Concentration Limitations

a. Liquid waste concentrations discharged from the Station shall not exceed the following I!mits:

1. For radionuclides (other than dissolved or entrained noble gases), liquid effluent concentrations released to unrestricted areas shall not exceed those specified in 10 CFR 20, Appendix B, Table II, Column 2.

2. For dissolved or entrained noble gases, concentrations shall not exceed 2E-4 Ci/ml.

b. If the concentration of liquid effluents exceed above limits in Step 6.2.1.a.,

promptly reduce concentrations to within limits.

~,.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 13 OF 125

c. Daily concentrations of radioactive materials in liquid waste released to unrestricted areas shall meet the following:

Volume of Waste Discharged + Volume of Dilution Water 21 (1)

Volume of Waste Discharged x [pCi/ml.

MPC i

I where:

Ci/mli = the concentration of nuclide i in the liquid effluent discharge:

MPC

= the maximum permissible concentration in unrestricted areas of nuclide, i

i, expressed as pCi/ml frorr,10 CFR 20, Appendix B, Table II, for radionuclides other than noble gases, and 2E-4 pCi/ml for dissolved or entrained noble gases 6.2.2 Liquid Monitoring Instrumentation

a. Radioactive Liquid Efiluent Monitoring Instrumentation Radioactive liquid effluent monitoring instrumentation channels shown on Attachmer,ts 1 and 2, Radioactive Liquid Effluent Monitoring Instrumentation, shall be operable with their alarm / trip setpoints set to ensure that limits of 6.2.1.a.

are not exceeded.

1. Alarm / trip setpoints of these channels shall be determined and adjusted in accordance with 6.2.2.d., Setpoint Calculation.

2. If a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint is less conservative than required by 6.2.2.a., perform one of the following:

. Promptly suspend release of radioactive liquid effluents monitored by the affected channel

. Declare the channelinoperable

. Change the setpoint to an acceptable, conservative value S

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 14 OF 125

b. Radioactive Liquid Effluent Monitoring Instrumentation Operability Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performing a Channel Check, Source Check, Channel 4

Calibration, and Channel Functional Test at the frequencies shown in Attachments 3 and 4, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.

1

1. If the number of operable channels is less than the minimum required by the tables in Attachment 1 or 2, perform the action shown in those tables.

2. Attempt to return the instruments to operable status within 30 days. If unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. Applicable Monitors Liquid effluent monitors for which alarm / trip setpoints shall be deterrr.ined are:

Instrument Number Release Point North Anna Surry Liquirl Radwaste Effluent Line LW-111 LW 108 Service Water System Effluent Line SW-108 SW-107 A, B, C, D Condenser Circulating Water Line SW-130, SW-230 SW-120, SW-220 Radwaste Facility Eftluent Line N/A RRM-131 4

i

4 VIRGINIA

' PA P-2103 POWER Ru?'SION 3 FAGE l$ OF 125 t

d. Setpoint Calculation NOTE: This methodology does not preclude use of more conservative setpoints.

1. Maximum setpoint values shall be calculated by:

CF j

c :

g-(2) where:

the setpoint,in pCi/ml, of the radioactivity monitor measuring the c =

radioactivity concentration in the effluent line prior to dilution:

C=

the effluent concentration limit for the monitor used to implement 10 CFR 20 for the Station, in pCi/ml; f

the flow setpoint as measured at the radiatica monitor location, gpm;

=

F dilution water flow calculated as:

=

(Surry) F = f + (200,000 gpm x Number of Cire. Pumps in Service)

(N. Anna) F = f + (218,000 gpm x Number of Cire. Pumps in Service)

2. Each of the condenser circulating water channels (Surry: SW-120, SW 220)

(North Anna: SW-130, SW-230) monitors the effluent (service water, including component cooling service water, circulating water, and liquid radwaste)in the circulating water discharge tunnel beyond the last point of possible radioactive material addition. No dilution is assumed for this pathway. Therefore, Equation j

(2) becomes:

c=C (3)

The setpoint for Station monitors used to implement 10 CFR 20 for the site becomes the effluent concentration limit.

3. In addition, for added conservatism, setpoints shall be calculated for the liquid radwaste effluent line (Surry: LW-108, North Anna: LW-111), the service water system effluent line (Surry: SW-107 A, B. C, and D, North Anna:

SW-108), and the Radwaste Facility effluent line (Surry: RRM-131).

l l

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VIRGINIA VPAP.2103 IGWER REVISION 3 PAGE 16 OF 125

4. For the tiquid radwaste effluent line, Equation (2) becomes:

CFK uv c=-

(4) 7 where:

Kw t

The fraction of the efnuent concentration limit, used to implement

=

10 CFR 20 for the site, attributable to the liquid radwaste effluent line pathway.

5. For the service water system effluent line, Equation (2) becomes:

CFK Sw c=

(5) f,

.vhere:

Kw 3

The fractSn of the effluent concentration limit, used to implement

=

10 CFR 20 for the Station, attributable to the service water effluent line pathway.

6. For the Radwaste Facility effluent line, Equation (2) becomes'.

CFK gw c=

(6) where:

Kgw The fraction of the effluent concentration limit, used to implement

=

10 CFR 20 attributable to the Radwaste Facility effluent line

pathway,

7. The sum K w 4 Ksw + Kaw sall not be greater than 1.0.

t

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 17 OF 125 6.2.3 1.lquirt Efiluent Dose 1,lmit

a. Requirement At least once per 31 days, perform the dose calculation in Steps 6.2.3.c. and 6.2.3.d.

to ensure the dose or dose conunitment to the maximum exposed member of the pub'ic from radioactive materials in liquid releases (from each reactor unit) to unrestricted areas is limited to:

1. During any calendar quarter:

. less than or equal to 1.5 nuem to the total body

. less than or equal to 5 nvem to the critical organ 2, During any calen.ar year:

. Less than or equal to 3 mrem to the total body

. Less than or equal to !O mrem to the critical organ

b. Action if the calculated dose from release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accordance with VPAP 2802, Notifications and Reports, that identifies causes for exceeding 'imits and defines corrective actions taken to reduce l

releases of radioactive materials in liquid effluents to ensule that subsequent releases will be in compliance with the above limits, i

5

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 18 OF 125

c. Surry Dose Contribution Calculations NOTE: Thyroid and GI LLI organ doses must le calculated to determine which is the critical organ for the period being considered, Dose contributions shall be calculated for all radionuclides identified in liquid eTluents released to unrestricted areas based on the equation:

D = t F M [C A i (7) where:

Subscripts Tli, refers to the total body dose (see Equation (11))

=

0, refers to the organ dose (see Equation (12))

i, refers to individual radionuclide D=

the cumulative dose commitment to the total body or critical organ from the liquid effluents for thL period t, in mrem the period for which C and F are av, raged for all liquid releases, hours t

=

i M=

the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless,0.2 from Appendix 11 A. Surry UFSAR F

the near field average dilution factor for C during any liquid effluent

=

i release; the ratio of the average undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted areas C=

the average concentration of radionuclide, i,in undiluted liquid effluent i

during the period, t, from all liquid releases, in pCi/ml 4

4

i j

VIRGINIA VPAP-2103 POWER REVISION 3 i

PAGE 19 OF 125 i

i i

A=

the site related ingestion dose conunitment factor to the total body or critical i

1 i

l organ of an adult for each identified principal gamma and beta emitter in I

mrem ml per hr pCi. Values for Ai are given in Attachment 5. Liquid 1

Ingestion Pathway Dose Factors For Surry Power Station.

J l

i j

A; = 1.14 E+05 (21BF; + 5B1;) DF; (8) where:

j 1 E+06 pCi/pci x 1 E+03 ml/kg/(8760 hr/yr), units conversion 1.14 E+05

=

i factor l

adult fish consumption, kg/yr, from liUREG-0133 21

=

3 adult invertebrate consumption, kg/yr, from NUREG-0133 5

=

j Bl i the bicaccumulation factor for nuclide, i, in invertebrates, pCi/kg per pCi/

=

l 1, from Table A 1 of Regulatory Guide 1.109, Rev. I 3

the bioaccumulation factor for nuclide, i, in fish, pCi/kg per pCi/1, from -

j DF

=

)

Table A 1 of Regulatory Guide 1.109, Rev.1 i

DF,=

the critical organ dose conversion factor for nuclide, i, for adults, in mrem /

pCi, from Table E-11 of Regulatory Guide 1,109, Rev. I i

r i

I l

i 1

f Y

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

VIRGINIA VPAP 2103 a

POWER REVISION 3 PAGE 20 OF 125

d. North Anna Dose Contribution Calculations I

NOTE: Attachment 6, North Anna Liquid Ingestion Pathway Dose Factor Calculation provides the derivation for Equation (9).

i Dose contribution shall lx calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on:

j D=[Q;XB i

Where:

l Subscripts Tii, refers to the total body dose (see Equation (11))

=

o, refers to the organ dose (see Equation (12))

i, refers to individual radionuclide D=

the cumulative dose commitment to the total lxxiy or critical organ from the liquid efnuents for the period t,in mrem Bi= Dose Commitment Factors (mrem /Ci) for adults. Values f or B are provided i

i m Attachment 7, North Anna Liquid Ingestion Pathway Dose Commitment Factors for Adults i

Qi = Total released activity for the considered period and the ith nuclide Q; = t x C; x Waste Flow (10) i l

Where:

the period for which C and F are averaged for all liquid releases, hours t

=

i C=

the average concentration of radionuclide, i, in undiluted liquid effluent i

during the period, t, from any liquid releases,in pCi/ml l

l

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 21 OF 125

e. Quarterly Composite Analyses For radionuclides not determined in each batch or weekly composite, dose contribution to current monthly or calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on previous monthly or quarterly composite analyses. Ilowever, for reporting purposes, calculated dose contribution shall be based on the actual composite analyses.

6.2A 1.iquid Radwaste Treatment

a. Hequirement

1. The Liquid Radwaste Treatment System and/or the Surry Radwaste Facility Liquid Waste System shall be used to reduce the radioactive materials in liquid waste prior to discharge when projected dose due to liquid effluent, from each reactor unit, to unrestricted areas would exceed 0.06 mrem to total body or 0.2 mrem to the critical organ in a 31-day period.

7. Doses due to liquid releases shall be projected at least once per 31 days.

c Auw l

F y ' e th Uguid waste is discharged without treatment and in excess of the abo' e limits, within 30 days, piepare and submit to the NRC, a special report in I

acwrdance with VPAP-2802, Notifications and Reparts, that includes the following:

l. An explanation of why liquid radwaste was being discharged without treatment, j

identification of any inoperable equipment or sub-system, and the reason for the l

inoperability.

2. Actions taken to restore inoperable equipment to operable status.

l

3. Summary description of actions taken to prevent a recurrence.

l l

c. Projected Total llody I)ose Calculation

1. Determine Dn, the total body dose from liquid effluents in the previous 31-day penod, per Equa ion (7) or Equation (9)(Surry and North Anna, respectively).

2. Estimate R, the ratio of the estimated volume ofliquid effluent releases in the l

i present 31-day period to the volume released in the previous 31-day period.

. _ _ - _ _ ~

I VIRGINIA VPAP-2103 4

POWER REVISION 3 PAGE 22 OF 125 e

L

3. Estimate F,the ratio of the estimated liquid effluent radioactivity concentration j

i in the present 31 day period to liquid efnuent concentration in the previous 31-day period (pCihn!).

i

4. Determine PDra, the projected total body dose in a 31-day period.

PDTB

• UTB(N F )

(11)

I 3

d. Projected Critical Organ Dose Calculation i

llistorical data pertaining to the volumes and radioactivity of liquid effluents I

released in connection with specific Station functions, such as maintenance or refueling outages, shall be used in projections as appropriate.

1. Determine D,, the critical organ dose from liquid effluents in the previous 4

t 31-day period, per Equation (7) or Equation (9)(Surry and North Anna, respectively).

2. Estimate R as in Step 6.2.4.c.2.

i

3. Estimate F as in Step 6.2.4.e.3.

4. Determine PD,, = projected critical organ dose in a 31 day period.

PDg=Do(R ;F )

j 6.2.5 Liquid Sampling I

Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis requirements shown in Attachments 8 and 9. Radioactive Liquid Waste Sampling and Analysis Program (Surry and North Anna, respectively).

6.3 Gasemis Radioactive Waste Efnuents 6.3.1 Gascops Efnuent Dose Rate Limitation

a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

1. 'ihe dose rate limit for noble gases shall be s 500 mrem / year to the total body and 5 3000 mrenvyear to the skin.

l

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

l VIRGINIA VPAP-2103 j

POWER REVISION 3 PAGE 23 OF 125 i

2. The dose rate limit for 1I31, for tritium, and for all radioactive materials in l

particulate form with half lives greater than 8 days shall be s 1500 mre'm/ year i

to the critical organ.

i

b. Action

l. If dose rates exceed the above limits, promptly decrease the release rate to within the above limits.

1 I

2. Dose rates due to noble gases in gaseous effluents shall be determined, continuously, to be within the limits specified in Step 6.3.1.a.

2

3. Dose rates due to 1333, tritium, and all radionuclides in particulate form with -

half lives greater than 8 days, in gaseous effluents shall be determined to be j

within the above lim.its by obtaining representative samples and performing j-analyses in accordance with the sampling and analysis program specified on l

Attachments 10 and 11, Radioactive Oaseous Waste Sampling and Analysis i

Program.

1 i

i 3

1 a

t i

i 4

l 4

J i

s

,. ~

,._-....-m

1 i

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 24 OF 125

c. Calculations of Gaseous Effluent Dose Hates

1. The dose rate limit for noble gases shall be determined to be within the limit by limiting the release rate to the lessor of:

((K;yydiyy + K ipy C;py ] s 500 mrem /yr to the total body (13) i OR

(((L;yy + 1.1 M;yy ) d;yy + (L;py + 1.1 M;py ) dipv] s 3000 mrem /yr to the skin (14)

I where:

Subscripts vv, refers to vent releases from the building ventilation vent

=

including Radwaste Facility Ventilation Vent; pv, refers to the vent releases from the process vent; i, refers to individual radionuclide Kjyy, Kipv The total body dose factor for ventilation vents or process vent

=

release due to gamma emissions for each idendfied noble gas radionuclide, i, in mrem /yr per Curie /sec. Factors are listed in Attachments 12 and 13, Gaseous Effluent Dose Factors (Surry and North Anna, respectively)

L y, Lipv The skin dose ft.ctor for ventilation vents or process vent iv

=

release due to beta emissions for each identified noble gas radionuclide i, in mrem /yr per Curie /sec. Factors are listed in i

Attachments 12 and 13 l

hijyy, hiipv The air dose factor for ventilation vents or process vent release

=

{

due to gamma emissions for each identified noble gas radionuclide,1, in mrad /yr per Curie /sec. Factors are listed in Attachments 12 and 13 d d,n The release rate for ventilation vents or process vent of noble

=

gas radionuclide, i, in gaseous effluents in Curie /sec (per site) 1.1 The unit conversion factor that converts air dose to skin dose,

=

in mrem / mrad

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 25 OF 125 333

2. The dose rate limit for 1

, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days, shall be determined to be within the limit by restricting the rele ;c rate to:

lI' ivy hivv + I'ipv bipv ] 5; 1500 mrem /yr to the critical organ (15) i where:

Piyy, P9y The critical organ dose factar for ventilation vents or process

=

333,11, and all radionuclides in particulate form with 3

vent for 1 half-lives greater than 8 days for the inhalation pathway, in mrenVyr pe: Curie /sec. Factors are listed in Attachments 12 and 13 The release rate for ventilation vents or process vent of 1133, dm d,,

=

3 11, and all radionuclides, i, in particulate form with half-lives greater than 8 days in gaseous effluents in Curie /sec (per site)

3. All gaseous releases, not through the process vent, are considered ground level and shall be included in the detemiination or d,,

6.3.2 Gaseous Monitoring Instrumentation

a. Requirement

1. The radioactive gaseous effluent monitoring instrumentation channels shown in 4 or 15, Radioactive Gaseous Effluent Monitoring instrumentation, shall be operable with alarnVtrip setpoints set to ensure that limits specified for noble gases in Step 6.3.1.a. are not exceeded. Alarm / trip setpoints of these channels shall be determined and adjusted in accordance with Step 6.3.2.d.

2. Each radioactive gaseous effluent monitoring instrumentation channel shall be f

demonstrated operable by Channel Checks Source Checks, Channel Calibrations, and Channel Functional Tests at the frequencies shown in 6 or 17, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.

ViltGINIA VPAP-2103 POWER REVISION 3 PAGE 26 OF 125

b. Action

1. If a radioactive gaseous effluent monitoring instrumentation chamiel alartn/ trip 1

setpoint is less conservative than required by 6.2.2.a., promptly:

. Suspend the release of radioactive gaseous ef0uents monitored by the affected channel and declare the channel inoperable; or

. Change the setpoint so it is acceptably conseivative

2. If the number of operable channels is less than the minimum required by tables in Attachment 14 and 15, take the action shown in those tables.

3. Return instruments to operable status within 30 days. If unsuccessful, explain j

in the next Semiannual Radioactive Effluent Release Report why the j

inoperability was not corrected in a timely manner.

i

c. Applicable Monitors Radioactive gaseous effluent monitors for which alann/ trip setpoints shall be determined are:

Instrument Number Helease Point North Anna Surry Process Vent GW 102,GW 1781 GW-102, GW-130 1 I

Condenser Air Ejector SV-12 ), SV-221 SV 111. SV-211 l

Ventilation Vent A VG-104, VG-179-1 N/A l

Ventilation Vent B VG 113 VG-180-1 N/A I

Ventilation Vent No. I N/A VG-104

(

Ventilation Vent No. 2 N/A VG 110, VG 131 1 Radwaste Facility Vent N/A RRM-101 I

u

- =.

t VIRGINIA VPAP 2103-POWER REVISION 3 PAGE 27 OF 125

d. Setpoint Calculat!ons

1. Setpoint calculations for each monitor listed in Step 6.3.2.c. shall maintain this relationship:

D2Dpy + Deae + O (16) vv i

j where:

l D

Step 6.3.1.a. dose limits that implement 10 CFR 20 for the Station.

=

l mrenvyr i

The noble gas Station boundary dose rate from process vent gaseous j

Dy

=

p effluent releases, mrem /yr The noble gas Station boundary dose rate from condenser air ejector 1

D

=

eae 1

gaseous efnuent releases, mrenVyr j

The noble gas Station boundary dose rate from:

D

=

vy a

f Surry: Summation of the Ventilation Vents 1,2, and the Radwaste Facility vent gaseous effluent releases, mrem /yr North Anna: Summation of ventilation vent A plus B gaseous j

effluent releases, mrem /yr

2. Setpoint values shall be determined by:

i R

x 2.12 E-03 C

(17)

=

m p

i l

where:

The release pathway, process vent (pv), ventilation vent (vy) m

=

i condenser air ejector (cae), or Radwaste Facility (rv)

C

- =

The effluent concentration limit implementing Step 6.3.1.a.

m for the Station, pCi/ml I

R The release rate limit for pathway m detennined from

=

m_

I33 methodology in Step 6.3.1.c., using Xe as nuclide' to be released, pCi/se :

2.12E-03 "FM per ml/sec

=

F The maximum flow rate for pathway m, CFM

=

m

VIRGINTA VPAP-2103 POWER REVISION 3 PAGE 28 OF 125 l

NOTE According to NUREG-0133, the radioactive effluent radiation monitor alamVirip setpoints should be based on the.

otive noble gases. It is not practicable to apply instantaneous alarm / trip setpoints to integrating monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases.

6.3.3 Noble Gas Effluent Air Dose Limit l

a. Requirement

1. The air dose in unrestricted areas due to noble gases released in gaseous effluents from each unit at or beyond the site boundary shall be limited to:

. During any calendarquarter: 55 tm ads for gamma radiation and s 10 mrads for beta radiation

. During any calendar year: $ 10 mrads for gamma radiation and 520 mrads for beta radiation

2. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with Step 6.3.3.c.

at least once per 31 days.

b. Action If the calculated air dose from radioactive noble gases in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accor Snce with VPAP-2802, Notifications and Reports, that identifies the causes for exceeding the limits and defines corrective actions that have been taken to redi.: releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits in Step 6.3.3.a.

c. Noble Gas Efiluent Air Dose Calculation Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qvy.

..-.---mw

,,...<--%.4c.._

.,.e,._,,

_._,,,n..

f.

