ML20137P216

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Semiannual Effluent Release Rept Jan-June 1985
ML20137P216
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/30/1985
From: Barnes W, Hickman O, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
85-625, NUDOCS 8509190559
Download: ML20137P216 (45)
v • d • e


Text

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SEMI-ANNUAL EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JANUARY 01, 1985, TO JUNE 30, 1985 PREPARED BY: w[

William C. Barnes III '

! Assistant Supervisor Health Physics (Count Room & Environmental)

REVIEWEDBY:(( ,

O. E. Hickman, Jr. '(/

Supervisor Health Physics (Technical Services)

REVIEWED BY: M A.~ H. Staff Superinten ent Health Physics f

/ '

APPROVED BY: s E. Wayne Harrell tion Manager 8509190559 850630 -

DR ADOCK O 38  ;

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FORWARD This report is submitted as required by Appendix A to Operating License Nos.

NPF-4 and NPF-7, Technical Specifications for North Anna Power Station, Units ,

1 and 2, Virginia Electric and Power Company, Docket Nos. 50-338, 50-339, Section 6.9.1.12.

5 RADI0 ACTIVE EFFLUENT RELEASE REPORT

FOR THE NORTH ANNA POWER STATION 1.

JANUARY 01, 1985, TO JUNE 30, 1985 INDEX-SECTION NO. SUBJECT PAGE 1 1 PURPOSE AND SCOPE . . . . . . . . . . . . . . . 1  :

2 DISCUSSION .................. 2 3 SUPPLEMENTAL INFORMATION ........... 3 i i

! . Attachment 1 Effluent Release Data . . . . . 4 I Attachment 2 Revisions to Offsite Dose Calculation Manual (00CM) . . . 5 l j Attachment 3 Revisions to Process Control Program (PCP) . . . . . . . . . 6 1 v I Attachment 4 Major changes to Radioactive Solid Waste Treatment Systems . 7 Attachnent 5 Radioactive Liquid and Gaseous a

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Effluent Monitoring  ;

5 Instrumentation Inoperable. . . 8 Attachment 6 Unplanned Releases. . . . . . . 9 i

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1.0 PURPOSE AND SCOPE The Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents of Light-Water-Cooled Nuclear Power Plants,"

Revision 1. June 1974, with data summarized on a quarterly basis following

^

the format of Appendix B thereof. The report also includes a list of unplanned releases during the reporting period.

As required by Technical Specification 6.15, changes to the ODCM for the time period covered by this report are included. Information is provided to support the changes along with a package of those pages of the

00CM changed.

This report includes changes to the PCP with information and documentation necessary to support the rationale for the changes as required by Technical Specificaiton 6.14.

Major changes to radioactive solid waste treatment systems are reported as required by Technical Specification 6.16. Information to support the reason for the change and a summary of the 10 CFR Part 50.59 evaluation are included. In lieu of reporting major changes in this report, major changes 4

to the radioactive solid waste treatment systems may be submitted as part of the annual FSAR update.

As required by Technical Specificaiton 3.3.3.10.b and 3.3.3.11.b a list and explanation for the inoperability of radioactive liquid and/or gaseous 1

effluent monitors is provided in this report.

2.0 DISCUSSION The basis for the calculation of the percent of technical specification for the critical organ in Table 1A is Technical Specification 3.11.2.1.b.

l

- Page 2 Technical Specification 3.11.2.1.b requires that the dose rate for iodine-131, for tritium, and for all radionclides in particlate form with

half lives greater than 8 days shall be less than or equal to 1500 mrem /yr i

to the critical organ at and beyond the site boundary. The critical organ is the child's thyroid, inhalation pathway.

4 The basis for the calculation of percent of technical specification for the total body and skin in Table 1A is Technical Specification 3.11.2.1.a.

Technical Specification 3.11.2.1.a requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin.

The basis for the calcula' tion of the percent of technical specification  ;

in Table 2A is Technical Specification 3.11.1.1. Technical Specification

3.11.1.1 states that the " concentration of radioactive material released in

, liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 i

x 10 microcuries/ml.