,y%,-,

-,7,.

c 4

w.-.v.,.

,n..--

y.,

4 VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 29 OF 125 1he air dose to areas at or beyond the site boundary due to noble gases shall be j

detennined by the following:

For gamma radiation:

= 3.17 E-08 [ l M ;yy Q jyy + M ;py Qipy]

D g I

I (18)

For teta radiation:

I b = 3.17 E-08 [ [ N;yy Q;yy + N ipyQ;py J (19) l D

a 5

Where:

1 Subscripts vv. refers to vent releases from the building ventile%n vents,

=

including the Radwaste Facility Ventilation Vent and air ejectors pv, refers to the vent releases from the process vent l

i, refers to individual radionuclide i

Dg the air dose for gamma radiation, in mrad

=

I Db the air dose for beta radiation, in mrad

=

l M vy, M v i

ip the air dose factors for ventilation vents or process vent release

=

due to gamma emissions for each identified noble gas radionuclide, i, in mrad /yr per Curie /sec. Factors are listed in l

Attachments 12 and 13 N vy, Nipv the air dose factor for ventilation vents or process vent release i

=

due to beta emissions for each identified noble gas l

radionuclide, i, in mradiyr per Curie /sec. Factors are listed in l

Attachments 12 and 13 Qjvy, Qipv the release for ventilation vents or process vent of noble gas

=

radionuclide, i, in gaseous effluents for 31 days, quarter, or year as appropriate in Curies (per site)

I

- a

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 30 OF 125 6.3.4 I 131,113, and Itadionuclides In Particulate Form Efiluent Dose 1.imit

a. Requirement

1. Methods shall be implemented to ensure that the dose to any organ of a member of the public from II31, tritium, and all radionuclides in particulate fonn with half-lives greater than 8 days, in gaseous effluents released from the site to unrestricted areas from each reactor unit shall be limited:

. During any calendar quarter: s 7.5 mrem to the critical organ

. During any calendar year: s 15 mrem to the critical organ

2. Cumulative dose contributions to a member of the public from iI3I, trit' ai, and radionuclides in particulate form with half-lives greater than 8 days, in ' (cous effluents released to unrestricted areas for the current calendar quarter and current calendar year shall be determined at least once per 31 days in accordance with Steps 6.3.4.c. or 6.3.4.d.

b. Action if the calculated dose from the release of II3I, tritium, and radionuclides in paniculate form, with half lives greater than 8 days,in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC within 30 days, a special report in accordance VPAP-2802, Notifications and Reports, that contains the:

1. Causes for exceeding limits.

2. Corrective actions taken to reduce releases.

3. Proposed corrective actions to be taken to assure that subsequent releases will be in compliance with limits stated in Step 6.3.4.a.

... - -.~ -.

- _. -_..=

I i

VIRGINIA VPAP-2103

)

POWER REVISION 3 PAGE 31 OF 125 4

c. Surry Dose Calculations j

Gaseous releases, not through the process vent, are considered ground level and l

shall be included in the deterrnination of d

. llistorical data pertaining to the l

volumes and radioactive concentrations of gaseous effluents released in connection to specific Station functions, such as containment purges, shall be used in the estimates, as ::ppropriate.

i i

1. The dose to the maximum exposed member of the public, attributable to l

gaseous effluents at and beyond the site boundary that contain 1I33, tritium, and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by:

= 3.17 E-08 (((RM ;yy d;yy + RM ;py d;py ) + (Rl;yy d;yy + RI;py d;py B (20)

D r i

Where:

Subscripts vv, refers to vent releases from the building ventilation

=

vents, including the Radwaste Facility Ventilation Vent and air ejectors; l

pv, refers to the vent releases from the process vent Dr the dose to the critical organ of the maximum exposed

=

member of the public in mrem 4

RMivv, RMipv = the cow milk pathway dose factor for ventilation vents or process vent release due to II3I, tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in mrem /yr per Curie /sec. Factors are listed in l 8, Critical Organ and Inhalation Dose Factors For Surry Riivy, Riipv the inhalation pathway dose factor for ventilation vents or

=

process vent release due to II3I, tritium, and from ll l

particulate-fonn radionuclides with half-lives greater than 8 l

days, in mrem /yr per Curie /sec. Factors are listed in 8 dm 6,n the release for ventilation vents or process vent of 1333,

=

tritium, and from all particulate-form radionuclides with half lives greater than 8 days in Curies l

l 1

~

VIRGINIA VPAP 2103 s OWER REVISION 3 PAGE 32 OF 125 the inverse of the number of seconds in a year 3.17 E-08

=

d. North Anna Dose Calculations I

Gaseous releases, not through process vent, are considered ground level and shall be included in the determination of b 11istorical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection to specific Station functions, such as containment purges, shall be t; sed in the estimates as appropriate.

1. The dose to the maximum exposed member of the public, attributable to gaseous effluents at and beyond the site boundary that coraain 133I, tritium, and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by:

i

= 3.17 E-08 [ [ R divy + R;py dipy l D

(21) iyy r

1 Where:

Subscripts vv, refers to vent releases from the building ventilation vent;

=

pv, refers to the vent releases from the process vent Dr the dose to the critical organ of the maximum exposed member

=

of the public in mrem Rivy, Ripv the cow-milk dose factor for ventilation vent or process vent

=

release due to 1131, tritium, and from all particulate-fonn radionuclides with half-lives greater than 8 days, in mrenVyr Rev.3 per Curie /sec. Factors are listed in Attachment 19 Critical Organ Dose Factors for North Anna dm by, the release for ventilation vent or prc;:ess vent of II33, tritium,

=

and from all particulate-form radionuclides with half-lives greater than 8 days in Curies 3.17 E-08 the inverse of ti number of seconds in a year

=

l

.. ~..

l VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 33 OF 125 l

6.3.5 Gaseous Radwaste Treatment L

llistorical data pertaining to the volumes and radioactive concentrations of gaseous ef0uents released in connection with specific Statico functions, such as containment purges, shall be used to calculate projected doses, as appropriate, i

a. Requirement

1. The Gaseous Radwaste Treatment System and the Ventilat on Exhaust i

Treatment System shall be used to reduce radioactive material m gaseous waste prior to its discharge when projected gaseous effluent air doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation, averaged over 31 days. (North Anna)

2. Appropriate portions of the Gaseous Radwaste Treatment System shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent icleases, l

from each unit to areas at and beyond the site boundary, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation, averaged over 31 days, 1

(Surry) l

3. The Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to its dischwge when the projected doses due to gaseous ef0uent releases, from each unit to areas at and beyond the site boundary, would exceed 0.3 mrem to the critical organ, averaged over 31 days.

4. Doses due to gaseous releases from the site shall be projected at least once per 31 days, based on the calculations in Steps 6.3.5.c.,6.3.5.d., and 6.3.5.e.

b. Action If gaseous waste that exceeds the limits in Step 6. 3.5.a. is discharged without ueatment, prepare and submit to the NRC within 30 days, a special report in accordance with VPAP 2802, Notification; and Reports, that includes:

1. An explanation why gaseous radwaste was being discharged without treatment, identification of any (noperable equipment or subsystems, and the reason for the inoperability.

l

2. Actions taken to restore the inoperable equipment to operable status.

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 34 OF 125 i

3. Summary description of actions taken to prevent recurrence,

c. Projected Gamma Dose

1. Determine D, the 31-day gamma air dose in the previous 31-day period, g

per Equation (18).

i

2. Estimate R, the ratio of the estimated volume of gaseous effluent in the present g

31-day period to the volume released during the previous 31 day period.

3. Estimate F, the ratio of the estimated noble gas effluent a;tivity in the prescat g

31 day period to the noble gas effluent activity during the previous 31-day period (pCi/ml).

i

4. Determine PD, the projected 31-day gamma air dose.

g PD

= - D (R x F, )

(22) 9 g

9 L

d. Projected lieta Dose

l. Determine D,, the 31 day beta air dose in the previous 31 days, t

per Equation (19).

2. Estimate R and F as in Steps 6.3.5.c.2. and 6.3.5.c.3.

g s

3. Determine PD, the projected 31 day beta air dose.

ti PDb"O@g xF )

( )

b 8

e. Projected Maximum Exposed Member of the Public Dose

1. Determine Dnm, the 31-day maximum exposed member of the public dose in the previous 31-day period, per Equation (20) or Equation (21), where Dr =

Dnw.

2. Estimate Fi, the ratio of the estimated activity from 1131, radioactive materials in particulate fomi with half lives greater than 8 days, and tritium in the present 31 day period to the activity of 1131, radioactive materials in particulate form with half lives greater than 8 days, and tritium in the previous 31 day period (pCi/ml).

l

..-n,,

,-,n,,

,-n..

-.,,,n._,-,,,,,,-,..._,.-w,

-,a,,-.-,r,.-,

,.e

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 35 OF 125 4

3. Determine PDena, the projected 31-day maximum exposed member of the public dose.

PD

=Dmax(R x F; )

(24) nm g

6.4 Total Dose 1.imit to Public From Uranium Fuel Cycle Sources 6.4.1 Hequirement The annual (calender year) dose or dose commitment to the maximum exposed member of the public due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or the critical organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).

)

3 6.4.2 Action i

a. If the calculated doses from release of radioactive materials in liqu'd or gaseous i

t effluents exceed twice the limits in Steps 6.2.3.a.,6.3.3.a., or 6.3.4.a., calculate, including direct radiation contribution from the units and from outside storage tanks, whether limL.a Step 6.4.1 have been exceeded.

b. If the limits in Step 6.4.1 have been exceeded, prepare and submit to the NRC within 30 days a special report in accordance with VPAP-2802, Notifications and l

Reports, that defines the corrective action to be taken to reduce subsequent releases and to prevent recurrence, and includes a schedule for achieving conformance with the limits. Special reports, as defined in 10 CFR 20.405c, shall include:

1, An analysis that estimates the radiation exposure (dose) to the maximum exposed member of the public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases covered by the report.

2. A description of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

3. If the estimated dose exceeds the limits in Step 6.4.1, and if the release condition that violates of 40 CFR 190 has not already been corrected, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

= - _ - -

- ~ - - - _

~ - -.

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 36 OF 125 1

6.5 Radiological Environmental Monitoring i

j 6.5.1 Monitoring Program j

a. Requirc nent l

1. The Radiological Environmental Monitoring Program shall be conducted as

]

specified in Attachments 20 or 21 Radiological Environmental Monitoring i

Program.

j

2. Samples shall be collected from specific locations specified in Attachment 22 i

or 23, Environmental Sample Locations.

3. Samples shall be analyzed in accordance with:

j

+ Attachment 20 or 21 requirements

. Detection capabilities required by.utachment 24 or 25, Detection Capabilities for Environmental Sample Analysis Guidance of the Radiological Assessment liranch Technical Position on a

Environmental Monitoring dated November,1979, Revision No.1 l

b. Action

{

l. If the Radiological Environmental Monitoring Program is nut being conducted as required in Step 6.5.1.a., report the situation in accordance with VPAP-2802, Rev.3 i

Notifications and Reports, by preparing and submitting to the NRC, in the Annual Radiological Environmental Operating Report required by Technical Specification (Surry Technical Specification 6.6.B.2 and North Anna Technical l

Specification 6.9.1.8), a description of the reasons for not conducting the j

program as required, and the plan for precluding recurrence.

i 4

4

~

-... ~,. -. - -

~. -....

-r,,,

,.,. _.....-4,-.

--.-..-.m

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 37 OF 125

2. If, when averaged over any calendar quarter, radioactivity exceeds the reporting levels of Attachment 26 or 27, Reporting Levels for Radioactivity Concentrations in Environmental Samples, prepare and submit to the NRC within 30 days a special report in accordance with VPAP 2802, Notifications gg and Reports, that:

+ Identifies the causes for exceeding the limits, and

+ Defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of Steps 6.2.3,6.3.3, and 6.3.4 When more than one of the radionuclides listed in Attachment 26 or 27 are detected in the sampling medium, the report shall be submitted if:

concentration (1) concentration (2) 2 LC)

(25) reporting level (1), reporting level (2) +

3. When radionuclides other than those listed in Attachments 26 and 27 are detected and are the result of plant effluents, the report shall x submitted if the potential annual dose to a member of the public is equal to or greater than the calendar year limits of Steps 6.2.3, 6.3.3, and 6.3.4. The report is not required if the measured level of radioactivity was not the result of plant effluents; however,in such an event, report and describe the condition in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, nev.3 Notifications and Reports.

4, if milk or fresh leafy vegetable samples are unavailable from one or more of the sample locations required by Attachment 20 or 21, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may the. be deleted from the monitoring program. Identify -

the cause of the unavailability of samples and identify the new locations for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report in accordance with VPAP 2802, Notifications and Reports, l ney,3 Include in the report a revised figure and table for tiie ODCM to reflect the new locations.

.__._J

VIRGINIA VPAP-2103 POWER REVISION 3 i

PAGE 38 OF 125 6.5.2 1.und Use Census

a. Requirement l

A land use census shall be conducted and shall identify within a distance of 8 km 4

(5 miles) the location in each of the 16 meteorological sectors of the following:

1

. Nearest milk animal l

. Nearest residence

• Nearest garden greater than 50 m2 (500 ft ) that produces broad leaf vegetation 2

1 The land use census shall be conducted during the growing season at least once i

j per 12 months using information that will provide the best results (e.g., door to-

]

door survey, aerial survey, local agriculture autlwrities). Land use census l

results shall be included in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.

l Rev.3 l

2. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors 4

wit:i ihe highest predicted deposition source strength (D/Qs) in lieu of the -

ganien census. Specifications for broad leaf vegetation sampling given in j 0 or 21 shall be followed, including analysis of control samples.

l

b. Actio.i

1. If a land use census identifies locations that yield a calculated dose or dose commitment greater than the values currently being calculated in Step 6.3.4.a.2, l

identify the new locations in the next Semiannual Radioactive Effluent Release Report in accordance with VPAP-2802, Notifications and Reports.

l Rev.3 I

4 I

i i

f 4

m I

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 39 OF 125

2. If a land use census identifies locations that yield a calculated dose or dose conunitment (via the same exposure pathway) 20 percent (Surry) or 25 percent

""*'3 (North Anna) greater than at a location from which samples are currently being obtained, add the new locations to the Radiological Environmental Monitoring Program within 30 days. Sampling locations, excluding the control station location, having the lowest calculated dose or dose commitments (via the same exposure pathway) may be deleted from the monitoring program after October 31 of the year in which this land use census was conducted. Identify new locations in the next Semiannual Radioactive Eff!" ant Release Report and include in the report revised figures and tables reflecting the new locations in Rev.3 accordance with VPAP-2802, Notifications and Reperts. [ Commitment 3.2.3]

6.5.3 Interlaboratory Comparison Program

a. Requirement Radioactive materials (which contain nuclides produced at the Stations) supplied as part of an Interlaboratory Comparison Program that has been approved by the NRC shall be analyzed.

b. Action

1. Analyses shall be performed as part of the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies (Cross Check) Program and include:

Program Cross Check of:

Milk 1UI, Gamma. K, Sr" and Sr*

131, g3 (Tritium), Sr" 3

Water Gross Beta, Gamma,1 and Sr* (Blind-any combinations of above radionuclides)

Air Filter Gross Beta, Gamma, Sr*

2. If analyses are not performed as required by Step 6.5.3.b., report in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Rev.3 Notifications and Reports, the corrective actions taken to prevent a recurrence.

.. J

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 40 OF 125

c. Methodology and Results

1. Methodology and results of the cross-check program shall be maintained in the contractor-supplied Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual, IWL-0032-361.

2. Results shall be reported in the Annual Radiological Environmental Monitoring Report in accordance with VPAP-2802, Notifications and Reports.

l Rev.3 6.6 Reporting Requirements 6.6.1 Annual Radiological Environmental Operating Report Routine Radiological Environmental Operating Reports covering the operatio i of the units during the previous calendar year shall be submitted prior to May 1 of eat 1 year.

A single submittal may be made for the Station. Radiological Environmental Operating Reports shall include:

e

a. Summaries, interpretations, and analysis of trends of results of radiological environmental surveillance activities for the report period, including:

s

. A comparison (as appropriate) with preoperational studies, operational controls, and previous environmental surveillance reports

• An assessment of the observed impacts of the plant operation on the environment

. Results of land use census per Step 6.5.2

b. Results of analysis of radiological environmental samples and of environmental radiation measurements taken per Step 6.5.1, Monitoring Program. Results shall be summarized and tabulated in the format of the table in the Radiological Assessm:nt Branch Technical Position on Environmental Monitoring.

1. If some individual results are not available for inclusion with the report, the report shall be submitted, noting and explaining reasons for missing results.

2. Missing data shall be submitted in a supplementary report as soon as possible,

c. A summary description of the radiological environmental monitoring program,

d. At least two legible maps covering sampling locations, keyed to a table giving distances and directions from the centerline of one reactor. One map shall cover stations near the site boundary; a second shall include more distant stations.

s

__________,._,__,____s_

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 41 OF 125

e. Results of Station particip v in in the Interlaboramry Comparison Program, per S ep 6.5.3.

f. Discussion of deviations fro - Station's environmental sampling schedule per 0 or 21.

g. Discussion of analyses in which the lower limit of detection (LLD) required by 4 or 25 was not achievable, 6.6.2 Semiannual Radioactive Effluent Release Report

a. Requiren.:nt Radioactive Effluent Release Reports covering operation of the units during the previous 6 months of operation shall lx submitted within 60 aays after January 1 and July 1 of each year. A single submittal may be made for the Station and should combine those sections that are common to both units. Radioactive Effluent Release Reports shallinclude:

1. A summary of quantities of radioactive liquid and gaseous effluents and solid waste released. Data shall be summarized on a quarterly basis following the format of Regulatory Guide 1.21, Appendix B.

2. An as:.essment of radiation doses to the maximum exposed members of the public due to the radioactive liquid and gaseous effluents released from the Station during the previous calendar year. This asressment shall be in accordance with Step 6.6.2.b. and shall be included only in Radion:tive Effluent Release Reports submitted within 69 days after January 1 of each year.

3. A list of unplanned releases from the site to unrestricted areas, during the reporting period, that exceeded the limits in Steps 6.2.1 and 6.3.1.

4. Majc r changes to radioactive liquid, gaseous, and solid waste treatment systems during the reporting period.

5. Cha.1ges to VPAP-2103, Offsite Dose Calculation Manual (see Step 6.6.4).

6. A listing of new locations for dose calculations or environmental monitoring identified by the land use census (see Step 6.5.2).

j

VIRGINIA VPAP-2103 POWER REV'SION 3 PAGE 42 OF 125

b. Dose Assessment

1. Radiatio 1 dose to individuals due to radioactive liquid and gaseous effluents from the Station during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109.

Population doses shall not be included in dose assessments.

2. The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station shall be incorporated with the dose assessment performed above. If the dose to the maximum exposed member of the public exceeds twice the limits of Steps 6.2.3.a.1,6.2.3.a.2,6.3.3.a.1, or 6.3.4.a.1, the dose assessment shall include the contribution from direct radiation.

NOTE: NUREG-0543 states,"There is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in confonnance with the EPA Uranium Fuel Cycle Standard,40 CFR Part 190."

3. Meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used for detennining gaseous pathway doses.

6.6.3 Annual Meteorological Data

a. Meteorological data collected over the previous year shall be in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

b. Meteorological data shall be retained in a file on site and shall be made available to the NRC upon request.

6.6.4 Changes to the ODCM Changes to the ODCM shall be:

a. Reviewed and approved by Station Nuclear Safety and Operating Committee (SNSOC) and Station Manager prior to implementation.

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 43 OF 125

b. Documented. Records of reviews shall be retained as Station records.

Documentation shallinclude:

1. Sufficient information to support changes, together with appropriate analyses or evaluations justifying changes.

2. A determination that a change will not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations, and will maintain the level of radioactive effluent control required by:

10 CFR 20.106 40 CFR 190 10 CFR 50.36a 10 CFR 50, Apper iix !

c. Submitted to the NRC in tim form of a complete, legible copy of the entire ODCM as a part of, or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

d. Submitted to the Management Safety Review Committee (MSRC) Coort aator.

[ Commitment 3.2.1]

e. Submitted to the NRC in accordance with VPAP-280', Notifications and Reports. lRev3 z

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 44 OF 125 7.0 RECORDS 7..

The following individual and packaged docurnents and copies d any related correspondence completed as a result of the performance or implementation of this procedure are records. They shall be subndtted to Records Management in accordance with VPAP-1701, Records Management. Prior to transmittal to Records Management, the sender shall assure that:

. Each record is packaged when applicable,

. QA p:ogram requiremerts have been fulfilled for Quality Assurance records,

. Each record is legible, completely filled out, and adequately identifiable to the item or activity involvel

. Each record is stanped, initialed, signed, or otherwise authenticated and dated, as required by this procedure.

7.1.1 Individual Records

. None 7.1.2 Record Packages

. Records of changes to the ODCM in accordance with Step 6.6.4 Records of meteorological data in accordance with Step 6.6.?

Records of sampling and analyues

. Records of radioactive materials and other effluents released to the environment J

. Records of preventive maintenance, surveillances, and calibrations 7.2 The following documents completed as a result of th m, : mentation of this procedure are not records and are not required to be transmitted to Records Management.

None i

._____--_-____--u

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 45 OF 125 A'ITACllMENT I (Page1of1)

SURRY RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minituum Instrument Operable Action Channels 1.

GROSS RADIOACTIVITY MONITORS PROVIDING

% s4 AND AUTOhtATIC TERMINATION " RELEASE (a) Liquid Radwaste Efiluent Line 1

1 (b) Radwaste Facility Liquid Efiluent Line

]

1 a

2.

GROSS BETA OR GAMMA RADIOACrlVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE (a) Circuhding Water Discharge Line 1

2 (b) Component Cooling Service Water Efiluent Line 4

2 3.

FLOW RATE MEASUREMENT DEVICES (a) Liquid Radwaste Efiluent Line 1

3 (b) Radwaste Facility Liquid Efiluent Line 1

3 ACTION 1:

If the number of operable channels is less than required, effluent releases shall be suspended.

ACTION 2:

If the number of operable channels is less than required, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal gamma emitters, as defined in Attachment 8 Surry Radioactive Liquid Waste Sampling and Analysis Program.

ACTION 3:

If the number of operable channels is less than required, effluent releases via this pathway shall be suspended.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 46 OF 125 A'lTACllMENT 2 (Page 1 of 2)

NORTil ANNA RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Miniinuin Instrument Operable Action Cliannels -

1.

GROSS RADIOACTIVITY. MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (a) Liquid Radwaste Efuuent Line i

1 2.

GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDlNG ALARM BUT NOT PROVIDING AUTOMATIC TFV" NATION OF RELEASE (a) service Water System Ef0uent Line l

1 (b) Circulating Water System Ef 0uent Line 1

4 3.

FLOW RAlli MEASUREMENT DEVICES (a) Liquid Radwaste Ef0uent Line 1

2 4.

CONTINUOUS COM"OSITE SAMPLERS AND SAMPLER FLOW MONITOR (a) Clarifier Efuuent Line 1

1 5.

TANK LEVEL INDICATING DEVICES (Note 1)

(a) Refueling Water Storage Tanks 1

3 (b) Casing Cooling Storage Traks 1

3-

. (c) PG Water Storage Traks (Note 2) 1 3

(d) Boron Recovery Test Tanks (Nete 2) 1 3

..m.

.m

1 i

VIRGINIA VPAP-2103 POWER REVISION 3 i

PAGE 47 OF 125 ATTACllMENT 2 (Page 2 of 2)

NORTil ANNA RADIOACTIVE LIQUID EFFI,UENT MONITORING INSTRUMENTATION ACTION 1:

If the number of operable channels is less than required, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least lx10 7 pCi/g or an isotopic radioactivity at a lower limit of detection of at least 5x10 7 pCi/g.

ACTION 2:

If the number of operable channels is less than required, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Design capacity performance curves generated in situ may be f

used to estimate flow.

A CflO N 3:

If the number of operable channels is less than required, liquid additions to this tank may continue provided the tank liquid level is estimated during allliquid additions to the tank.

1 ACTION 4:

If the number of operable channels is less than required, make repairs as soon as possible. Grab samples cannot be obtained via this pathway.

NOTE 1: Tanks included in this requirement are those outdoor tanks tha' c not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overtlows and surrounding area drains connected to the liquid radwaste treatment system.

l NOTE 2: This is a shared system with Unit 2.

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VIRGINI A.

VPAP 2103 POWER REVISION 3 PAGE 48 OF 125 NITACHMENT 3 (Page1of1)

SURRY RADIOCTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEII,IsANCE REQUIREMENTS Channel Channel Source Channel Channel DeScript. ion

'"" '"""I.

Check Check Calibration IeSt 1.

GROSS. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (a) Liquid Radwaste Effluent Line D

P R

Q l Rev.3 (b) Radwaste Facility Liquid EITiuent Line D

P R

Q l Rev.3 2.

GROSS BETA OR GAMMA RADIOACTIV-ITY MONITORS PROVIDING ALARM BUTNOT PROVIDING AUTOMATIC TER-MINATION OF RELEASE (a) Circulating Water Discharge Line D

M R

Q (b) Component Cooling Service Water Efflu-S M

R

-Q ent Line 3.

FLOW RATE MEASUREMENT DEVICES (a) Liquid Radwaste Eftluent Line DR N.A.

R N.A.

l Rev.3 (b) Radwaste Fauhty Liquid Efiluent Line DR N.A.

P.

N.A.

lRev3 i

j 1

VIRGINIA VPAP-2103.

POWER REVISION 3 PAGE 49 OF 125 I

i NI'TACilhiENT 4 (Page 1 of 2)

NORTil ANNA RADIOACTIVE LIQUID EFFLUENT h10NITORING l

INSTRUhlENTATION SURVEILLANCE REQUIREh1ENTS -

L Channel F

Channel Source Channel Channel Descript. ion

""C

""I Check Check Calibration i-feSt l

1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC f

TERMINATION OF RELEASE (a) Liquid Radwaste Effluent Line D

D R

Q (NOTE 1)'

2.

GROSS BETA OR G AMMA RADIOACTIV.

1 ITY MONITORS PROVIDING ALARM j

BUTNOTPROVIDING AUTOMATICTER-2 MINATION OF RELEASE l

(a) Service Water System Effluent Line D

_M R

Q (NOTE 2) l (b) Circulating Water System Efiluent Line D

M R

Q (NOTE 2)

I 3.

FLOW RATE MEASUREMENT DEVICES (a) Liquid Radwaste Efiluent Line D (NOTE 3)

N.A.

R Q

1 4.

CONTINUOUS COMPOSITE SAMPLERS l

AND SAMPLER 110W MONITOR j

(a) Clarifier Effluent Line N.A.

N. A.-

R N.A.

5.

TANK LEVEL INDICATING DEVICES (NOTE 6) l (a) Refueling Water Storage Tanks D (Note 4)

N.A.

R Q

(b) Casing Cooling Storage Tanks D (Note 4)

N.A.

.R Q

j (c) PG Water Storage Tanks (NOTE 5)

D (Note 4)

- N.A.

R Q

l (d) Boron Recovery Test Tanks (NOTE 5)

D (Note 4)

N.A.

R

-Q I-i

't 4

r

}

4 i

VIRGINIA VPAP-2103 -

POWER REVISION 3 PAGE 50 OF 125 A'lTACilM ENT 4 a

(Page 2 of 2) 1 NORTII ANNA RADIOACTIVE 1 IQUID EFFl UENT h10NITORING INSTRUMENTATION SURVEll.I.ANCE REQUIREMENTS NOTE 1: The Channel Functional Test shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a.

Instrument indicates measured levels above the alam1/ trip setpoint.

b. Instrument controls not set in operate mode.

NOTE 2: The Channel Functional Test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a.

Instrument indicates measured levels above the alann/ trip setpoint.

b. Instrument controls not set in operate mode.

NOTE 3: Channel Check shall consist of verifying indication of flow during periods of release.

Channel Check shall be make at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

NOTE 4: During liquid additions to the tank.

NOTE 5: This is a shared system with Unit 2.

NOTE 6: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

l l

i VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 51 OF 125 NITACllMENT 5 (Page1of1)

LIQUID INGESTION PATilWAY DOSE FACTORS FOR SURRY STATION UNITS 1 AND 2 Total Hody Ai Thyroid Ai GI 1 LI Radionuclide mremlhr mrern/hr mrem /hr j

pCi/mi pCi/mi pCi/mi 11-3 2.82E-01 2.82E-01 2.82E '

Na-24 4.57E-01 4.57E-01 4.57E-01 i

Cr-51 5.58Edo 3.34E-01 1.40E+03 2.16E44 -

Mn-54 1.35E+03 Fe-55 8.23E+03 -

2.03EMM 6.32E+05 Fe-59 7.27Ed4 1.22EMM-

- Co-58 1.35E+03 Co-60 3.82E+03 3.25E+N Zn-65 2.32E+05 3.23E+05 Rh-86 2.9 IE+02 1.23E+02 St-89 1.43E+02 8.00E+02 Sr-90 3.01EMM.

3.55E+03 Y-91 2.37E+00

-.89E+04 4

Zr-95 3.46E+00 '

1.62EMM Zr-97 8.13E-02 5.5 iE+N NN95 1.34E+02 1.51E+06 Mo-99 2.43E+01 2.96E+02 Ru-103 4.60E+01 1.25E+N Ru-106 2.01E+02 1.03E+05 Ag-110m 8.60E+02 5.97E+05 -

Sb-124 1.09E+02

- 6.70E-01 7.84E+03 Sb-125 4.20E+01

- 1.79E-01 1.94E+03 Te-125m 2.91E+01 6.52E+01 8.66E+02 Te-127m 6.68E+01 1.40E+02 1.84E+03 Te-129m 1.47E+02 3.20E+02 4.69E+03 -

Te-131m 5.71E+01 1.08E+02 6.80E+03 Te-132 1.24E+02 1.46E+02 6.24E+03 l-131 1.79E+02

-1.02E+05 8.23E+01 l

l-132 9.96E+00 9.96E+02 5.35E+00 -

1-133

- 3.95E+01 1.90E+04 1.16E+02.

1-134 5.40E+00 2.62E+02 1.32E-02 1-135 2.24E+01

4. ole +03 6.87E+01 Cs-134 1.33E44 -

2.85E+02 Cs-136 2.WE+03 3.21E+02 Cs 137 7.85EMG 2.32E+02 I

Cs-138 5.94E+00 5.12E-05 Ba-140 1.08E+02 3.38E+03 La-140 2.10E -

5.83E+04 Ce-141 2.63E-01 8.86E+03 Ce 143 4.94E-02 1.67EMM Ce-144 -

9.59E+00 6.N E+N Np-239 1.91E-03 7.11E+02 --

I i

I

,. ~ _ _ -

,4,...,,r.,_,,.,_.,,,

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 52 OF 125 ATTACilMENT 6 (Page 1 of 5)

NORTil ANNA LIQUID INGESTION PATIlWAY DOSE FACTOR CALCULATION UNITS 1 AND 2 1.0 Equation (6)

D = t F[f;C; A; (6-1) i where:

D = cumulative dose commitment to the total body or critical organ, from the liquid effluents for the period t,in mrem

= period for which C and F are averaged for all liquid releases, hours t

i F = the near field average dilution factor for C; during any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the average flow from the Station discharge structure to unrestricted areas fi = the individual dilution multiplication factor to account for increases in concentration of long-lived nuclides due to recirculation, listed on page 4 of this attachment. "fi"is the ratio of the total dilution flow over the effective dilution flow C = average concentration of radionuclide, i, in undiluted liquid effluent during the period, t, i

from any liquid releases,in pCi/ml A = the site related ingestion dose commitment factor to the total body or critical organ of an i

adult for each identified principal gamma and beta emitter listed on page 4 of this attachment, in mrem-ml per hr-Ci A; = 1.14 E405 (730/Dw+ 21 BF;/D ) DF; (6-2) a where:

1.14 E+05 = (1 E+06 pCi/pCi x 1 E+03 ml/kg)/8760 hr/yr, units conversion factor -

730 adult water consumption, kg/yr, from NUREG-0133

=

1

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 53 OF 125 A'ITACIIMENT 6 (Page 2 of 5)

NORTil ANNA LIQUID INGESTION PATilWAY DOSE FACTOR CALCULATION UNITS 1 AND 2 dilution factor from the near field area within one-quarter mile of the Dw

=

release point to the potable water intake for the adult water consumption.

D, includes the dilution contributions from the North Anna Dam to Doswell (0.73), the Waste Heat Treatment Facility (C /Cc), and Lake t

Anna Reservoir (Cg.C ). The potable water mixing ratio is calculated as:

L Rev3 x 0.73 )

(63) 1/(C /C )(C /CL ) x 0.73 = C /(CR L

C R

C where C,C and C are the respective concentrations for the considered 1

C L R

nuclide in the Discharge Channel, Waste Heat Treatment Facility (l.agoon) and the Reservoir. Calculation is per expressions 11.2-5,11.2-6, and 11.2-8 of the North Anna UFSAR t

the bioaccumulation factor for nuclide, i, in fish, pCi/kg per pCi/1, from BFi

=

Table A-1 of Regulatory Guide 1.109, Rev. I Da dilution factor for the fish pathway, calculated as 1/(C /Cc) where CL lRev3

=

L l

and Cc are the concentrations for the considered nuclide in the Discharge i

Channel and the Waste Heat Treatment Facility (Lagoon). Calculation is per Expressions 11.2-5, and 11.2-6 of North Anna's UFS AR DFi 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 i

- ~.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 54 0F 125 A'ITACllMENT 6 i

(Page 3 of 5)

NORTil ANNA LIQUID INGESTION PATilWAY DOSE FACTOR CALCULATION UNITS I AND 2

)

2.0 Equation (9)

Equation (6) is simplified for actual dose calculations by introducing:

i WASTE FLOW WASTE FLOW (6-4)

CIRC. (WATER) FLOW + WASTE FLOW CIRC. FLOW and CIRC. FLOW f = 1[FFECi'iVE DIL. FLOW; i

I

)

Effective dilution flow rates for individual nuclides "i" are listed on Attachmem 7, North Anna Liquid Pathway Dose Commitment Factors for Adults. Then the total released activity (Qi) for the considered period and the ith nuclide is written as:

Q; = t x C; x WASTE FLOW (6-6) and Equation (6) reduces to:

A.

D=[Q i EFF. DIL. FLOW.

I 7) 1 I

For the long lived, dose controlling nuclides the effective dilution flow is essentially the over (dam) flow rate out of the North Anna Lake system (i.e., the liquid pathway dose is practically independent from the circulating water flow rate. However, to accurately assess long range average effects of reduced circulating water flow rates during outages or periods of low lake water temperatures, calculations are based on an average of 7 out of 8 circulating water pumps running at 218,000 gpm = 485.6 cft/sec per pump.

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 55 OF 125 A'lTACilMENT 6 (Page 4 of 5)

NORTil ANNA LIQUID INGESTION PATilWAY DOSE FACTOR CALCULATION UNITS 1 AND 2 NOTE: The 218.000 gpm flow rate per Circulating Water pump is based on Reference 3.1.21.

The choice of seven Circulating Water pumps is considered realistic. Compared to j

this, the NAPS UFSAR, Chapter i 1.2 (Reference 3.1.18), contains an extreme conservative consideration based on the minimum flow in accordance with

, y,3 j

Reference 3.1.21 with only two Circulating Water pumps operating. Eve 1 at such a low flow rate, which cannot be sustained during power generation, liquid pathway I34 effluent dose factcrs increase only slightly for the dose controlling nuclides (i.e., Cs I37 19 percent, Cs 15 percent).

l By defining Bj = A / EFF. DIL. FLOW, the dose calculation is reduced to a two factor i

i 4

formula:

i j

D = [Q;x B; (6-8) i j

Values for Bi(mrem /Ci) and EFF. DIL. FLOWi are listed in Attachment 7.

l l

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e VIRGINIA VPAP-2103 i

POWER REVISION 3 j

PAGE 56 OF 125 1

A'ITACllMENT 6 f

(Page 5 of 5) l-NORTil ANNA LIQUID INGESTION PATIIWAY DOSE FACTOR CALCULATION UNITS 1 AND 2 i

Individual Dilution Totalliody Ai Critical Organ Aj Radionuclide Multiplication Factor mrem /hr mrem /hr l

(f )

pCi/ml pCi/mi i

H-3 14.9

6. lME+00 6.18EMX) 3 Na 24 1.0 3.7 IE+01 3.7IB+01 -

l Cr5l 1.7 1.10E+(K)

Mn-54 7.0 8.62E+02 4.52E+03 -

l Fe-55 11.3 1.30E+02 5.56E+02

{

Fe-59 2.2 9.47E+02 2.47E+03 Co-58 2.8 2.49E+02 1.I1E+02 Co-60 13.3 8.27E+02 3.75E+02 Zn-65 6.1 3.28E+(4 7.25E+(M Rb-86 1.5 3.53E+04 7.59E+04 l

Sr-89 2.3 8.70E+02 Sr-90 15.8 2.39E+05 Y 91 2.5 3.42E-01 j

Zr-95 2.7 2.98E-01 4.41E-0 I l Rev.3 I

Zr-97 1.0 1.50E-(M 3.27E-(4 l

Nt>-95 1.9 1.13E H)2 2.10E+02 l Rev.3 j

Mo-99 1.0 7.48E+(X) 3.93E+01 Ru-103 2.0 4.10E44X) 1 Ru 100 7.6 2.65E+0!

1 Ag 110m 6.2 4.94E+00 8.32E+00 i

Sb-124 2.6 4.37E+01 2.08E+00 Sh-125 11.4 2.4bE+01 -

1.lbE+00

{

Te-125m 2.5 3.23E+02 8.73E+02 Te-127m 3.7 7.82E+02 2.29E+(0 l

Te-129m 1.9 1.52E+03 3.58E+03 Te-131m 1.0 1.12E+02

-1.35E+02 4

Te-132 1.0 5.04E+02 5.37E+02 l 131 1.2 9.66E+01 1.69E+02 l

l-132 1.0 1.03E-01 2.95E-01 1-133 1.0 3.47E+00 1.14E+0!

l l-134 1.0 2.15E-02 6.00E-02 l-135 1.0 6.58E 01 1.78E+00 Cs-134 10.3 5.80E+05 7.09E+05 Cs-136 1.3 6.01E+04 8.35EMM Cs-137 15.8 3.45E+05 5.26E+05 j

Cs-138 1.0 9.18E-01 1.85E+00 Ba-140 1.3 2.65E+01 5.08E-01 i

La-140 1.0 4.47E-03 1.69E 4E

{

Ce-141 1.8 2.14E-02 1.89E-Ol j

Cc-143 1.0 1.35E-(M 1.22E+00

-j Ce 144 6.6 1.41E+00 1.10E+01 Np-239 1.0 5.13E-(4 9.31E-04

'j VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 57 OF 125 i

k A'ITACllMENT 7 (Page 1 of 1)

NORTil ANNA LIQUID PATIIWAY COSE COMMITMENT FACTORS FOR ADULTS B = A F / CIRC FLOW = A / Effective Dilution Flowi) l ney,3 i

i i Effective Dilution Flow Totalllody Ai Critical Organ Ai Radionuclide (cft/sec)

(mrem /Ci)

(mrem /Ci) 2 11-3 2.26E+02 2.tcE44 2.66E4M Na-24 3.39E+03 1.07E44 1.07E-(M

]

Cr.51 1.99E+03 5.44E4e N/A l

Mn-54 4.88E+02 1.73E-02 9.08E 02 Fe-55

3. ole +02 4.23E-03 1.81E-02 Fe-59 1.57E+03 5.93E-03 1.55E-02 l

Co-58 1.20E+03 2.(ME-03 9.10E4M Co-60 2.55E+02 3.18E-02 1,44 E-02 i

Zn 65 5 60E+02 5.74E-01 1.27E+00 i

kl>_86 2.34E+03 1.48E-01

3. l bE-01 Sr-S4 1.46E+03 5.84E-03 N/A 4

i

~

Trb)

2. I 6E+02 1.09E+01 N/A i

YM l.34E+03 2.50E4)6 N/A

{

Zr-95 1.27E+03 2.30E4)6 3.40E-06 l Rev.3 Zr 97 3.39E+03 4.33E-10 9.46E-10 3

7 >95 1.78E+03 6.24E4M

1. I6E-03 l Rev.3 Mo-99 3.30E+03 2.22E-05 1.17E4M Ru-103 1.68E+03 2.40E-05 N/A Ru-106 4.48E+02 5.80E44 N/A l

Ag-1IOm 5.52E+02 8.78E-05 1.48E-(M l

Siw124 1.32E+03 3.25E-04 1.55E-05 Sb-125 2.98E+02 8.10E-04 3.80E-05 I

Te-125m 1.35E+03 2.35E-03 6.35E-03 Te-127m 9.16E+02 8.37E-03 2.46E-02 Te-129m 1.82E+03 8.19E-03 1.93E-02 Te-13 Im 3.38E+03 3.27E-04 3.92E4M Te I32 3.27E+03 1.51E-03 1.61 E-03 1 131 2.94E+03 3.22E44 5.62E44 1-132 3.40E+03 2.98E-07 8.51E-07 I-133 3.39E+03

- 1.00E4)5 3.29E-05 I-134 3.40E+03 6.19E-08 1.73E-07 i

1-135 3.40E+03 -

1.90E-06 5.15E4b l

Cs-134 3.29E+02 1.73E+01 2.11E+01 i

Cs-136 2.62E+03 2.25E-01 3.12E-01 Cs-137 2.15E+02 1.57E+01 2.40E+0!