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

j Unplanned releases presented in Attachment 6 are defined according to i

the criteria presented in 10 CFR Part 50.73. Gaseous unplanned releases are those radioactive releases that exceed 2 times the applicable concentrations

) i of the limits specified in Appendix B, Table II of 10 CFR Part 20 in unrestricted areas, when averaged over a time period of one hour. Liquid ,

e i unplanned releases are those effluent releases that exceed 2 times the (

i i I

- Page 3 limiting combined Maximum Permissible Concentration (MPC) specified in

. Appendix B. Table II of 10 CFR Part 20 in unrestricted areas for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour, i J

3.0 SUPPLEMENTAL INFORMATION 2 There are no inclusions for the time period covered by this report.

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. Page 4 ATTACHMENT 1 EFFLUENT RELEASE DATA 1/85-6/85 This attachment includes a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21. ~

TABLE 1A EFFLUENT AND WASTE DISPOS'AL SEMI-ANNUAL REPORT (1985)

CASE 0US EFFLUENTS - SUMMATION OF ALL RELEASES h0RTH ANNA POWER STATION EST. TOTAL UNITS 1stQUARTER 2ndQUARTER 1 ERROR A. Fission and Activation Cases:

1. Total Release Ci 7.28E+1 2.40E+2 1.50E+1
2. Average Release Rate for Period uCi/sec 9.36E+0 3.05E+1 B. Iodines:
1. Total Iodine-131 Release Ci 9.36E-3 3.38E-2 1.50E+1
2. Average Release Rate for Period: uC1/see 1.20E-3 4.30E-3 C. PARTICULATES (T > 8 days)
1. Total Particulate (T > 8 days) Release C1 2.83E-5 1.94E-3 1.50E+1
2. Average Release Rate for Period uCi/sec 3.64E-6 2.47E-4

. 3. Cross Alpha Radioactivity Release Ci 1.71E-5 6.64E-5 D. Tritium:

1. Total Release Ci 5.43E+0 2.25E+0 1.30E+1
2. Average Release Rate for Period uCi/sec 6.98E-1 2.86E-1 E., Percentage of Technical Specificaiton Limits:
1. Total Body Dose Rate  % 3.24E-2 1.34E-1
2. Skin Dose Rate  % 9.24E-3 3.82E-2
3. Critical Organ Dose Rate  % 1.35E-3 3.OllE-3

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

GASEOUS EFFLUENTS MIXED MODE RELEASES NORTH ANNA POWER STATION Page 1 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT ist QUARTER 2nd QUARTER lstQUARTER 2nd QUARTER Fission and Activation Cases: * * **

Ci

  • 1.14E-1 Xenon - 131m Ci *
  • 9.71E-2
  • Xenon - 133 Ci 2.49E+1 3.16E+1 8.46E+0 3.38E+1 Xenon - 133m Ci *
  • 6.04E-2 6.59E-1 Xenon - 135 Ci 3.02E+0 7.61E+0
  • 4.03E+0 Xenon - 133m Ci l C1 * * *
  • Xenon - 138 Other (Specify) Ci Argon - 41 C1 * *
  • 6.86E-2 C1 C1 Total for Period C1 2.79E+1 3.92E+1 8.62E+0 3.88E+1 Ci Iodines: Ci Iodine - 131 Ci 1.63E-5 4.15E-5 4.23E-6 4.21E-6 Iodine - 132 Ci * *
  • 2.48E-7 Iodine - 133 Ci 6.18E-5 1.37E-4 3.57E-7 6.82E-6 Iodine - 134 Ci
  • *
  • 2.42E-6 Iodine - 135 Ci Ci Total for Period' Ci 7.81E-5 1.79E-4 4.59E-6 1.37E-5 Ci Particulates: Ci Ci
  • 3.03E-8 *
  • Barium - 140 Ci Lanthanum - 140 Ci * * *
  • Other (Specify) Ci Manganese - 54 Ci
  • 1.09E-8
  • 4.64E-9 Iron - 55 Ci
  • 5.97E-8 Cobalt - 60 Ci 5.22E-8 *
  • Less than lower limits of detection

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TABLE IC EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

CASEOUS EFFLUENTS-CROUND-LEVEL RELEASES NORTH ANNA POWER STATION Page 1 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT lst QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER Fission and Activation Gases:

  • a =

Krypton - 85 Ci Krypton - 85m C1 3.76E-1 1.64E+0 *

Xenon - 133 Ci 1.86E+O 2.66E+1 1.64E-5 1.91E-4 Xenon - 133m Ci * * *

  • Xenon - 135 Ci 1.67E+1 6.06E+1 .6.34E-2 1.23E-1 l

Xenon - 153m Ci 9.42E+0 3.80E+1 2.32E-2 6.24E-2 Xenon - 138 Ci 4. 34E+0 2.llE&l *

  • Other (Specify) Ci l Argon - 41 Ci 1.75E+0 6.38E+0 5.26E-6 2.12E-5 Ci l

j Ci Total for Period Ci 3.62E+1 1.62E+2 8.65E-2 1.86E-1 Ci Iodines: Ci l Iodine - 131 Ci 6.62E-4 2.18E-3 2.61E-6 1.37E-5 l Iodine - 132 C1

  • 3.43E-5 1.04E-5 9.23E-5 Iodine - 133 Ci 8.56E-3 3.09E-2 1.87E-5 1.07E-4 l Iodine - 134 Ci *
  • 9.70E-6 1.55E-4 i l

Iodine - 135 Ci

  • 2.96E-5 2.06E-5 1.39E-4 Ci

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l Total for Period Ci 9.22E-3 3.31E-2 6.20E-5 5.07E-4 l Ci Particulates: Ci Strontium - 89 C1

  • 1.66E-5 8.18E-7 3.09E-6 Cesium - 137 Ci 1.74E-5 6.56E-5 1.40E-6 5.79E-6 l Barium - 140 Ci * * *
  • l Other (Specify) Ci Lanthanum - 140 Ci * * *
  • Niobium - 95 Ci '
  • 1.12E-7 9.31E-7 Iron - 55 C1 l 3.69E-10 4.27E-5 .

l Cobalt - 58 C1 3.20E-6 2.25E-6 5.50E-7 3.92E-6 l Cobalt - 60 C1 4.51E-6 1.12E-5

  • 3.lbE-b
  • Less than lower limits of detection

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TABLE IC EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT (1985)

CASEOUS EFFLUENTS-GOUND-LEVEL RELEASES NORTH ANNA POWER STATION

! Page 2 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RF1. FACED UNIT Ist QUARTER 2nd QUARTER let QUARTER 2nd QUARTER J Particulates (cont):

Yttrium - 91 Ci

  • 1.79E-3 *
  • 6.38E-7 5.17E-6 Rubidium - 88 (TS < 8 days) Ci 5.64E-3 5.50E-2 * *.

Rubidium - 89 (Th ( 8 days) C1 4.75E-3 2.50E-2 3.73E-7

  • Tellurium - 131m (TN < 8 days) C1 -
  • 4. 7,4 E-5 *
  • Tellurium - 132 (Th < 8 days) Ci 8.65E-5 2.26E-4 *
  • Cesium - 138 (Th < 8 days) C1 1.76E-2 9.40E- 2 8.52E-4 4.41E-4 i Ci i Total For Period (T > 8 days) C1 2.54E-5 1.93E-3 2.88E-6 1.38E-5 l Total For Period (Th ( 8 days) C1 2.81E-2 1.74E-1 8.53E-4 4.46E-4 Total For Period C1 2.81E-2 1.76E-l 8.56E-4 4.60E-4 l Ci GROSS ALPHA: Ci 1.71E-5 6.64E-5 *
  • Ci TRITIUM: C1 5. 3 7E+0 2.2IE+0 5.1ME-3 3.04E-Z

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1983)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES NORTH ANNA POWER STATION EST. TOTAL g UNIT Ist QUARTER 2nd QUARTER ERROR % .

A. Fission & Activation Products

1. Total release (not including tritium, gases, alpha) Ci 1. 34 E-1 2.40E-1 1.50E+1
2. Average diluted concentration during period pCi/ml 1.90E-10 3.38E-10
3. Percent of applicable limit (T.S.)  % 4.55E-3 5.92E-3 B. -Tritius l 1. Total release activity. Ci 4.37E+2 4.01E+2 1,50E+1
2. Average diluted concentration during period. pCi/ml 6.21E-7 5.64E-7
3. Percent of applicable limit (T.S.)  % 2.07E-2 1.88E-2 C. Dissolved and entrained gases
1. Total release activity. Ci 6.05E-1 2.27E-1 1.50E+1
2. Average diluted concentration during period. uC1/ml 8.59E-10 3.20E-10
3. Percent of applicable limit (T.S.)  % 4.30E-4 1.60E-4 D. Cross Alpha Radioactivity
1. Total release activfty. Ci <MDA <MDA 1.50E+1 E. Volume nf veste released (prior to dilution) Liters 8.61E+7 7.69E+7 F. Volu=e of dilution water used during period Liters 7.04E+11 7.IIE+11