Cs-138 3.40E+03 2.65E-06 5.34E46 Ba 140 2.65E+03 9.83E-05 1.88E-06 La-140 3.36E+03 1.31E-08 4.94E-08 Cc-141 1.85E+03 1.14E-07 1.00E-06 j

Cc-143 3.37E+03 3.93E-10 3.55E4)6 Ce-144 5.14E+02 2.70E-05 2.10E4M Niw239 3.32E+03 1.5 IE-09 2.75E4)9

l VIRGINIA VPAv-2103 POWER REVISION 3 PAGE 58 OF 125 ATI'ACllMENT 8 (Page 1 of 3)

SURRY RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Sampling Minimum Analysis Type of Activity D

o LD Type Frequency Frequency Analysis

( Cihn!),(Note 1)

Principle Gamm 5 x 10'7 p

p Emitters (Note 3) l3I 4

(Each Batch)

(Each Batch) l 1 x 10 Dissolved and 4

Batch Releases ntrained Gases 1 x 10 (One B tch/M)

(Gamma Emitters)

(Note 2)

P M Composite H3 1 x 10-5 (Each Batch)

(Note 4)

Gross Alpha 1 x 10'7 89 and Sr*

5 x 10'8 P

Q Composite Sr (Each Batch)

(Note 4)

Fe55 1 x 104 E

Continuous W Composite 5

• 10' t rs

'o 6

y (Note 6)

(Note 6) 1131 4

1 x 10 Dissolved and Continuous M

Ennained Gases 1x W Releases Grab Sample (Gamma Emitters) 3 1 x 10 5 (Note 5)

Continuous M Composite H

(Note 6)

(Note 6)

Gross Alpha 1 x 10-7 89 and Sr*

5 x 10-8 Continuous Q Composite Sr 55 4

(Note 6)

(Note 6)

Fe 1 x 10 l

1

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 59 OF 125 A'ITACllM ENT 8 (Page 2 of 3)

SURRY RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM NOTE 1: For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD =

(8-1)

- I ^* )

E V = 2.22E+06 a Y

• e Where:

the "a priori" (before the fact) Lower Limit of Detection (as microcuries LLD

=

per unit mass or volume) (see 4.8) the standard deviation of the background counting rate or of the counting sb

=

rate of a blank sample as appropriate (as counts per minute, cpm)

E the counting efficiency (as counts per disintegration)

=

V the sample size (in units of mass or volume)

=

2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y

the fractional radiochemical yield (when applicable)

=

A the radioactive decay constant for the particular radionuclide

=

f l

At the elapsed time between the midpoint of sample collection and time of

=

counting Typical values of E, V, Y and At should be used in the calculation.

p The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not as an a "posteriori" (after the fact) limit for a particular measurement.

NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and appropri.'te methods will be used to obtain a representative sample for ana'ysis.

l

)

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 60 OF 125 A'ITACllMENT 8 (Page 3 of 3)

SURRY RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM NOTE 3: The principal gamma emitters for which the LLD specification Applies exclusively are the 1

l34 following radionuclides: Mn, Fe,CoS8, Co*, Zn65, McW, Cs

, Csl37, Cel41, and 54 59 Ce #4. This list does not mean that only these nuclides are to be detected and reported.

l Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with l

the above nuclides, shall also be identified and reported.

j NOTE 4: A coinposite sample is one in which the quantity of liquid sampled is proportional to the j

quantity of liquid waste discharged and for which the method of sampling employed results in a sp cimen that is representative of the liquids released.

NOTE 5: A continuous release is the discharge of liquid wastes of a indiscreie volume, e.g., from a volume of a system that has an input flow during the continuous release.

NOTE 6: To be representative of the quantities and concentrations of radioactive materials in liquid eftluents, composite sampling shall employ appropriate methods which will result in a specimen representative of the effluent release.

l t

t i

I 1

4 I

i

?

a i

4 v

v

~

4 VIRGINIA VPAP 2103 l-POWER REVISION 3 PAGE 61 OF 125 t

4 A'lTACilMENT 9 (Page1of1)

NORTil ANNA RADIOACTIVE LIQUID WASTESAMPLING AND ANALYSIS PROGRAM 4

i l

Liquid Release Sampling Minimum Analysis Type of Activity D

o I D Type Frequency Frequency Analysis

( Ci/ml),(Note 1)

Principle Gamma 5 x 10'7 p

p Emitters (Note 3) 4 (Each Batch)

(Each Batch) 1 1 x 10 131 4

Dissolved and Ba'ch Releases Ennained Gases 1xid (One B tch/M)

(Gamma Emitters)

(Notes 2 and 7)

P M Composite 113 1 x 10-5 (Each Batch)

(Note 4)

Gross Alpha 1 x 10~7 P

Q Composite Sr* and SrW 5 x 10~8 i

j ss 4

(Each Batch)

(Note 4)

Fe j x 19 j

Principal Gamma 5 x 10~7 Emitters (Note 6)

I33 4

Continuous W Composite I

1 x 10 Dissohed and (Note 6)

(Note 6)

Entrained Gases 1 x 10 5 (Gamma Emitters) 3 1 x 10-5 (Note 5)

' Continuous M Composite H

J (Note 6)

(Note 6)

Gross Alpha 1 x 10~7 2

Continuous Q Composite Sr" and Sr*

5 x 10'8 55 4

(Note 6)

(Note 6)

Fe 1 x 10 4

l VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 62 OF 125 ATTACilMENT 9 (Page 2 of 3)

NORTil ANNA RADIOACTIVE LIQUID WASTESAMPLING AND ANALYSIS PROGRAM NOTE 1: For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD =

(9-1)

-N'#*)

E

• V e 2.22E+06 e Y e

Where:

LLD the "a priori"(before the fact) Lower Limit of Detection as defined above

=

(as microcuries per unit mass or volume)(see 4.8) the standard deviation of the background i.ounting rate or of the counting sh

=

rate of a blank sample as appropriate (as counts per minute, cpm)

E the counting efficiency (as counts per disintegration)

=

V the sample size (in units of mass or volume)

=

2.22E406 = the number of disintegrations per minute (dpm) per microcurie Y

the fractional radiochemical yield (when applicable)

=

A the radioactive decay constant for the particular radionuclide

=

At the elapsed time between the midpoint of sample collection and time of

=

I counting Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori"(before 1 e fact) limit representing the capability of a 5

measurement system and not as an a "posteriori" (after the fact) limit for a particular measurement.

NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyxs, each batch shall be isolated, and then thoroughly mixed as the situation permits, to assure representative sampling.

i

J VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 63 0F 125 t

ATI'ACilMENT 9 (Page 3 of 3) t NORTII ANNA RADIOACTIVE LIQUID WASTESAMPLING AND ANALYSIS PROGRAM NOTE 3: The principal gamma emitters for which the LLD specificatiot.pplies exclusively are the I34 following radionuclides: Mn, Fe, CoM,Co",Zn65, mow 54 S9 Cs

, CsI37, CeI41, and Ce

. This list does not mean that cnly these nuclides are to be detected and reported.

344 Other peaks that are measura';L and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.

NOTE 4: A composite sample is one in which the quantity of liquid sampled is proportional to the quantity ofliquid waste discriarged and for which the method of sampling employed results in a specimen that is representative of the liquids released.

NOTE 5: A continuous release is the discharge of li aid wastes of a indiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

NOTE 6: To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the corr.posite sample to be representative of the effluent releases.

NOTE 7: Whenever the secondary coolant activity exceeds 10-5 pCi/ml, the turbine building sump pumps shall be placed in manual operation and samples shall tv ken and analyzed prior to release. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i

-,,+

r

--w r,

,,w.,

---

w,

,,--,-ems-

..n

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 64 OF 125 NITACllMENT 10 (Page 1 of 5)

SURRY RADIOACTIVE GASEOUS WASTE SAMPL.ING AND ANALYSIS PROGRAM Gaseous Release Sampling Minimum Analysis Type of Activity

' **5

• I t

n

)

Type Frequency Frequency Analysis g

Pri r to Release A. Waste Gas Prior to Release Principal Gamma a

x 10 Storage Tank (Each Tank)

Emitters (Note 2)

(

bS ple)

Principle Gamma 4

1 x 10 B. Containment Prior te Release Prior to Release Emitters (Note 2)

(

}

Purge (Each PURGE)

H3 4

1 x 10 G

C. Ventilation Weekly Princip! Gamma 1 x 10'4 WeektY (1) Process vent (Grab Sample)

Emitters (Note 2)

(2) Vent Vent #1 3

(3) Vent Vent #2 (Note 3)

(Note 3)

H 1 x 10 '

(4)SRF Vent Continuous Weekly (Note 5) gi31 1 x 10-12 (Note 4)

(Charcoal Sample)

Continuous Weekly (Note 5)

Principal Gamma 1 x 10'11 D. All Release.

(Note 4)

Particulate Sample Emitter (Note 2)

Con ""

Types as listed Cm s te Gross Alpha I x 10-11

' e 4)

Particulate Sample in A, B,and C Quarterly

[t Composite Sr and Sr 1 x 10-"

89 90 4)

Particulate Continuou.s e Gases Gmss 4

Noble Gr.s Monitor 1 x 10 (Note 4)

Beta and Gamma Principle Gamma 4

1 x 10 E. Condenser Air Weekly Weekly Emitters (Note 2) r mple 3

4-Ejector (Note 3)

H 1 x 10

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 65 OF 125 A'ITACilMENT 10 (Page 2 of 5)

SURRY RADIOACTIVE GASEOUS WASTE SAMPLING AND ANA13 SIS PROGRAM er nto Gaseous Release Sampling Minimum Analysis Type of Activity g

pev 3 1ype Frequency Frequency Analys,is

( Ci/ml),(Note 1)

Principle Gamma 1

10'4 Prior in R+ase Prior to Release Emitters 3

4 (Grab Sample)

(Ench Release) 11 1 x 10 Continuous Charcoal Sample 3:31 1 x 10-1I F. Containment (Note 4)

(Note 6)

Continuous Particulate Sample Principal Gamma 1 x 10.to

""E ""E "

(Note 4)

(Note 6)

Emitter (Note 2) surization Composite Continuous Particu! ate Sample Gross Alpha 1 x 10-10 1

(Note 4)

(Note 6)

Continuous Composite 89 Particulate Sample Sr and Sr90 1 x 1010 (Note 4)

(Note 6)

+

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 66 OF 125 ATI'ACIIMENT 10 (Page 3 of 5)

SURRY RAl)IOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM NOTE 1: For a particular measurement system (which may include radiochemical separation):

4.66 s b LLD -

(10-1)

E V + 2.22E+06 Y

• e (731)

Where:

LLD the "a priori"(before the fact) Lower Limit of Detection as defined above

=

(as microcuries per unit mass or volume) (see 4.8).

the randard deviation of the btekground counting rate or of the counting sb

=

rate of a blank sample as appropriate (as counts per minute, epm).

E the counting efficiency (as counts per disintegration).

=

V the sample size (in units of mass or volume).

=

2.22E+06 = the number of disintegrations per minute (dpm) per microcurie.

Y the fractional radiochemical yield (when applicable).

A the radioactive decay constant for the particular radionuclide.

=

At the elapsed time between the midpoint of sample collection and time of

=

counting.

Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori"(before the fact) limit representing the capability of a measurement system and not as an a "posteriori" (after the fact) limit for a particular measurement.

VIRGINIA VPAP.2103 POWER REVISION 3 PAGE 67 OF 125 ATTACllMENT 10 (Page 4 of 5)

SURRY RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr87, Kr88 yel33, yel33rn yel35, yel35ni I38

, and Xe for gaseous emissions and Mn, Fe, Co,Co*,Zn65, yow 54 59 S8 I34

,Cs

,CsI37, Ce34I l44 and Ce for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other nuclides with half lives greater than 8 days, that are measurable and identifiable at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.

NOTE 3: Sampling and analysis shall also be performed following shutdown, start-up, and whenever a thermal power change exceeding 15 percent of the rated thermal power occurs within any oue-hour period, when I3I a.

Analysis shows that the dose equivalent I concentration in the primary coolant has increased more than a factor of 3; and

b. The noble gas activity monitor shows that effluent activity has increased by more than a factor of 3.

NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the period covered by each dose or dose rate calculation made in accordance with Steps 6.3.1, 6.3.3, and 6.3.4.

NOTE 5: Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, start-up or thennal power change exceeding 13 percent of rated thermal power in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of charging. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the correspondnig LLDs may be increased by a factor of 10. This requirement applies if:

y A

131 Analysis shows that the dose equivalent 1 concentration in the primary coolant has a.

increased by a factor of 3; and

b. Noble gas monitor shows that effluent activity has increased more than a factor of 3.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 68 OF 125 ATTACilMENT 10 (Page 5 of 5)

'JRRY RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM NOTE 6: To be representative of the quantities and concentrations of radioactive materials in gaseous effluents, composite sampling shall employ appropriate methods which will result in a specimen representative of the effluent release.

4

\\

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 69 OF 125 ATTACllMENT 11 (Page 1 of 4)

NORTil ANNA RADIOACTIVE GASEOUS WASTE SAMPl.ING AND ANALYSIS PROGRAM Gaseous Release Sampling Minimum Analysis Type of Activity g

Type Frequency Frequency Analys,s i

( Ci/ml),(Note 1)

A. Waste Gas Pri r to Release Principal Gamma 4

E Tn 1 x 10 Storage Tank

("

Grab Sample) 1 Principle Gamma 4

l 10

11. Containment Prior to Release Prior to Release Emitters (Note 2)

I Purge (Each PURGE)

H3 1 x 10-6 G

p C. Ventilation Monthly Principle Gamma 4

1 x 10 (1) I'rocess vent (Grab Sample)

Monthly Emitters (Note 2)

(2) Vent Vent A (Notes 3,4, and 5)

(Note 3)

H3 4

1 x 10 '

(3) vent ventit Continuous Weekly g131 1 x 10-12 (Note 4)

(Charcoal Sample)

Continuous Weekly IMncipal Gamma 1 x 10'll D. All Release (Note 4)

Particulate Sample Emitter (Note 2) th C tinuous Types as listed

(,

posie Gross Alpha 1 x 10'11 Particulate Sample in A,11, and C Quarterly Composite Sr" and Sr*

I x 10'll

(

Particulate Continuous e Gases Gross Noble Gas Monitor 1 x 10-6 (Note 4)

Beta or Gamma E. Condenser Air Principle Gamma 4

1 x 10 Ejector / Steam Weekly Weekly Emitters (Note 7)

Generator Grab Sample 3

4 H

1 x 10 lilowdown Vent (Note 6) l gev,3 F. Containment Principle Gamma 1

10'4 Vacuum Steam Prior to Release Prior to each Emitters (Note 2)

Ejector (llogger)

(Grab Sample)

Release H3 1 x 10-6

l VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 70 OF 125 ATI'ACllMENT 11 (Page 2 of 4)

NORTIl ANNA RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM NOTE 1: For a particular measurement sys.un (which may include radiochemical sepcration):

4.66 s b LLD =

(11-1)

- S ^*)

E

• V e 2.22E+06

• Y

• e Where:

LLD the "a priori"(before the fact) Lower Limit of Detection as defined above

=

(as microcuries per unit mass or volume) (see Subsectior. 4.8) the standard deviation of the background counting rate or of the counting sb

=

rate of a blank rample as appropriate (as counts per minute, cpm)

E the counting efficiency (as counts per disintegration)

=

V the sample size (in units of mass or volume)

=

2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y

the fractional radiochemical yield (when applicable)

=

A the radioactive decay constant for the particular radionuclide

=

At the elapsed time between the midpoint of sample collection and time of

=

counting Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori"(before the fact) limit representing the capability of a measurement system and not as an a "posteriori" (after the fact) limit for a particular measurement.

l 1

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 71 OF 125 g

NITACllMENT 11 (Page 3 of 4)

NORTil ANNA RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr*7, Kr,Xel33, xcl33m, xel35, Xe135m, and XeI38 88 for 54, Fe*, Cos8,Co*,Zn65, gg99 I34 l37 I4I I44 gaseous emissions and Mn

, Cs

.Cs

, Ce and Ce for particulate emissions. This list does not mean that only these nuclides are to be detected and r: ported. Other peaks that are measurable and identifiable, at levels exceedi;.g the LLD, together with the above nuclides, shall also be identified and reported.

NOTE 3: Sampling and analysis shall also be perfonned following shutdown, start-up, and whenever a thermal power change exceeding 15 percent of the rated thermal power occurs within any one-hour period if:

I3I a.

Analysis shows that the dose equivalent I conc ntration in the primary coolant is greater than 1.0 pCi/gm; and

b. The noble gas activity monitor shows that effluent activity has increased by more than a factor of 3.

NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the period covered by each dose or dose rate calculation made in accordance with Steps 6.3.1,6.3.3, and 6.3.4.

NOTE 5: Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be perfonned at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, start-up or thennal power change exceeding 15 percent of rated thermal power in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of charging. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if:

I3I

a. Analysis shows that the dose equivalent I concentration in the primary coolant is greater than 1.0 pCi/gm and;

b. Noble gas monitor shows that effluent r.ctivity has increased more than a htor of 3.

a

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 72 OF 125 j

i NITACilMENT 11 (Page 4 of 4) l NORTil ANNA RADIOACTIVE GASEOUS 'WAS1E SAMPLING AND ANAIJSIS PROGRAM 5

NOTE 6: Whenever the secondary coolant activity exceeds 10 5 pCi/ml, samples shall be obtained l

and analyzed weekly. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity j

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 NOTE 7: The principal gainma emittere for which the LLD specitication applies exclusively are the j

following radionuclides: Kr, Kr88, Xel33, Xel33'",Xe135, xe135:n, and Xel38 for 87 j

gaseous emissions. This list does not mean that only these nuclides are to be detected and

)

reported. Other peaks that are measurable and identifiable, at levels exceeding the LLD l

foge*her with the above nuclides, shall also be identified and reported.

e l

I a

ll 1

i d

4 a

'd

--.v.

, ~ _ -

~~,,..-,..y_.___-,

~..., -,.

,,-.~...-..,m.

m.

,.,....--.---ve--,

VIRGINIA VI'Al'-2103 l'OWER REVISION 3 PAGE 73 OF 125 A'ITACilMENT 12 (Page 1 of 3)

GASEOUS EFl?LUENT DOSE FACTORS FOR SURRY (Onmrna and lieta Dose Factors) 3 yjQ = 6.0E-05 sec/m at 499 meters N Direction Dose Factors for Ventilation Vent K;yy L;yy Miyy Niyy Noble Gas Total llody Skin Gamma Air lieta Air Radionuclide mrem /yr mrem /yr mradlyr mradlyr Curie /see Curie /sec Curie /sec Curie /see Kr-83m 4.54E+00 1.16E403 1.73EM)4 Kr-85m 7.02E+04 8.76E+04 7.38E+04 1.18E+05 Kr 85 9.66E402 8.04E+04 1.03E+03 1.17EM)5 Kr-87 3.55E405 5.84EM)5 3.70E+05 6.18E405 Kr-88 8.82E+05 1.42E+05 9.12E+05 1.76E+05 Kr 89 9.96E+05 6.06EM)5 1.04E+06 6.36E+05 C

Kr.90 9.36E+05 4.37E+05 9.78E+05 4.70E+05 Xe-131m 5.49E+03 2.86E+04 9.36EM)3 6.66E+04 Xe-133m 1.51E+04 5.96E+04 1.96E+04 8.88E+04 Xe-133 1.76E404 1.84E+04 2.12E+04 6.30E+04 Xe 135m 1.87E+05 4.27E+04 2.02E405 4.43E+04 Xe 135 1.09E+05 1.12E405 1.15E+05 1.48E+05 Xe-137 8.52E+04 7.32E+05 9.06E+04 7.62E405 Xe-138 5.30E+05 2.48E+05 5.53E+05 2.85E+05 Ar-41 5.30E+05 1.61E+05 3.58E405 1.97E+05

4 VIRGINIA VPAP 2103 i

POWER REVISION 3 l

PAGE 74 OF 125 I

A'ITACilMENT 12 (Page 2 of 3)

GASEOUS EFFl.UENT DOSE FACTORS FOR SURRY (Gamma and 11 eta Dose Factors) 3 j

yjQ = 1.0E-06 sec/m at 644 meters N Direction Dose Factors for l'rocess Vent Nv Lv Mipv Ky ip i

ip Total Slody Skin Gamma Air Beta Air Noble Oas j

Radionuclide mrem /yt mrem /yr mradlyr mrad /yr j

Curie /sec Curic/sec Curie /sec Curie /sec l

Kr 83n-7.56E-02 1.93E+01 2.88E+02 I

Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 I

Kr-85 1.61 E+0!

1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E403 6.17E+03 1.03E+04 i

Kr-88 1.47E404 2.37E+03 1.52E+04 2.93E+03 I

Kr-89 1.66E+04 1.01E404 1.73E+04 1.06E+04 j!

Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe 131m 9.15E+01 4.76E+02 1.56E+02 1.11E403 1

i Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 f

Xe-135m 3.12E+03 7.l l E+02 3.36E+03 7.39E+02 Xe 135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe 137 1.42E+03 1.22E+04 1.51 E+03 -

1.27E+04 -

Xc 13X 8.83E+03 4.13E+03

- 9.21E403 4.75E+03 -

Ar-41 8.84E403 2.69E+03 9.30E+03 3.28E+03

.,---,nr-

---v.,

y

l 1 noisiveR,901 1 ediuG yrotalugeR ot gnidrocca rotcaf esod rof atad oN DN 70+E261 80+E57 9 131l DN DN 441-cC DN DN 141-eC l

DN DN 041-alI DN DN 731-sC DN DN 631-sC DN DN 431 -sC 30+E33 6 504E08 3 m921 eT 30+E70 6 5i2 463 m721-eT DN ON m01 l-g A DN DN 601 uR DN DN 301-uR DN.

DN 59-bN DN DN 59 rZ DN DN 19-Y

~

3 DN DN 09-tS DN DN 68-bR DN DN 76-nZ i

DN DN 06-oC j

DN DN 85 oC DN DN 95-eF

~

DN DN 45-nM l

10+E55 8 30+E315 15-rC 0(+E21 1 40+E57 6 3-11 ces/eiruC ces/eiruC I

tnerm rv/merm edilcunoidaR f

rv/ pi vP vviP I

l noitewiD S sretem 446 ta m/ces 60 E01 = Q/X tneV ssecorP l

3 noitceriD N sretem 994 ta m/ces 50-E0 6 = Q/X tneV noitalitn%

{

3

)srotcaF esoD yawhtaP noitalahnI(

)

i YRRUS ROF SROTCAF ESOD TNEU,IFFE SUOESAG l

)3 fo 3 egaP(

{

21 TNEMliCATTA l

i 521 FO 57 EGAP 2

3 NOISIVER REWOP i

3012 PAPV AINIGRIV

)

i VIRGINIA VPAP 2103 I'OWER REVISION 3 l

PAGE 76 OF 125 NITACllMENT 13 (Page 1 of 3) 1 GASEOUS EFFl.UENT DOSE FACTORS FOR NORTil ANNA 4

(Gamma and Beta Dose Factors) 3 y/Q = 9.3E-06 sec/m at 1416 meters SE Direction 3

Dose Factors for Ventilation Vent i

1

{

K yy 1.jy y Miyy Njyy i

Noble Gas Total flody Skin Gamma Air lleta Air i

Radionuclide mrem /yr mrem /yr mrad /yr mradlyr j

Curie /see Curie /see Curie /sec Curie /sec l

Kr.83m 7.03E-01 1.79E+02 2.68EM)3 a

j Kr 85m INE+04 1.36E404 1.14E404 1.83EM14 Kr-85 1.50E+02 1.25E+04 1.60E+02 1.81E+04 l

Kr-87 5.51 E+04 9.05E+04 5.74E404 9.58E+04 Kt-88 1.37E405 2.20EM)4 1.41 E+05 2.72E+04 Kr-89 1.54E+05 9.39E+04 1.61E+05 9.86E+04 Kr-90 1.45E+05

- 6.78E+04

- 1.52E+05 7.28E+04 i

Xe-131m 8.51 E+02 4.43E+03 1.45E+03 -

1.03E+04 Xe-133m 2.33E+t)3 9.24E+03 3.04E+03 1.38E+04 Xe-133 2.73E+03 2.85E+03 3.28E+03 9.77E+03 4

Xe-135m 2.90E+04 6.61 E+03

- 3.12E+04 6.87E+03 Xe-135 1.68E+04 1.73E+04 1.79E+04 2.29E+04 i

Xe-137 1.32E+04 1.13E+05 1.40E404 1.18E+05 Xe-138 8.21 E+04 3.84E+04

- 8.57E+04 4.42E+04 Ar-41 8.22E+04 2.50EM)4 8.65E+04 3.05E+04 4

i

,e r-,-a y--

e--

,-e--,..,-r,-..,,,

.a

.n, w,

w

VIRGINlA VPAP 2103 POWER REVISION 3 PAGE 77 OF 125 A'ITACllMENT 13 (Page 2 of 3)

GASEOUS EFFI,UENT DOSE FACTORS FOR NORTil ANNA (Gamma and Beta Dose Factors) 3 yjQ = 1.2E-06 sec/m at 1513 meters S Direction Dose Factors for Process Vent Kv L;py Mv Nipv ip ip Noble Gas Total Body Skin Gamma Air Heta Air Radionuclide mrem /yr mmu/n inrad/v1 mrad /yr Curie /see Curie /see Curie /sec Curie /see Kr-83m 9.07E-02 2.32E+01 3.46E+02 Kr 85m 1.40EM)3 1.75E+03 1.48E+03 2.36E+03 Kr 85 1.93E+01 1.61E+03 2.06E+01 2.34E+03 Kr-87 7.10E403 1.17E+04 7.40E+03 1.24EM)4 Kr-88 1.76E+04 2.84E+03 1.82E+04 3.52E+03 Kr-89 1.99E+04 1.21EM)4 2.08E+04 1.27E+04 Kr-90 1.87E+04 8.75E+03 1.96E+04 9.40E+03 Xe-131m 1.1OE+02 5.71E402 1.87E+02 1.33EM)3 Xe-133m 3.OlEM)2 1.19E+03 3.92E+02 1.78E+03 Xe-133 3.53E+02 3.67 E+02 -

4.24E+02 1.26E+03 Xe-135m 3.74E+03 8.53EM12 4.03E+03 8.87E+02 Xe-135 2.17E+03 2.23EM)3 2.30E+03 2.95E+03 Xe 137 1.70E403 1,46E+04 1.81E+03 1.52E+04 Xe 138 1.06EM)4 4.96E+03 1.1 IE+04 -

5.70E+03 -

Ar-41 1.06E404 3.23E+03 1.12E+04 3.94E+03

I i

VIRGINIA VPAP-2103 POWER REVISION 3 i

PAGE 78 OF 125 i

NITACllMENT 13 (Page 3 of 3) j GASEOUS EFFl.UENT DOSE FACTORS FOR NORTil ANNA 1'

(Inhalation Pathway Dose Factors) 3 l

Ventilation Vent yjQ = 9.3E 06 sec/m at 1416 meters SE Direction 3

i Process Vent yjQ = 1.2E-06 sec/m at 1513 meters S Direction Pv Pjyy ip 3

i Radionuclide mrem /yr inrem/vr j

Curie /sec Curie /sec Il-3 1.05E404 1.35E+03

)

Cr-51 7.95E+02 1.02EW2 Mn 54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND

~

Zn 65 ND ND

~

Rb 86 ND ND Sr-90 ND ND Y 91 ND ND j

Zr-95 ND ND Nb-95 ND ND j

]

Ru 103 ND ND j

Ru-106 ND ND Ag 110m ND ND Te 127m 5.64E+04 7.28E+03 Tc 129m 5.88E+04 7.59E+03 Cs-134 ND ND I

Cs-136 ND ND Cs-137 ND -

ND Ha-140 ND ND Cc-141 ND ND 4

Ce-144 ND ND l 131 1.51 E+08 1.95E+07 ND - No data for dose factor according to Regulatory Guide 1.109, Revision i

-.iwy.w---.

r-

---,-,.---,w,.

,,yy,z.-r,

-c, e,

---w-w,

-r,

+~.wn-

2 VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 79 OF 125 l

NITACilMENT 14 S

(Page I of 2) l SURRY RADIO ACTIVE G ASEOUS EFFl.UENT MONITORING INSTRUMENTATION i

MINIMUM INSTRUMENT OPERAlll.E ACTION 1

CilANNEl S i

1. PROCESS VENT SYSTEM (a)

Noble Gas Activity Monitor - Providing Alarm and j

j Automatic Tennination of Release (b) lodine Sampler 1

2 (c) Particulate Sampler 1

2 (d) Process Vent Flow Rate Monitor 1

3 i

(e)

Sampler Flow Rate Measuring Device 1

3

2. CONDENSER 'IR EJECTOR SYSTEM (a) Gross Activity Monitor 2 (one per unit) 1 (b) Air Ejector Flow Rate Measurim Device 2 (one per unit) 3

3. VENTILATION VENT SYSTEM (NOTE 1)

(a)

Noble Gas Activity Monitor i

I (b) lodine Sampler 1

2 (c)

Particulate Sampler 1

2 (d) Ventilation Vent Flow Rate Monitor 1

3 (e)

Sampler Flow Rate Measuring Device 1

3 NOTE 1: One each for the Ventilation Vent I and 2 and Radwaste Facility Ventilation Vent effluent points i

l U

i i

VIRGINIA VPAP 2103 i

POWER REVISION 3 PAGE 80 OF 125 I

i A'ITACllMENT 14 (Page 2 of 2) l l

SURRY RADIOACTIVE G ASEOUS EFFl.UENT MONITORING INSTRUMENTATION j

i ACTION 1:

If the number of operable channels is less than required, effluent releases via this path i

t may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these

}

samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

)

ACTION 2:

If the number of operable channels is less than tequired, effluent releases via the cffected path may continue provided samples are continuously collected within one hour with auxiliary sampling equipment as required in Attachment 10.

f A CrlO N 3:

If the number of operable channels is less than required, effluent releases via this j

pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i k

i n

l 4

1

.me-

..,v

_m,...,.-,, -,,.,.. - - -, -

-..r.

,,,.m.

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

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

i l

VIRGINIA VPAP-2103 4

POWER REVISION 3 PAGE 81 OF 125 j

i j

NITACllMENT 15 l

(Page 1 of 2) l NORTil ANNA RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION j

MINIMUM INSTRUMENT OPERAlli,E ACTION

]

CilANNEl S

1. PROCESS VENT SYSTEM j

(a)

Noble Gas Activity Monitor - Providing Alarm and j

,, 4 Automatic Termination of Release g

(b) lodine Sampler 1

2, 5 (c)

Particulate Sampler 1

2, 5 l

(d) Process Vent Flow Rate Monitor 1

1

)

)

(e)

Sampler Flow Rate Measuring Device i

1

2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor 1

3 (b) Flow Rate Measuring Device 1

1 i

3. VENTILATION VENT SYSTEM (Shared with Unit 2)

(a)

Noble Gas Activity Monitor 1 (NOTE 1) 2 (b) lodine Sampler 1 (NOTE 1) 2 i

(c)

Particulate Sampler 1 (NOTE 1) 2 i

(d) Flow Rate Monitor 1 (NOTE 1) 1 (e) Sampler Flow Rate Measuring Device 1 (NOTE 1) 1 NOTE 1: One per vent stack t

l y

w g_g w-y]np 4

.,y-.

-*w----

w

,.+,e

~,-v g-,

,-,y-.

,y m

m

+

j i

j VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 82 OF 125 j

A'lTACilMENT 15 i

(Page 2 of 2) i NORTil ANNA RADIOACTIVE GASEOUS EFFI,UENT MON!TORING l

INSTRUMENTATION l

ACrlON 1:

If the number of operable channels is less than required, effluent releases via this path i

may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

A CrlO N 2:

If the number of operable channels is less than required, effluent releases via 'his pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and l

these samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i 3

ACTION 3:

If the number of opeiable channels is less than required, effluent releases via this l

pathway may continue provided the frequency of the grab sampla required by

]

Technical Specification requirement 4.4.6.3.b is increased to at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> -

and these samples are analyzed for gross activity or gamma isotopic activity within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

A C rlO N 4:

If the number of operable channels is less than required, the contents of the Waste Gas Decay Tanks may be released to the environment provided that prior to initiate the i

release:

At least two independent samples of the tank's contents are analyzed, and a.

b. At least two technically qualified members of the Station Staffindependently verify the release rate calculations and discharge valve lineup; i

Otherwise, suspend release of Waste Gas Decay Tank effluents.

A C rlO N 5:

If the number of operable channels is less than required, effluent releases from the Waste Gas Decay Tanks may continue provided samples are continuously collected with auxiliary sampling equipment as required in Attachment 11.

J J

?

4

--e.,%u,,-.

v 7-

,mw,-we-r

.--.-.9,.-,,

-w--c, e- - *.

e e

---w

-m*

r--,

VIRGINIA VI'Al' 2103 POWER REVISION 3 j

PAGE 83 OF 125 A'I'I'ACllS1ENT 16 (Page 1 of 1)

SURRY RADIOACTIVE G ASEOUS EFFl UENT $10NITORING INSTRUh1ENTATION SURVEll.l.ANCE REQUIREh1ENTS CIIANNEl.

CilANNEl.

CilANNEl. SOURCE CIIANNEl.

,,'l ^ I' DESCitlPTION CIIECK CilECK CAllllitATION l.

PROCESS VENT SYSTEh1 (a)

NoNe Oas Activity hionitor -

Providing Alann and Automatic D

hi,

• R Q

Tennination of Release (b) lodine Sampler W

N. A.

N. A.

N. A.

(c)

Paniculate Sampler

.W N. A.

N. A.

N. A.

(d)

Process Vent flow Rate hionitor D

N. A.

R N. A.

(c)

Smupler llow Rate hicasuring D

N. A.

SA O

Device 2.

CONDENSER AIR EJECTOR SYS-TEN 1 (a)

Gross Activity hionitor D

h1 R

Q (b)

Air Ejector Flow Rate hicasuring D

N. A.

R N. A.

Device

3. VENTILATION VENT SYSTEh!

(a)

Noble Gas Activity hionitor D

h1 R

Q (b) lodine Sampler W

N. A.

N. A.

N. A.

(e)

Particulate Smupler W

N. A.

N. A.

N. A.

(d)

Ventilation Vent ilow Rate hion-D N. A.

R N. A.

itor (c)

Smnpler Flow Rate hicasuring D

N. A.

SA Q

Device

• Prior to each Waste Gas Decay Tank release

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 84 OF 125 A'ITACith1ENT 17 (l' age 1 of 2)

NORTil ANNA RADIOACTIVE GASEOUS EFFI,UENT hlONITORING INSTRUh1ENTATION SURVEll,1 ANCE REQUIREh1ENTS g?g I'

CIIANNEl, Cil ANNEl, SOURCE CilANNEl.

p

,g' DESCRIPTION CilECK CilECK CAllilRATION

,,,pg.g, 1.

PROCESS VENT SYSTEh!

(a)

Noble Gas Activity hionitor-Pmviding Alann and Automatic D

l' R

Q (NOTE 1)

Temiination of Release (b) lodine Sampler W

N. A.

N. A.

N. A.

(c)

Particulate Sampler W-N. A.

N. A.

N. A.

(d) Process Vent Flow Rate hionitor D

N. A.

R Q

(c)

Sampler Flow Rate hicasuring D (NOTE 3)

N. A.

SA N. A.

Device 2.

CONDENSER AIR EJECTOR SYS-TEh1 (a)

Noble Gas Activity hionitor D

h1 R

Q (NOTE 2)

(b)

Flow Rate hicasuring Device D

N. A.

R N. A.

3. VENTILATION VENTSYSTEht (Shared with Unit 2)

(a)

Noble Gas Activity hionitor D

h1 R

Q (NOTE 2)

(b) lodine Sampler W

N. A.

N. A.

N. A.

(c)

Particulate Sampler W

N. A.

N. A.

N. A.

(d)

How Rate hionitor D

N. A.

R Q.

(c)

Sampler Flow Rate hicasuring D(NOTE 3)

N. A, SA N. A.

Device

_J

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 85 OF 125 A*ITACllh1ENT 17 (Page 2 of 2)

NORTil ANNA RADIOACTIVE GASEOUS EFFI UENT hlONITORING INSTRUS1ENTATION SURVEILI,ANCE REQUIREh1ENTS N O Tli I: The Channel Functional Test shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occt. if an.y of the following conditions exists:

a.

Instrument indicates measured levels above the alarm / trip setpoint.

b. Instrument controls not set in operate mode.

NOTE 2: The Channel Functional Test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

Instrument indicates measured levels above the alarm setpoint.

a.

b. Instrument controls not set in operate mode.

NOTE 3: Channel Checks shall consist of verifying indication of flow during periods of release.

Channel Checks shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

i

_____.__.__m

i 1

VIRGINIA VPAP-2103 i

POWER REVISION 3 PAGE 86 OF 125 l

NITACilalENT 18 (Page 1 of 2) j CRITICAI, ORGAN AND INilAl ATION DOSE FACTOltS 1:OR SURRY j

(Critical Pathway Dose Factors) 2 l

Ventilation Vent D/Q = 9.0E-10 nr at $150 meters S Direction 2

Process Vent D/Q = 4.3E-10 ni at 5150 meters S Direction RMiyy ipv RM Radionuclide mrem /vr mrem /vr 1

i Curie /sec Curie /sec 11 3 7.20E+02 3.12E402 Mn-54 ND ND Fe 59 ND ND Co-58 ND ND Co-60 ND ND i

Zn-65 ND ND Rb-86 ND ND Sr89 ND ND i

Sr-90 ND ND Y-91 ND ND l

Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND l

Ru-106 ND ND Ag-110m ND ND Te-127m 8.06E+04 3.85E+04 Te-129m 1.25E+05 5.98E+04 1-131 6.21 E+08 2.97E+08 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba 140 ND ND l

Ce-14i ND ND Ce-144 ND ND ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1 i

i

--e-x

--y

.r7w-

---

7

++=c

-mry*--W4 et-7

's-w-y v--erae c-

+vw'sWN^*

p e-

'WP-'

i i

VIRGINIA VPAP 2103 l

POWER REVISION 3 i

PAGE 87 OF 125 i

A'ITACllMENT 18 I

(Page 2 of 2)

CRITICAL, ORGAN AND INil AI,ATION DOSE FACTORS FOR SURRY i

j (Inhalation Pathway Dose Factors) 3 l

Ventilation Vent x/Q = 3.0E-07 sec/m at $150 meters S Direction 3

Process Vent X/Q = 1.3E-07 sec/m at 5150 meters S Direction i

j RM vy RMipv i

j Radionuclide mrem /vr mrem /yr i

Curie /sec Curie /sec j

11 3 1.94EH)2 8.41EMll i

Cr-51 1.73E401 7.48EM)0 Mn 54 ND ND

]

Fe 59 ND ND i

Co-58 ND ND Co-60 ND ND Zn 65 ND ND 1

Rb-86 ND ND Sr-89 ND ND i

St-90 ND ND

)

Y-91 ND ND Zr 95 ND ND Nb-95 ND ND j

Ru-103 ND ND Ru 106 ND ND Ag 110m ND ND Te-127m 1.46E+03 6.33E+02 Te-129m 1.64E+03 7.12E+02 1 131 4.45EM)6 1.93E+06

{

Cs-134 ND-ND Cs-136 ND ND 4

Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Cc-144 ND -

ND ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1

.-m-w-

,.,,y

.._y

,y.,,s,,,yc,gy._,

,.,__.-.,.7 9..