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985) l LIQUID EFFLUENTS NORTH ANNA POWER STATION Page 1 of 2 ,

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Fission and Activation Products Strontium - 89 Ci *

  • Ci *

Cesium - 134 C1 3.05E-2 5.50E-2 1.09E-5

  • Cobalt - 58 Ci 1.59E-2 3.66E-3 1.28E-5 2.81E-4 Cobalt - 60 Ci 1.08E-2 2.32E-2 1.33E-6 1.49E-3 Iron - 59 Ci * * *
  • Zine - 65 Ci * * *
  • Chromium - 31 Ci * * *
  • Manganese - 54 Ci
  • 5.67E-4 2.88E-8 8.79E-5 Niobium - 95 Ci
  • 1.12E-3 1.71E-8 1.77E-5 Zirconium - 95 C1 * * *
  • 6.36E-6
  • Barium - 140 Ci * * *
  • Lanthanum - 140 Ci * * *
  • Cerium - 141 Ci * * *
  • Other (Specify) Ci Sodium - 24 Ci 2.12E-3 1.40E-2 8.08E-6
  • 1.26E-8 7.87E-6 Silver - 110m Ci 2.15E-4 5.46E-3 7.15E-8 5.26E-5 Antimony - 122 Ci ' l.93E-3 6.28E-3 .

2.94E-8

  • 1.19E-4
  • Iodine .-- 133 C1 3.33E-3 6.88E-3 2.16E-4
  • 1.20E-4
  • 1.72E-3 2.71E-4
  • Tellurfum - 131m Ci *
  • 3.87E-6
  • 7.40E-5
  • C1 C1 C1 Ci Ci Total for Period C1 1.jJE-1 z.jst-1 v.u1E-4 f~94E-3 8 less than lower limits of detection

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TABLE 3 (1/85 - 6/85)

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH EST. TOTAL

1. Type of Waste UNIT PERIOD ERROR, %
a. Spent resins, filter sludges, m3 1.24E+2 1.0 E+1 evaporator bottoms, etc. Ci 1.00E+2 1.0 E+1
b. Dry compressible waste, m3 1.40E+2 1.0 E+1 contaminated equipment, etc. Ci 1.28E+1 1.0 E+1
c. Irradiated components, control m3 0. E . E rods, etc. Ci 0. E . E
d. Other(describe) m3 0. E . E Ci 0. E . E
2. Estimate of major nuclide composition (by type of' waste)
a. H 3  % 38.6 1. 0 E+1 Ni 63  % 22.4 1. 0 E+1 Fe 55  % 12.95 1. 0 E+1 Co 60  % 6.8 1. 0 E+1 Cs 137  % 5.94 1. 0 E+1 C 14  % 2.76 1. 0 E+1 Cs 134  % 2.75 1. 0 E+1 Cm 242  % 2.11 1. 0 E+1 Co 58  % 1.72 1. 0 E +1 Cm 244  % 1.02 1. O E +1 Pu 241  % l.01 1. 0 E+1 I 131  % .8 1. O E+1 Mn 54  % .71 1. 0 E +1 Sb 122  % .13 1. 0 E + 1 Pu 239  % .08 1. O E +1 Ce 144  % .04 1. 0 E +1 1.a 140  % .03 1. 0 E +1 Ba 140  % .03 1. 0 E +1 Sr 90  % .01 1. 0 E +1 Xe 133  % .Q1 1. O E +1 Nb 95  % .007 1. 0 E + 1 Zr 95  % .003 1. 0 E +1 Pu 238  % .002 1. 0 E + 1 Te 99  % .001 1. O E + 1 I 129  % .0006 1. 0 E +1

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b.  % .