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 88 OF 125 A'ITACllMENT 19 (Page1of1)

CRITICAI, ORGAN DOSE FACTORS FOR NORTil ANNA (Critical Pathway Dose Factors)

Ventilation Vent D/Q = 2.4E-09 m-2 at 3250 meters N Direction Process Vent D/Q = 1.lE-09 m-2 at 3250 meters N Direction RM yy RM i

ipy Radionuelide mrem /vr mrentlyr Curie /sce Curie /sec 11 3 1.73E+03 9.36EM)2 Mn-54 ND ND Fe-59 ND ND

^

Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND

~

Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND r

Ru-103 ND ND Ru-106 ND ND Ag-llom ND ND Te-127m 1.97E+05 9.04E+04 Te-129m 2.95E+05 1.35E+05 1 131 1.45E+09 6.72E+08 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Cc-144 ND ND ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1 l

VIRGINIA VPAP.2103 POWER REVISION 3 PAGE 89 OF 125 NITACilh1ENT 20 (Page 1 of 2)

SURRY RADIGl.OGICAl, ENVIRONh1 ENTAL,510NITORING PROGRAh!

Exposure Pathway Number ut ; ample and Cullection Type and Frequency of and/or Sample Sample l>ocation Frequency Analysis

1. DIRECT RADIATION About 40 Routine Monitoring Stations to be placed as follows:

1) Inner Ring in general area of site boundary with station in each sector GAMM A DOSE

2) Outer Ring 6 to 8 km from the site with a Quarterly Quanerly station in each sector

3) The balance of the 8 dosimeters should be placedin specialinterest areas such as population centers nearbyresidents, schools, and in 2 or 3 areas to serve as controh

2. AIRBORNE Samples from 7 locations:

a) I sample from close to the site boundary location of the highest Radiciodine Cannister calculated annual II3I Analysis Weekly average ground level Continuous Radiciodines and D/Q Sampler Particulates b) 5 sample locations 6-8 operation with Particulate Samplei km distance located in a sample collection Gross beta radioactivity concentric ring around weekly analysis following filter the Station change; c) I sample from a control location 15-30 km Gaimna isotoinc analys.is distant, providing valid fc mp site (bylocation) background data 9" "#' Y

)

1 VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 90 OF 125 I

i 4

j NITACllMENT 20 (Page 2 of 2)

SURRY RAI)lOlA)GICAl, ENVIRONMENTAL 2 hlONITORING PROGR AM i

l i

Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample 1.ocatlun Frequency Analysis 4

3. WATERBORNE Gamma isotopic analysis a) I sample upstream monthly; j

a) Surface Monthly Sample b) I sample downstream ComI)o. site for tritium analysis quarterly Gamma isotopic and tritium b) Ground Sample from 1 or 2 sources Quarterly analysis quarterly e) Sedimentfrom 8("[;

f"r" Ganuaa isotopic analysis Smi AnnaHy shmchne

""""'""""""Y 4

potential recreational value

"""'E'#8I'*"

""Y I Semi-Annuall>[

Gamma isotopic analysis d) Silt 1

the Stat. ion semi annually

4. INGESTION I

a) 4 samples from milking l

animalsin the vicinity of

"*"' is topic and P

)

a) Milk b) 1a pl from milking Monthly animals at a control analys.is monthly j

location (15-30 km distant) l a) 3 samples of oysters in the vicinity of the Bi-monthly Gamma isotopic on edibles j

Station b) 5 samples of clams in the vicinity of the Hi-monthly Gamma isotopic on edibles b) Fish and Station

[

Invertebrates c) I sampling of crabs from the vicinity of the Annually Gamma isotopic on edibles Station d) 2 samples of fish from the vicinity of the Senu. Annually Gamma.isotop.ic an edibles Station (catfish, white perch, cel)

I a) I sample corn Gamma. isotopic on edible c) Food Products b) 1 sample soybean Annually I

portion I

c) I sample peanuts I

l

4 1

J j

VIRGINIA VPAP 2103 j

POWER REVISION 3 PAGE 91 OF 125 i

f NITACliMENT 21 j

(Page 1 of 5) j NORTil ANNA RADIGI,0GICAL ENVIRONMENTAL MONITORING PROGRAM j

(NOTE 1) i l

Exposure Pathway Number of Sample and Collection Type and Frequency of 4

and/or Sample Sample Location (NOTE 2)

Frequency Analysis

1. DIRECT RADIATION l

(NOTE 3) 3 36 routine monitoring

]

stations either with two or more dosimeters or with one 3

instrument for measuring l

and recording dose rate

]

continuously to be placed as follows:

i

1) An inner ring of stations, one in each GAMMA DOSE meteorological sector l

within the site boundary

2) An outer ring of Quarterly Quarterly i

stations, one in each meteorological sector l

within 8 km range from the site

3) The balance of the stations to be placed in l

special interest areas l

such as population i

centers, nearby residences, schools, and i

in 1 or 2 areas to serve as control stations 1

i 1

1

.i i

VIRGINIA VPAP-3103 POWER REVISION 3 j

PAGE 92 OF 125 1

NITACil51ENT 21 l

(Page 2 of 5)

NORTil ANNA RADIGIA)GICAL ENVIRONh1 ENTAL MONITORING PROGRAM i

Exposure Pathway Number of Sample and Collection Type and Frequency of 1

and/or Sample Sample Location (NOTE 2)

Frequency Analysis I

2. AIRBORNE j

Samples from 5 locations:

)

a) 3 samples from close to l

the 3 site boundary i

locations (in different Radiciodine Cannister sectors) of the highest i131 Analysis, weekly calculated histancal annual average ground Continuous Radiciodines and level D/Q

sampler, Particulates b) I sample from the operation with Particulate Sampler vicinity of a community sample Gross beta radioactivity having the highest collection weekly analysis following filter calculated annual change: (NOTE 4) l average ground level l

4 D/Q

]

c) I sample from a control Gamma isotopic analysis location 15-40 km 4

1. *E * '" 7 ' "" "}

distant and in the least quarterly (NOTE 5) prevalent wm. d direct. ion

3. WATERIlORNE Samples from 3 locations:

a) I sample upstream Gamma isotopic analysis f

monthly; (NOTE 5) a) Surface b) I sample downstream Grab Monthly Compos.ite for tritium 2

c) 1 sample from cooling analysis quarterly i

lagoon b) Ground amp fmm I r sources

"""" is topic and tritium 1

Grab ruarterly only iflikely to be affected analys.is quarterly (NOTE 5)

I sample from downstream Gamma isotopic analysis c) Sediment area with existing or Sem. Annually i-potential recreational value semi-annually (NOTE 5)

,p

.,y

.->q

,er---

,-w

,,y-y-

1

-y,ww c-

-m-.

S

VIRGINIA VPAP 2103 POWER REVISION 3 i

PAGE 93 OF 125 i

NITACilMENT 2I i

(Page 3 of 5)

NORTil ANNA ItADIOI.OGICAI, ENVIRONMEN i e @ a m AING PROGRAM d

Exposure Pathway Number of Sample and Sainple Collection Type and Frequency of and/or Sample IA> cation (NOTE 2)

Frequency Analysis j

4. INGESTION a) Samples from milking f

animals in 3 locations within 5 km distance having the highest potential,if there are none, then, I sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are Monthly at all Gamma isotopic (NOTE 5) a) Milk times and 1333 analysis monthly (NOTE 7) calculated to be greater than 1 l

1 mrem per yr (NOTE 6) l b) I sample from milking animals at a control location (15 30 km distant and in the least prevalent wind j

direction) a) I sample of commercially and recreationally important 4

species (bass, sunfish, catfish) q b) Fish and in vicinity of plant discharge Gamma isotopic on edible Semiannually Invertebrates area portions b) 1 sample cf same species in

]

areas not influenced by plant discharge a) Samples of an edible broad leaf vegetation grown nearest i

each of two different offsite locations of highest predicted historical annual average Monddy if and I ]is topig(NOTE 5) c) Food Products groung level D/Q if milk available,or at t3 analyss sampimg is not performed harvest b) 1 sample of bicad leaf vegetation grown 15-30 km distant in the least prevalent wind direction if milk sampling is not performed i

( _-. -. --

I i

VIRGINIA VPAP-2103 POWER REVISION 3 i

PAGE 94 OF 125 A'ITACIIMENT 21 (Page 4 of 5)

NORTil ANNA RADIGl.OGICAL ENVIRONMENTAL MONITORING PROGRAM 1

NOTE 1: The number, media, frequency, and location of samples may vary from site to site. This i

table presents an acceptable minimum program for a site at which each entry is applicable, j

Local site characteristics must be examined to determine if pathways not covered by this j

table may significantly contribute to an individual's dose and be included ii. (ne sampling i

program.

1 NOTE 2: For each and every sample location in Attachment 21, specific parameters of distance and direction sector from the centerline of the reactor, and additional description where i

pertinent, shall be provided in Attachment 23. Refer to Radiological Assessment 13 ranch Technical Positions and to NUREG-0133, Preparation of Radiological Effluent Technical 4

Specifications for Nuclear Power Plant. Deviations are permitted from the required sampling schedule if specimens are unattainable due to hazardous conditions, seasonal f

unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

j If specimens are unattainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Step 6.6.1, it is recognized that, at times, it i

may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time, in these instances suitable alternative media and locations i

may be chosen for the panicular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to Step 6.6.2, identify the cause of the unavailability of samples for that pathway and identify the new locations for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report revised figures and tables from the ODCM reflecting the new locations.

s I

m v._.,

v,

,.a.,

...,.,.y

,,e

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 95 OF 125 ATI'ACllMENT 21 (Page 5 of 5)

NORTil ANNA RADIOLOGICAL ENVIRONMENTAL, MONITORING PROGRAM NOTE 3: One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this table, a thermoluminescent dosimeter (TLD)is considered to be one phosphor: two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation. The 36 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

NOTE 4: Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay, if gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

NOTF. 5: Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

NOTE 6: The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

NOTE 7: If milk sampling cannot be performed, use item 4.c (Page 3 of 4, Attachment 21)

VIRGINIA VPAP-2103 4

POWER REVISION 3 4

j PAGE 96 OF 125 i

A'ITACllh1ENT 22 (Page 1 of 4)

SURRY ENVIRONh1 ENTAL S Ah1PLING 1 OCATIONS 4

U l LOCATION DIRECTION REMARKS g

g, Air Charcoal ant!

Site Boundary 4

Surry Station (SS) 0.37 NNE Location at Sector

]

Particulate with Highest D/Q liog Island Reserve (IllR) 2.0 NNE i

Bacons Castle (BC) 4.5 SSW Alliance (ALL) 5.1 WSW Colonial Parkway (CP) 3.7 NNW Dow Chemical (DOW) 5.1 ENE Fort Eustis (FE) 4.8 ESE Newport News (NN) 16.5 ESE Control Location l

Environmental Control (00)

Onsite **

TLDs West North West (02) 0.17 WNW Site Boundary Surry Station Discharge 0.6 NW Site Boundary (03)

North North West (04) 0.4 NNW Site Boundary i

North (05) 0.33 N

Site Boundary North North East (06) 0.28 NNE Site Boundary i

North East (07) 0.31 NE Site Boundary

(

East North East (08) 0.43 ENE Site Boundary i

East (Exclusion)

(09) 0.31 E

Onsite West (10) 0.40 W

Site Boundary i

West South West (11) 0.45 WSW Site Boundary South West (12) 0.30 SW Site Boundary South South West (13) 0.43 SSW Site Boundary I

South (14) 0.48 S

Site Boundary South South East (15) 0.74 SSE Site Boundary South East (16) 1.00 SE Site Boundary East (17) 0.57 E

Site Boundary Station Intake (18) 1.23 ESE Site Boundary llog Island Reserve (19) 1.94 NNE Near ReIident

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 97 OF 125 NITAClIh1ENT 22 (Page 2 of 4)

SURRY ENVIRONh1ENTAI, SAhlPI. LNG 1.OCATIONS D S ',

Cls g 3 g,'

l.OCATION 1)lRECTION REhlARKS 5

)

Environmental Bacons Castle (20) 4.45 SSW Approx. 5 miles TLDs Route 633 (21) 3.5 SW Approx. 5 miles Alliance (22) 5.1 WSW Approx. 5 miles Surry (23) 8.0 WSW Population Center Route 636 and 637 (24) 4.0 W

Approx. 5 miles Scotland Wharf (25) 5.0 WNW Approx. 5 miles Jamestown (26) 6.3 NW Approx. 5 miles Colonial Parkway (27) 3.7 NNW Approx. 5 miles Route 617 and 618 (28) 5.2 NNW Approx. 5 miles Kingsmill (29) 4.8 N

Approx. 5 miles Williamsburg (30) 7.8 N

Population Center Kingsmill North (31) 5.6 NNE Approx. 5 miles Hudweiser (32) 5.7 NNE Population Center Water Plant (33) 4.8 NE Approx. 5 miles Dow (34) 5.1 ENE Approx. 5 miles Lee 11all (35) 7.1 ENE ~Ebpulation Center Goose Island (36) 5.0 E

Ipprox. 5 miles Fort Eustis (37) 4.S ESE~I$pprox. 5 miles Newport News (38) 16.5 ESE Population Center James River lltidge (39) 14.8 SSE Control Benn's Church (40) 14.5 S

Control Smithlield (41) 11.5 S

Control a

~

Rushmere (42) 5.2 SSE Approx. 5 miles Route 628 (43) 50 S

Approx. 5 miles Milk Lee llall 7.1 ENE.

Epp's

~

4.8 SSW -

Colonial Parkway 3.7 NNW Judkin's 6.2 SSW William's 22.5 S

Control Location

VIRGINIA VPAP 2103 POWER REVISION 3 PAGE 98 OF 125 A'lTACll51ENT 22 (Page 3 of 4)

SURRY ENVIRONh1 ENTAL, SAh1PI,ING l.OCATIONS g); f' N

E LOCATION DIRECTION REh1 ARKS Well Water Surry Station Onsite* *

• Hog Island Reserve 2.0 NNE Bacons Castle 4.5 SSW Jamestown 6.3 NW Crops (Corn, Pea-Slade's Farm 2.4 S

State Split nuts, Soybeans)

Brock's Farm 3.8 S

State Split Crops Poole's Garden 2.3 S

State Split (Cabbage, Kale)

Carter's Grove Garden 4.8 NE State Split Lucas's Garden l Rev3 (Chester, Va.)

River Water Surry Station intake 1.9 ESE (Ili-monthly) liog Island Point 2.4 NE

~

Newport News 12.0 SE

~

Chicahominy River 11.2 WNW Control Location Surry Station Discharge 0.17 NW River Water Surry Discharge 0.17 NW (htonthly)

Scotland Wharf 5.0 WNW Control Location Sediment Chicahominy River 11.2 WNW Control Location (Silt)

Surry Station intake 1.9 ESE Surry Station Discharge 1.0 NNW 11og Island Point 2.4 NE Point of Shoals 6.4 SSE Newpon News 12.0 SE

h VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 99 OF 125 A'ITACllMENT 22 (Page 4 of 4)

SURRY ENVIRONMENTAL, S AMI'1,1NG 1 OCATIONS

' A' II'I'f UI I',

I 1 OCATION 1)lRECTION REMARKS g

,3,,

{

g,

)

Clams Chicahominy River 11 2 WNW Control location Surry Station Discharge 1.3 NNW

~

llog Island Point 2.4 NE Jamestown 5.1 WNW Lawne's Creek 2.4 SE Oysters Deep Water Shoals 3.9 ESE Point of Shoals 6.4 SSE Newport News 12.0 SE Crabs Surry Station Discharge 0.6 NW i;ish Surry Station Discharge 0.6 NW Shoreline Hog Island Reserve 0.8 N

ISediment Buru ell's Bay 7.76 SSE Onsite Location -in Lead Shield Onsite sample of Well Water-taken from tap-water at Surry Environmental Building i

1 I

m_--______.----_-----__s__

a+w4-s asa m-a;

,4J...a wn, - - - +.

My

--eai sk

+

s a<.,

en VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 100 OF 125 A'ITACliSIENT 23 (Page 1 of 4)

NORTil ANNA ENVIRONMENTAL SAh1PLING LOCATIONS I

Distance an<l Direcibn From Unit No. I SIyII*

I'kSt gh' e

,[

gg 1)irection REMARKS Sample Media Location r

A Sewage Tn'atment Quanctly &

On-Site Enviromnental 01 0.20 NE Phuit Annually

[unej TLDs Frederick's IIall 02 5.30 SSW

[uane{y&

y Mineral,VA 03 7.10 WSW

["[af Wares Crossroads N

5.10 WSW

[u " f y Route 752 05 4.20 NNE-m ane{ &

Sturgeon's Creek Marina 05A 3.20 N

["

ffy #

Y Levy,VA 06 4.70 ESE

[" "af y Bumpass, VA 07 7.30 SSE ftanerly & Musion

[/nually Boundary End of Route 685 21 1.00 WNW Route 700 22 1.00 WSW Quanerly & Exclusion Annually Boundary

" Aspen lillis

23 0.93 SSE Quanerly & Musion Annually Boundary 4

e{lyl Orange, VA 24 22.00 NW Control Bearing Cooling Tower N-1/33 0.06 N

Quanerly On-Site Sturgeon's Creek Marina N-2/34 3.20 N

Quanctly Parking Lot "C" NNE-3/35 0.25 NNE Quanerly On-Site Good 18"pc Church NNE-4/36 4.96 NNE Quanerly Parking Lot "B" NE-5/37 0.20 NE Quanerly On-Site Lake Anna Marina NE-6/38 1.49 NE Quanerly Weather Tower Fence ENE-7/39 0.36 ENE Quarterly On-Site 16ute 689 ENE-8/40 2.43 ENE Quanerly NearTr:dning Facility E-9/41 0.30 E

Quanerly On-Site "Moming Glory 11111" E-10/42 2.85 E

Quarterly Island Dike ESE-11/43 0.12 ESE Quancrly On-Site Route 622 ESE-12/44 4.70 ESE Quanerly a

w

-.,-w r,

e-

-.,w-e-s 4

-- we-ce,,

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 101 OF 125 NITACllMENT 23 (Page 2 of 4)

NORTil ANNA ENVIRONhiENTAL SAMPLING 1.OCATIONS Distance and Direction Frotn Un:t No.1 St ticin stance

, "Ilect in C

Sample Media Location g;m. tion REMARKS cy Envirotuuental Biology Lab SE-13/45 0.75 SE Quanctly On-Site TLDs Route 701 (Dam Entrance)

SE-14/46 5.88 SE Quarterly I

0"

" Aspen Ilills" SSE-15/47 0.93 SSE Quarterly Elk Creek SSE-16/48 2.33 SSE Quarterly Warehouse Compound S-17/49 0.22 S

Quanctly On-Site Gate Elk Creek Church S-18/50 1.55 S

Quarterly 7;

NAPS Access Road SSW-19/51 0.36 SSW Quarterly On-Site Route 618 SSW-20/52 5.30 SSW Quanerly NAPS Access Road SW-21/53 0.30 SW Quarterly On-Site 5

Route 7to SW-22/54 4.36 SW Quanerly

~

p 500 KV Tower WSW-23/55 0.40 WSW Quarterly On-Site

- a Exclusion Route 7(0 WSW-24/56 1.00 WSW Quanerly Boundary N APS Radio Tower W-25/57 0.31 W

Quarterly On-Site Route 685 W-26/58 1.55 W

Quanerly Exclusion Erk! of Route 685 WNW-27/59 1.00 WNW Quanerly Boundary H. Purcell's Private Road WNW 28/60 1.52 WNW Quanerly Etul of #1/#2 Intake NW-29/61 0,15 NW Quanctly On-Site Lake Anna Campground NW-30/62 2.54 NW Quarterly

1. 1/#2 Intake NNW-31/63 0.07 NNW Quarterly On-Site Route 208 NNW-32/64 3.43 NNW Quarterly Burupass Post C, ice C-1/2 7.30 SSE Quarterly Contml Orange, VA C-3/4 22.00 NW Quarterly Control Mineral. VA C-5/6 7.10 WSW Quarterly Contml Louisa. VA C-7/8 11.54 WSW Quanctly Control C

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 102 OF 125 ATI'ACilMENT 23 (Page 3 of 4)

NORTil ANNA ENVIRONMENTAL SAMPLING LOCATIONS C

Distance and Direction Froin Unil No,1 b.til,in 1 stan e ph,.",I, "'].

Sample Media Location Direction REMARhS

(

)

Airtome N APS Sewage Treatment 01 0.20 NE Weekly

[On-Site Plant Particulate Frederick's llall 02 5.30 SSW Weekly l

and hiineral, VA 03 7.10 ~

WSW Weekly RaJioiodine Wares Crossroads N

5.10 WNW Weekly Route 752 05 4.20 NNE Weekly Sturyeon's Creek N1arina 05A 3.20 N

Weekly

,y Levy,VA 06 4.70 ESE Weekly Bumpass, VA 07 7.30 SSE Weekly M[5 End of Route 685 21 1.00 WNW Weekly Exclusion

"* M Boundary NNdS Route 700 22 1.00 WSW Weekly Exclusion Boundary Exclusion D.

" Aspen Ilills" 23 0.93 SSE Weekly Boundary Orange, VA 24 22.00 NW Weekly Control Waste licat Treatment Surface Water Facility (Second Cooling OS 1.10 SSE Monthly Lagoon)

Nonh Anna River (upstream)Rt 669 Bridge 09A 12.9 WNW Monthly Control (Brool:'s Bridge)

Nonh Anna River i1 5.80 SE Monthly (downstream)

Ground Water (well water) lliology Lab OIA 0.75 SE Quanerly Aquaty Waste lleat Treatment Sediment Facility (Second Cooling 08 1.10 SSE Semi-Annually Lagoon)

Nenh Anna River (upstream)Rt 669 Bridge 09A 12.9 WNW Semi-Annually Control (Brook's Bridge)

North Anna River 11 5.80 SE Semi-Annually (downstream)

Shoreline Soil Lake Anna (upstream) 09 2.20 NW Semi-Annually Soil N APS SewageTreatment 01 0.20 NE Once per 3 yrs On-Site Ilant

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 103 OF 125 A'ITACilMENT 23 (Page 4 of 4)

NORTil ANNA ENVIRONMENTAI, SAMPLING LOCATIONS Distance and Direction From Unil No.1 Sample Media Location St,1<in l} tance fr' Direction REMARKS

((

)

cy Soit Fredericks llall 02 5.30 SSW Once per 3 yrs (continued)

Mineral, VA 03 7.10 WSW Once per 3 yrs

~

Wares Crossroads (M

5.10 WNW Once per 3 yrs Route 752 05 4.20 NNE Once per 3 yrs Sturgeon's Creek Marina USA 3.20 N

Once per 3 yrs

~

_ Levy,VA 06 4.70 ESE Once per 3 yrs Bumpass, VA 07 7.30 SSE Once per 3 yrs Exclusion Erkl of Route 685 21 1.00 WNW Once per 3 yrs Boundary Exclusion Route 700 22 1.00 WSW Once per 3 yrs Boundary Exclusion

" Aspen Ilills" 23 0.93 SSE Once per 3 yrs Boundary Orange, VA 24 22,00 NW Once per 3 yrs Control Milk 12 8.30 NW Monthly l1 13 5.60 SSE Monthly d

I)

Waste IIcat Treatment Fish Facility (Second Cooling 08 1.10 SSE Semi-Annually Lagoon)

Lake Orange 25 16.50 NW Semi-Annually Control Food Pnxlucts Route 713 14 varies NE (Broad Leat Route 614 15 varies SE Monthly vegetation)

Route 629/322 16 varies NW if available,er Control Route 685 21 varies WNW at harvest

~

" Aspen llills" Area 23 varies SSE m

i VIRGINIA VPAP-2103 POWER REVISION 3 i

PAGE 104 0F 125 A'ITACIIMENT 24 l

(Page 1 of 2)

DETECTION CAPAllILITIES FOR SURRY ENVIRONMENTAL SAMPLE ANALYSIS

[

(NOTE 1) l LOWER LIMIT OF DETECTION (LLD)

+

i

^ ' ' " "

Fish Sed; ment j

Analysis Water Particulate

• "'8

( Ci/kg)

(pCi/kg)

(Note 2)

(pCill) or Gases (pCi/l)

. (pCi/kg)

(".et)

(n.ett (pCi/m3)

(wet) i I

Gross beta 4

0.01 11-3 2,000 Mn-54 15 '

130 l

Fe-59 30 260 i

Co-58, 60 15 130 Zn-65 30 260 i

Zr-95 30 l

Nb-95 15 I131 (Note 3) 1 0.07 1

-60 Cs-134 15 0.05 130 15' 60 150 Cs-137 18 0.06 150 I8 80 180-

[.

Ba-140 60 60 La 140 15 15 l

NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental

{

measurements are given in Regulatory Guide 4.13.

L NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Other peaks.:

j_

that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

NOTE 3: LLD for the Ground (drinking) Water Samples. The LLD for the Surface (non-drinking)

Water Samples is 10 pCi/1.

-. ~

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 105 OF 125 ATTACllMENT 24 (Page 2 of 2) 1)ETECTION CAPAllILITIES l'OR SURRY ENVIRONMENTAL SAMPLE ANALYSIS (NOTE 1)

LOWER LIMIT OF DETECTION (LLD)

NOTE 1: For a particular measurement system (which may include radiochemical separation):

4.66 s b lid =

(24-1)

~ I ^* )

""3 E

• V a 2.22E+06

• Y e e Where:

LLD the "a priori"(before the fact) Lower Limit of Detection as defined above

=

(as microcuries per unit mass or volume) (see 4.8) the standard deviation of the background counting rate or of the counting sh

=

rate of a blank sample as appropriate (as counts per minute, cpm)

E the counting efficiency (as counts per disintegration)

=

V the sample size (in units of mass or volume)

=

2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y

the fractional radiochemical yield (when applicable)

=

A the radioactive decay constant for the particular radionuclide

=

At the elapsed time between sample collection (or end of the sample

=

collection period) and time of counting (for environmental samples, not plant effluent samples)

Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not as an a "posteriori" (after the fact) limit for a particular measurement.

5 VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 106 0F 125 i

A"ITACliMEN'I' 25 (Page 1 of 2)

DETECTION CAPAllILITIES FOR NORTil ANNA ENVIRONMENTAL SAMPLE ANALYSIS _(NOTE 1)

]

1,0WER LIMIT OF DETECTION (LLD)

J i

Airborne Food Sediment i

Analysis Water Particulate

- Milk Products

'P N'

(E N}

(NOTE 2)

(pCill) or Gases (pCill).

(pCi/kg)

)

i (pCi/m3)

(wet)

Gross beta 4

0.01 i

H-3 2,000 Mn-54 15 130

)

Fe-59 30 260

]

Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 l Rev.3 l

Nb-95 15 l Rev.3 i

l-13I (NOTE 2) 1 0.07 1

6(,

Cs-134 15 0.05 130 15 60 150 i

Cs-137 18 0.06 150 18 80 180-Ba.I40 60 60-l Reva La-140 15 15.

l Rev3 i

NOTE 1: This list does not mean that only these nuclides are to be considered. Otner peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported l

in the Annual Radiological Environmental Operating Report pursuant to Technical 1

Specification 6.9.1.8.

NOTE 2: This LLD value is for drinking water samples.

i I-2 s

W 4

4 i

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

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 107 OF 125 ATTACl1 MENT 25 (Page 2 of 2)

DETECTION CAPAlllLITIES FOR NORTil ANNA ENVIRONMENTAL SAMPLE ANALYSIS (NOTE 1)

LOWER LIMIT OF DETECTION (LLD) (NOTE 3)

NOTE 3: For a particular measurement system (which may include radiochemical separation):

4.66 s b LLD =

(25-1) 43g E

V 2.22E+06 Y

e Rev.3 Where:

LLD the "a priori"(before the fact) Lower Limit of Detection as defined above

=

(as microcuries per tmit mass or volume) (see Step 4.8) the standard deviation of the background counting rate or of the counting Sh

=

rate of a blank sample as appropriate (as counts per minute, cpm)

E the counting efficiency (as counts per disintegration)

=

V the sample size (in units of mass or volume)

=

2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y

the fractional radiochemical yield (when applicable)

=

A.

the radicactive decay constant for the particular radionuclide

=

At the elapsed time between sample collection (or end of the sample

=

collection period) and time of counting (for environmental samples, not plant ef0uent samples)

Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not as an a "posteriori" (after the fact) limit for a particular measurement.

I i!

a l

1

i l

VIRGINIA VPAP-2103 i

POWER REVISION 3 I

PAGE 108 0F 125 l

A'ITACIIMENT 26 (Page 1 of 1)

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AT SURRY A

Analys.is

- Water Fish Milk Food Products (pCi/kg, wel).

(pCill)

(pCi/kg, wet)

(pCi/l) s (

in3 l

H-3 30,000 Mn-54 1,000 30,0(X) l Fe-59 400 10,000

)

- Co-58 1,000 30,000 j

Co-60 300 10,000 Zn 65 300 20,000

{

Zr-Nb-95 400 t

1-131.

(NOTE 1) 2 0.9 3-100 l

Cs-134 30 10 1,000 60

-1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 j

NOTE 1: Reporting level for the ground (drinking) water samples required by Attachment 20 The reporting level for the surface (non-drinking) water samples required by Attachment 20 is 20 pCi/1.

J

}.

I I

.l l

1 H

1

, _._...,,_ a.........

. VPAP-2103 VIRGINIA POWER REVISION 3 i

PAGE 109 0F 1251 4

A'ITACilMENT 27 (Page1of1)-

l REPORTING LEVEL S FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AT NORTiI ANNA i

(

Airlmrne Water Fist' Milk Food

• I Analysis l' articulate or (pCi/kg, wet)

- (pCi/l)

(pCi/k w (pCi/l) _

Gases (pCi/m3) f (NOTE 1)--

[

333 20,000 Mn-54 1,000 30,000 Fe-59

-400 10,000 -

Co-58 1,000 30,000-Co 60 300 10,000 l.

Zn 65 300 20,000 l

72-Nb-95 400 l

l-131 2-0.9

.3.

100 l

Cs-134 30 10

-1,0(X).

60 1,000 Cs-137 50 20 2,000 70-2,000 4

Ba-La-140 200 300 NOTE 1: For drinking water samples l

l h

t 4

...a.

-.....a,.

VIRGINIA VPAP-2103 POWER RLVISION 3 PAGE I10 OF 125 ATTACIIMENT 28 (Page 1 of 8)

SURRY METEORLOGICAL, LIQUID, AND GASEOUS PATilWAY ANALYSIS 1.0 MI'TEORI OGICAI, ANALYSIS

!.I Purpose The purpose of the meteorological analysis was to determine the annual average %/Q and D/Q values at critical locations around the Station for ventiiation vent (ground level) and process vent (mixed mode) releases. The annual average X/Q and D/Q values were used in a dose pathway analysis to determine both the maximum exposed individual at site boundary and member of the public. The X/Q and D/Q values resulting in the maximum exposures were incorporated into the dose factors in Attachments 12 and 18.

l.2 Meteorological Data, Parameters, and Methodology Onsite meteorological data for the period January 1,1979, through December 31,1981, was used in calculations. These data included wind speed, wind direction, and differential temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (i.e., ventilation vent), and those characterized as mixed mode (i.e., process vent). The portions of release characterized as ground level were based on AT158.9ft-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were iased on AT ss,9ti.28.2ft and 158.9 ft wind data.

i X/Q's and D/Q's were calculated using the NRC computer code "XOQDOQ - Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations",

September,1977 The code is based upon a straight line airflow modelimplementing the assumptions outlined m Section C (excluding Cla and Clb) of Regulatory Guide 1.111,

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors".

The open terrain adjustment factors were applied to the X/Q values as recommended in Regulatory Guide 1.111. The site region is characterized flat terrain such that open terrain 4

correction factors are considered appropriate. The ground level ventilation vent release calculations included a building wake correction based on a 1516 m2 ontainment minimum c

cross-sectional area. The effective release height used in mixed mode release calculations was

]

based on a process vent release height of 131 ft, ar.d plume rise due to momentum for a vent diameter of 3 in with plume exit velocity of 100 ft/sec, 1

~m,,

,~~.v-

--w--,---'-*

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 111 OF 125 ATTACilMENT 28 (Page 2 of 8)

SURRY METEORLOGICAL, LIQUID, AND GASEOUS PATIIWAY ANALYSIS Ventilation vent, and vent releases other than from the process vent, are considered ground level as specified in Regulatory Guide 1.111 for release points less than the height of adjacent solid structures, terrain elevations were obtained from Surry Power Station Units I and 2 Virginia Electric and Power Company Updated Final Safety Analysis Report Table 11 A-11.

X/Q and D/Q values were calculated for the nearest site boundary, resident, milk cow, and vegetable garden by sector for process vent and ventilation vent releases, X/Q values were also calculated for the nearest discharge canal bank for process and ventilation vent releases.

According to the definition for short term in NUREG-0133," Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations," October,1978, some gaseous releases may fit this category, primarily waste gas decay tank releases and containment purges.

Ilowever, these releases are considered long term for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past release reports.

i Therefore, the use of annual average concentrations is appropriate according to NUREG-0133.

1.3 Results The X/Q value that resulted in the maximum total body, skin, and inhalation exposure for ventilation vent releases was 6.0E-05 sec/m3 at a site boundary location 499 meters N sector.

For process vent releases, the site boundary X/Q value was 1.0E-06 sec/m3 at a location 644 meters S sector. The discharge canal bank X/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 7.8E-05 sec/m3 at a location 290 meters NW sectoi.

The discharge canal bank X/Q value for process vent was 1.6E-06 sec/m3 at a location 290 meters NW sector.

Pathway analysis i'dicated that the maximum exposure from 1131, and from all radionuclides in particulate form with half-lives greater than 8 days was through the grass-cow-milk pathway. The D/Q value ' rom ventilation vent releases resulting in the maximum exposure was 2

9.0E-10 per m at a location 5150 meters S sector. For process vent releases, the D/Q value was 4.3E-10 per m2 at a location 5150 meters S sector. For tritium, the X/Q value from ventilation vent releases resulting in the maximum exposure for the milk pathway was 3.0E-07 sec/m3, and 1.3E-07 sec/m3 for process vent releases at a location 5150 meters S sector. The inhalation pathway is the only other pathway existing at this location. Therefore, the %/Q values given for tritium also apply for the inhalation pathway.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 112 OF 125 A'ITACilMENT 28 (Page 3 of 8)

SURRY METEORI OGICAL, LIQUID, AND GASEOUS PATilWAY ANALYSIS 2.0 LIQUID PATilWAY ANALYSIS 2.1 Purpose The purpose of the liquid pathway analysis was to determine the maximum exposed member of the public in unrestricted areas as a result of radioactive liquid effluent releases. The analysis included a determination of most restrictive liquid pathway, most restrictive age group, and critical organ. This analysis is required for Subsection 6.2, Liquid Radioactive Waste Effluents.

2.2 Data, Parameters, and Methodology Radioactive liquid effluent release data for the years 1976,1977,1978,1979,1980, and 1981 was compiled from the Surry Power Station effluent release reports. The data for each year, along with appropriate site specific parameters and default selected parameters, were entered into the NRC computer code LADTAP as described in NUREG-0133.

Liquid radioactive ef0uents from both units are released to the James River via the discharge canal. Possible pathways of exposure for release from the Station include ingestion of fish and invertebrates and shoreline activities. The irrigated food pathway and potable water pathway i

do not exist at this location. Access to the discharge canal by the general public is gained two ways: access for bank fishing is controlled by the Station and is limited to Virginia Power employees or guests of employees, and boating access is open to the public as far upstream as the inshore end of the discharge canal groin. It has been estimated that boat sport fishing would be performed a maximum of 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per year, and that bank fishing would be performed a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year.

For an individual fishing in the discharge canal, no river dilution was assumed for the fish

[

pathway. For an individual located beyond the discharge canal groins, a river dilution factor of 5 was assumed as appropriate according to Regulatory Guide 1.109, Rev.1, and the fish, invertebrate, and shoreline pathways were considered to exist. Dose factors, bioaccumulation factors, and shore width factors given in Regulatory Guide 1,109, Rev.1, and in LADTAP were used, as were usage terms for shoreline activities and ingestion of fish and invertebrates.

Dose to an individual fishing on the discharge bank was determined by multiplying the annual dose calculated with LADTAP by the fractional year the individual spent fishing in the canal.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE I13 OF 125 o

ATTACllMENT 28 (Page 4 of 8)

SURRY METEORLOGICAL, LIQUID, AND GASEOUS PATilWAY ANALYSIS 2.3 Results For the years 1976,1977,1979,1980, and 1981, the invertebrate pathway resulted in the largest dose. In 1978 the fish pathway resulted in the largest dose. The maximum exposed member of the public was determined to utilize the James River.The critical age group was the adult and the critical organ was either the thyroid or GI-LLI. The ingestion dose factor, Ai,in Step 6.2.3 includes the fish and ir. vertebrate pathways. Aidose factors were calculated for the total body, thyroid, and GI-LLI organs.

3.0 GASEOUS PATIIWAY ANALYSIS 3.1 Purpose A gaseous effluent pathway analysis was performed to determine the location that would result in the maximum doses due to nobie gases for use in demonstrating compliance with Steps 6.3.1.a. and 6.3.3.a.. The analysis also included a determination of the location, pathway, and critical organ, of the maximum exposed member of the public, as a result of the releas: of I31, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for I

use in demonstrating compliance with Step 6.3 4.a. In addition. h analysis included a detennination of the critical organ, maximum age gwup, and sector locatian of an exposed individual through the innalation pathway from 1131, tritium, and particulates to demonstrate compliance with Steps 6.3.1.a..

3.2 Data, Parameters, and Methodology Annual average X/Q values were calculated, as described in Section 1 of this attachment, for the nearert site boundary in each directional sector and at other critical locations accessible to the public inside site boundary. The largest X/Q value was determined to be 6.0E-05 sec/m3 at site boundary for ventilation vent releases at a location 499 meters N direction, and 1.0E-06 sec/m3 at site boundary for process vent releases at a location 644 meters S direction. The maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble gases would be at these site boundary locations. The doses from both release points are summed in calculations to calculate total maximum dose.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 114 OF 125 l

ATTACllMENT 28 (Page 5 of 8)

SURRY MEP ORLOGICAL, LIQUID, aND GASEOUS PATilWAY ANALYSIS Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and X/Q values determined for maximum noble gas doses can be used to determine the I33 maximum dose fann 1

, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway.

The NRC computer code GASPAR," Evaluation of Atmospheric Releases", Revised 8/19/17, was run using 1976,1977,1978,1979,1980 and 1981 Surry Power Station gaseous effluent release report data. Doses from II3I, tritium, and particulates for the inhalation pathway-were calculated using the 6.0E-05 sec/m3 site boundary X/Q. Except for the source term data and the X/Q value, computer code default parameters were used. Results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway, in 1979, the teen was the critical age group. However, the dose calculated for the teen was only slightly greater than for the child and the doses could be considered equivalent.

The gamma and beta dose factors K vy, L vy, M vy, and N vv in Attachment 12 were obtained i

i i

i by performing a units conversion of the appropriate dose facte s from Table B-1, Regulatory Guide 1,109, Rev.1, to mrem /yr per Ci/m3 or mrad /yr per Ci/m3, and multiplying by the ventilation vent site boundary X/Q value of 6.0E-05 sec/m3.The same approach was used to calculate the gamma and beta dose factors Kipv, Lipv, Mipv, and Nipv in Attachment 12 using 3

the process vent site boundary X/Q value of 1.0E-06 sec/m.

d Inhalation pathway dose factors P vy and P v in Attachment 12 were calculated using the i

ip equation:

l P = K (BR) DFA;(c/Q)(mrem /yr per Curie /sec)

(28-1) where:

r K'

= a constant of unit conversion, IE+12 pCi/Ci 4

BR

= the breathing rate of the child age group,3700 m3/yr, from Table E-5, Regulatory Guide 1.109. Rev.1 DFAi = the thyroid organ inhalation dose factor for child age group for the ith radionuclide, i

in mrem /pCi, from Table E-9, Regulatory Guide 1.109, Rev.1 X/Q

= the ventilation vent site boundary X/Q,6.0E-5 sec/m3, or the process vent site 3

boundary X/Q,1.0E-06 sec/m as appropriate

.~

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 115 OF 125 A*ITACllMENT 28 (Page 6 of 8)

SURRY METEORLOGICAL, LIQUID, AND GASEOUS PATilWAY ANALYSIS Step 63.4.a., requires that the dose to the maximum exposed member of the public from 1131, tritium, and from all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to the specified limits. Dose calculations were performed for an exposed member of the public within site boundary unrestricted areas, discharge canal bank, and to an exposed member of the public beyond site boundary at real residences with the largest %/Q values using the NRC computer code GASPAR. Doses to Members of the Public were also calculated for the vegetable garden, meat animal, and milk-cow pathways with the largest D/Q values using the NRC computer code GASPAR.

It was determined that the member of the public within site boundary would be using the discharge canal bank for fishing a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year. The maximum annual X/Q at this location was determined to be 7.8E-05 sec/m3 at 290 meters NW direction. After applying a correction for the fractional part of year an individual would be fishing at this location, the dose was calculatu to be less than an individual would receive at site boundary.

The member of the public receiving the largest dose beyond site boundary was determined to be located 5150 meters S sector. The critical pathway was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid. For each year 1976,-1977, 1978, 1979,1980 and 1981 the dose to the infant from the grass-cow-milk pathway was greater than the dose to the member of the public within site boundary, nearest residence, vegetable or meat pathways. Th:refore, the maximum exposed member of the public was detemlined to be the infant, exposed through tl.e grass-cow-milk pathway. critical organ thyroid, at a location 5150 meters S sector. The only other pathway existing at this location for the infant is the inhalation.

i e

{

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 116 OF 125 Al ATI'AClIMENT 28 (Page 7 of 8)

SURRY METEORLOGICAL, LIQUID, AND GASEOUS PATilWAY ANALYSIS The RMjvy and RM v dose factors, except for tritium, in Attachment 18 were calculated by ip multiplying the appropriate D/Q value with the following equation:

' O (U

)

ff h

RM; = K Fm (r) (DFL; )

_s.g (1 - f f ) e

-X, t F

a g

Ps e

(28-2) p s

where:

K' a constant of unit conversion,1E+12 pCi/Ci

=

QF cow's consumption rate,50, in Kg/ day (wet weight)

=

Uap infant milk consumption rate,330, liters /yr

=

Yp agricultural productivity by unit area of pasture feed grass,0.7 Kg/m2

=

Ys agricultural productivity by unit area of stored feed,2.0,in Kg/m2

=

Fn stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev.

=

i I

fraction of deposited activity retained on cow's feed grass,1.0 for radiciodine, and r

=

0.2 for particulates DFLi thyroid ingestion dose factor for the ith radionuclide for the infant, in mrem /pCi,

=

from Table E-14, Regulatory Guide 1.109, Rev.1 A

decay constant for the ith radionuclide, in see-l

=

Aw decay constant for removal of activity of leaf and plant surfaces by weathering,

=

5.73E-07 sec-1 (corresponding to a 14 day half-life) transport time from pasture to cow, to milk, to receptor,1.73+05, in seconds tr

=

transport time from pasture, to harvest, to cow, to milk, to receptor,7.78E+06, in th

=

seconds fp fraction of year that cow is on pasture 0.67 (dimensionless). 7.78E+06 in seconds

=

fs fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensiantess

=

Parameters used above were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev.l.

,v

VIRGINIA VPAP.2103 POWER REVISION 3 PAGE 117 OF 125 ATTACllMENT 28 (Page 8 of 8)

SURRY METEORI.OGICAl.,1.lQUID, AND GASEOUS PATilWAY ANAL,YSIS Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used:

R 3= KK F OUap(DFL 3 ) [0.75(0.5/H)]%/Q (28-3) g m F where:

K"'=

a constant of unit conversion 1E+03 gm/kg absolute humidity of the atmosphere,8.0, gm/m3 H

=

0.75 = the fraction of total feed that is water 0.5 the ratio of the specific activity of the feed grass to the atmospheric water

=

X/Q = the annual average concentration at a location 5150 meters S sector,3.0E-07 sec/m3 for ventilation vent releases, and 1.3E-07 sec/m3 for the process vent releases Other parameters have been previously defined.

The inhalation pathway dose factors RI vy and Riipv in Attachment 18 were calculated using the following equation:

Rl; = K (BR) DFA;(x/Q)(mrem /yr per Cutie /sec)

(28-4) where:

K' a constant of unit conversion,1E+12 pCi/Ci

=

BR breathing rate of the infant age group,1400 m3/yr, from Table E-5, Regulatory

=

Guide 1.10!' Rev.I DFAi = thyroid organ mhalation dose factor for infant age group for the ith ndionuclide, in mrem /pCi, from Table E-10, Regulatory Guide 1.109, Rev.1 X/Q ventilation vent X/Q,3.0E-07 sec/m3, or the process vent site boundary X/Q,

=

1.3E-07 sec/m3, at a location 5150 meters S sector.

The GASPAR computer runs using 1976,1977,1978,1979,1980 and 1981 Surry effluent release data were reviewed to determine the percent of total dose from the cow milk and 133 inha!ation pathways for1 1l33 cont-ibuted less than 1 percent of the total dose to an infant's I33 thyroid except for the year 1977 when the percent I was 1.77. The calculations indicate that 1133is a negligible dose contributor and its inclusion in a sampling and analysis program and dose calculation is unnecessary.

________--_.u

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 118 OF 125 ATTACilh1ENT 29 (Page ! of 8)

NORTil ANNA A1ETEORLOGICAL, LIQUID, AND GASEOUS PATilWAY ANALYSIS 1.0 h1ETEOROLOGICAL ANALYSIS 1.1 Purpose The purpose of the meteorological analysis was to determine the annual average X/Q and D/Q values at critical locations around the Station for ventilation vent (ground level) and process vent (mixed mode) releases. The annual average X/Q and D/Q values were used to perform a dose pathway analysis to determine both t e maximum exposed individual at site boundary and h

member of the public. The X/Q and D/Q values resulting in the maximum exposures were incorporated into the dose factors in Attachments 13 and 19.

1.2 hieteorological Data, Parameters, and hiethodology Onsite meteorological data for the period January 1,1981, through December 31,1981, were used in calculations. This data included wind speed, wind direction, and differential I

temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (e.g., ventilation vent), and those characterized as mixed mode i

(i.e., process vent). The portions of release characterized as ground level were based on AT sssrt-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were i

based on AT158sn-28.2n and 158.9 ft wind data, i

X/Q's and D/Q's were calculated using the.NRC computer code "XOQDOQ - Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations",

I September,1977. The code is based upon a straight line airflow model implementing the assumptions outlined in Section C (excluding Cla and Clb) of Regulatory Guide 1.111,

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water-Cooled Reactors."

The open terrain adjustment factors were applied to the X/Q values as recommended in Regulatory Guide 1.111. The site region is characterized by gently rolling terrain so open terrain correction factors were considered appropriate. The ground level ventilation vent release calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area.

VIRGINIA VPAP-2103 1

POWER REVISION 3 PAGE 119 OF 125 A'ITACllMENT 29 (Page 2 of 8)

NORTil ANNA METEORLOGICAL, LIQUID, AND G ASEOUS PATIIWAY ANALYSIS The effective release height used in mixed mode release calculations was based on a process vent release height of 157.5 ft, and plume rise due to momentum for a vent diameter of 3 in.

with plume exit velocity of 100 ft/sec. Ventilation vent, and vent releases other than from the process vent, are consider-d ground level as specified in Regulatory Guide 1.111 for release points less than the height of adjacent solid structures, terrain elevations were obtained from North Anna Power Station Units 1 and 2, Virginia Electric _and Power Company Final Safety Analysis Report Table 11C.2-8.

f X/Q and D/Q values were calculated for the nearest site boundary, resident, milk cow, and vegetable garden by sector for process vent and ventilation vent releases at distances specified from North Anna Power Station Annual Environmental Survey Data for 1981. X/Q vc'ues were also calculated for the nearest lake shoreline by sector for the process vent and ventilation vent releases.

7 According to the definition for short term in NUREG-0133," Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations," October,1978, some gaseous 4

releases may fit this category, primarily waste gas decay tank releases and containment purges.

However, these releases are considered long temi for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past release reports.

Therefore, the use of annual average concentrations is appropriate according to NUREG-0133.

The X/Q and D/Q values calculated from 198 i meteorological data are comparable to the values presented in the North Anna Power Station UFS AR.

l.3 Results The X/Q value that resulted in the maximum total body, skin and inhalation exposure for ventilation vent releases was 9.3E-06 sec/m3 at a site boundary location 1416 meters SE sector.

For process vent releases, the site boundary X/Q value was 1.2E-06 sec/m3 at a location 1513 meters S sector. The shoreline X/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 1.0E-04 sec/m3 et a location 241 meters NNE sector. The shoreline X/Q value for process vent was 3.7E-06 sec/m3 at a locatior. 241 meters NNE sector.

i i

e

• e-

-s

e w

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 120 0F 125 ATl'ACllMENT 29 (Page 3 of 8)

NORTil ANNA METEORLOGICAL, LIQUID, AND GASEOUS PATIIWAY ANALYSIS Pathway analysis indicated that the maximum exposure from 1-131, and from all radionuclides in particulate fann with half-lives grer.ter than 8 days was through the grass-cow-milk pathway. The D/Q value from ventilation vent releases resulting in the maximum exposure was 2.4E-09 per m2 at a location 3250 meters N sector. For process vent releases, the D/Q value was 1.1E4)9 per m2 at a location 3250 meters N sector. For tritium, the X/Q value from i

ventilation "ent releases resulting in the maximum exposure for the milk pathway was 7.2E-07 4

i sec/m3, and 3.9E-07 sec/m3 for process vent releases at a location 3250 meters N sector.

2.0 LlQUID PATilWAY ANALYhlS 2.1 Purpose The purpose of the liquid pathway analysis was to determine the maximum exposed member of the public in unrestricted areas as a result of radioactive liquid effluent releases. The analysis includes a determination of most restrictive liquid pathway, most restrictive age group, and critical organ. This analysis is required for Subsection 6.2.

2.2 Data, Parameten, and Methodology Radioactive liquid effluent release data for the years 1979,1980, and 1981 was compiled from the North Anna Power Station semi-annual effluent release reports. The data for each year, along with appropriate site specific parameters and default selected parameters, was entered into the NRC computer code LADTAP as described in NUREG 0133.

4 Re-concentration of effluents using the small lake connected to larger water body model was selected with the appropriate parameters determined from T;ble 3.5.3.5, Design Data for Reservoir and Waste Heat Treatment Facility from Virginia Electric and Power Company, Applicant's Environmental Report Supplement, North Anna Power Station, Units I and 2, March 15,1972. Dilution factors for aquatic foods, shoreline, and drinking water were set to one. Transit time calculations were based on average flow rates. All other parameters were defaults selected by the LADT P computer code.

4

J VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 121 OF 125 ATTACilMENT 29 (Page 4 of 8)

NORTil ANNA METEOHLOGICAL, LIQUID, AND GASEOUS PATilWAY ANALYSIS 2.3 Results For each year, the fish pathway resulted in the largest dose. The critical organ each year was the liver, and the adult and teenage age groups received the same organ dose. However, since the adult total body dose was greater than the teen total body dose for each year, the adult was-selected as the most restrictive age group. Dose factors in Attachment 7 are for the maximum l

exposed member of the public, an adult, with the critical organ being the liver.

3.0 GASEOUS PATIIWAY ANALYSIS 3.1 Purpose i

A gaseous effluent pathway analysis was performed to determine the location that would result i

in the maximum doses due to noble gases for use in demonstrating compliance with Steps 6.3.1.a. and 6.3.3.a. The analysis also included a determination of the critical pathway, location of maximum exposed member of the public, and the critical organ for the maximum dose due to 133I, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for use in demonstrating compliance with requirements in Steps 6.3.1.a.1 and 6.3.3.a. The Analysis also included a determination of the critical pathway, location of maximum exposed member of the public, and the critical organ for the maximum dose due to 1 131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for use in demonstrating compliance with Steps 6.3.1.a.2 and 6.3.4.a.

3.2 Data, Parameters, and Methodolop,y Annual average %/Q values were calculated, as described in Section 1 of this attachment, for the nearest site boundary in each directional sector and at other critical locations beyond the site boundary. The largest X/Q value was determined to be 9.3E-06 sec/m3 at site boundary for ventilation vent releases ut a location 1416 mer s SE direction, and 1.2E-06 sec/m3 at site boundary for process vent releases at a location 1513 meters S direction. The maximum doses to total body and skin and air doses for gamma and beta radiation due to noble gases would be at these site boundary locations. The doses from both release points are summed in calculations i

to calculate total maximum dose.

i

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 122 OF 125 i

ATTACllMENT 29 (Page 5 of 8)

NORTII ANNA METEORLOGICAL, LIQUID, AND GASEOUS PATHWAY ANALYSIS Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and %/Q values determined for maximum noble gas doses can be used to determine the maximum dose from 1131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway.

The NRC computer code GASPAR," Evaluation of Atmospheric Releases," Revised 8/19/77, was run using 1979,1980 and 1981 North Anna Power Station Gaseous Effluent Release Report data. Doses from II33, tritium, and particulates for the inhalation pathway were 3

calculated using the 9.3E-06 sec/m site boundary X/Q. Except for the source term data and the X/Q value, computer code default parameters were used. Results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway.

The gamma and beta dose factors K vy, L vy, Mivy, and N vv in Attachment 13 were obtained i

i by performing a units conversion of the approoriate dose factors from Table B-1, Regulatory Guide 1.109, Rev.1, to mrem /yr per Ci/m3 ~.arad/yr per Ci/m3, and multiplying by the 3

ventilation vent site boundary X/Q value of 9.3E-06 sec/m. The same approach was t. sed in calculating the gamma and beta dose factors Kipy, L v, M y, and N y in Attachment 13 using ip ip ip 3

the process vent site boundary X/Q value of 1.2E-06 sec/m.

The inhalation pathway dose factors P vy and P v in Attachment 13 were calculated using the i

ip following equation:

P = K'(BR) DFA; (x/Q) (mrem /yr per Curie /sec)

(29-1) where:

K' a constant of unit conversion,1E+12 pCi/Ci

=

BR 3

the breathing rate of the child age group,3700 m /yr, from Table E-5, Regulatory

=

Guide 1.109, Rev.1 DFAi = the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in mrem /pCi, from Table E-9, Regulatory Guide 1.109, Rev.1 X/Q the ventilation vent site boundary X/Q,9.3E-06 sec/m3, or the process vent site

=

boundary X/Q,1.2E-06 sec/m3 as appropriate.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 123 OF 125 A'ITACllMENT 29 (Page 6 of 8)

NORTil ANNA METEORLOGICAL, LIQUID, AND GASEOUS PATIIWAY ANALYSIS Step 6.3.4.a., requires that the dose to the maximum exposed member of the public from II31, tritium, and from all radionuclides in particulate fami with half-lives greater than 8 days be less than or equal to the specified limits. Dose calculations were performed for an exposed member of the public within site boundary unrestricted areas, and to an exposed member of the public beyond site boundary at locations identified in the North Anna Power Station Annual Environmental Survey Data for 1981.

It was determined that the member of the public within site boundary would be using Lake Anna for recreational purposes a maximum of 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> per year. It is assumed that this member of the public would be located the entire 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> at the lake shoreline with the largest annual X/Q of 1.0E-04 at a location 241 meters NNE sector. The NRC computer code G ASPAR was run to calculate the inhalation dose to this individual. The G ASPAR results were corrected for the fractional year the member of the public would be using the lake.

Using the NRC computer code G ASPAR and annual average X/Q and D/Q values obtained as described in Section di...s attachment the member of the public receiving the largest dose beyond site boundary was detennined to be located 3250 meters N sector. The critical pathway was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid.

For each year 1979,1980 and 1981 the dose to the infant from the grass-cow-milk pathway was greater than the dose to the member of the public within site boundary. Therefore, the maximum exposed member of the pu' determined to be the infant, exposed through the grass-cow-milk pathway, critical organ thyroid, at a location 3250 meters N sector.

VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 124 OF 125 ATTACIIMENT 29 (Page 7 of 8)

NORTil ANNA METEORLOGICAL, LIQUID, AND GASEOUS PATHWAY /

' YSIS The Rivy and Ripv dose factors, except for tritium,in Attachmeiit 19 were calculated by multiplying the appropriate D/Q value with the following equation:

R; = K

{P Fm @) M )

8+

ps e

(29-2) i where:

K' a constant of unit conversion, IE+12 pCi/Ci

=

QF cow's consumption rate,50, in Kg/ day (wet weight)

=

Uap infant milk consumption rate,330 liters /yr

=

Yp agricultural productivity by unit area of pasture feed grass,0.7 Kg/m2

=

Ys agricultural productivity by unit area of storea feed,2.0,in Kg/m2

=

Fm stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev. I

=

fraction of deposited activity retained on cow's feed grass,1.0 for radiciodine, and r

=

0.2 for particulates DFL; = thyroid ingestion dose factor for the ith radionuclide for the infant, in mrem /pCi, from Table E-14, Regulatory Guide 1.109, Rev. I li

=

decay constant for the ith radionuclide, in sec-1 Aw decay constant for removal of activity of leaf and plant surfaces by weathering,

=

5.73E-07 sec-1 (corresponding to a 14 day half-life) transport time from pasture to cow, to milk, to receptor,1.73E+05, in seconds tr

=

l th transport time from pasture, to harvest, to cow, to milk, to receptor,7.78E+06, in

=

seconds fp fraction of year that cow is on pasture,0.58 (dimensionless),7 months per year from

=

NUREG-0597 fs fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensionless

=

Parameters used in the above equation were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev.l.

v VIRGINIA VPAP-2103 POWER REVISION 3 PAGE 125 OF 125 ATI'ACIIMENT 29 (Page 8 of 8)

NORTil ANNA METEORLOGICAL, LIQUID, AND GASEOUS PATIIWAY ANALYSIS Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the foilowing equation is used:

i i

H )(0.75(0.5/H)]X/Q R 3=KK FmQ Uap @

3 (29-3) g F

where:

K"'=

a constant of unit conversion 1E+03 gm/kg absolute humidity of the atmosphere,8.0, gm/m3

.H

=

0.75 = the fraction of total feed that is water O.5 the ratio of the specific activity of the feed grass to the atmospheric water

=

7/Q = the annual average concentration at a location 3250 meters N sector,7,2E-07 sec/m3 for ventilation vent releases, and 3.9E-07 sec/m for the process vent releases 3

Other parameters have been previously defined.

(

I t

A

~

I' i

ATTACHMENT - TWO CORRECTED PAGE RADIOAM'VE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JULY 1,1990 - DECEMBER. 31,.1990-l

._m.__

_-m- _ -.

TABLE IC NORTH ANNA POWER STATION

[

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

{

GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1990 Page 2 of 2 I

CONTINUOUS MODE BATCH MODE i

3rd 4th 3rd 4th i

NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates (cont.):

't Other (Specify)

Sodium - 24 (T

<'8 days)

Ci N/D N/D N/D 1.82E-10 Bromine - 84 (Th

<-8' days)

Ci N/D N/D 2.57E-9

• I/D Rubidium - 88 (T

< 8 days)

Ci N/D N/D N/D

.4/D Rubidium - 89 (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 Antimony - 122 (T

< 8 days)

Ci N/D N/D 2.03E-9 N/D Tellurium - 131m (T

< 8 days)

Ci N/D N/D N/D N/D Cesium - 138 (T

< 8 days)

Ci N/D.

N/D N/D 1.76E-7 Thuli_um - 1 7.0 (T

> 8 days)

Ci 7.88E-5 N/D N/D N/D l

)

Ruthenium - 106 (T

< 8 days)

Ci N/D N/D N/D 7.27E-5 l

3 l

Total for Period (T

> 8 days)

Ci 3.14 E-4 2.llE-4 7.59E-8 1.55E-5 Total for Period (T

< 8 days)

Ci N/D N/A 4.60E-9 7.29E-5 Total for Feriod Ci 3.14E-4 2.llE-4 8.05E-8 B.84E-5 GROSS ALPHA:

Ci N/D N/D N/D N/D TRITIUM:

Ci 3.51E+0 5.96E+0 2.87E-2 5.26E-1

~~

l iw.

'T in Not Detectable N/A is Not Applicable

.. - - - - =

_