Fe 55  % 51.05 10 E+1 H 3  % 15.I 1 0 E +1 Co 60  % 10.4 1 0 E+1

1 TABLE 3-CONTINUED PAGE 2

2. Estimate of major nuclide composition (by type of waste)
b. (con't)  % . E Cs 137  % 5.1 1.0 E +1 Ce 144  % 5.08 1 0 E +1 Ni 63  % 3.21 1 0 E +1 Pu 241 1 2.2 1.0 E +1 C 14  % 1.5 1 0 E +1 Cs 134  % 1.45 1 0 E +1 Zr 95  % 1.40 1 0 E +1 Nb 95  % 1.35 1 0 E +1 Co 58  % 1.1 1 0 E +1 Sr 90  % 1.0 1 0 E +1 cm. 242  % .5 1 0 E +1 -

Mn 54  % .3 1 0 E +1 Ru 103  % .1 1 0 E +1 Pu 238  % .01 1 0 E +1 Pu 239  % .01 1 0 E +1 Am 241  % .005 1 0 E +1 cm 243  % .003 1 0 E +1 Cm 244  % .003 1 0 E +1 Sb 122  % .002 1.0 E +1 l

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3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 32 Private Vehicle Barnwell, SC B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHI""ENTS MODE OF TRANSPORTATION DESTINATION 0

- Page 5 ATTACHMENT 2 (01/85-06/85)

REVISIONS TO 0FFSITE CALCULATION MANUAL (00CM)

No changes were made to the Offsite Oose Calculation Manual (ODCM) for the time period covered by this report.

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- Page 6 ATTACHMENT 3 (01/85-06/85)

REVISIONS TO PROCESS CONTROL PROGRAM (PCP)

No changes were made to the Process Control Program (PCP) for the time period covered by this report.

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. Page 7 ATTACHMENT 4 i

(01/85-06/85) 5 MAJOR CHANGES TO RADIOACTIVE SOLID WASTE TREATMENT SYSTEMS i

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No major changes to the radioactive solid waste 4

treatment systems were made for the time period l covered by this report. ,

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ATTACHMENT 5 (01/85-06/85)

RADI0 ACTIVE LIQUID AND GASEOUS

EFFLUENT MONITORING INSTRUMENTATION INOPERABLE 1

i None of the radioactive effluent monitors met the

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requirements of Technical Specification 3.3.3.10.b i and 3.3.3.11.b, for providing an account due to i

] inoperability.

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  • Page 9 ATTACHMENT 6 (01/85-06/85)

UNPLANNED RELEASES l No unplanned releases, as defined according to the criteria presented in 10 CFR Part 50.73, l

l occurred during the time period covered by this 4

report.

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SEMI-ANNUAL EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JANUARY 01, 1985 TO JUNE 30, 1985 l

PREPAREDBY:[ wd William C. Barnes III '

Assistant, Supervisor Health Physics (Count Room & Environmental)

REVIEWED BY: (( ,

O. E. Hickman, Jr. '(f Supervisor Health Physics (Technical Services) l REVIEWED BY: M A. H. Staff Superinten ent Health Physics I

APPROVED BY: s E. Wayne Harrell tion Manager

3, _ *'

i l-i FORWARD P

This report is submitted as required by Appendix A to Operating License Nos.  :

NPF-4 and NPF-7, Technical Specifications for North Anna Power Station, Units i 1 and 2. Virginia Electric and Power Company, Docket Nos. 50-338, 50-339, i

+

Section 6.9.1.12.

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P.ADI0 ACTIVE EFFLUENT RELEASE REPORT

^

FOR THE NORTH ANNA POWER STATION JANUARY 01, 1985, TO JUNE 30, 1985 i

INDEX SECTION NO. SUBJECT PAGE

]

1 PURPOSE AND SCOPE . . . . . . . . . . . . . . . 1 2 DISCUSSION .................. 2 3 SUPPLEMENTAL INFORMATION ........... 3 Attachment 1 Effluent Release Data . . . . . 4 1

Attachment 2 Revisions to Offsite Dose Calculation Manual (CDCM) . . . 5 Attachment 3 Revisions to Process Control Program (PCP)......... 6 Attachment 4 Major changes to Radioactive Solid Waste Treatment Systems . 7 Attachment 5 Radioactive Liquid and Gaseous

', Effluent Monitoring e

Instrumentation Inoperable. . . 8 i Attachment 6 Unplanned Releases. . . . . . . 9

i .

Page 1 1.0 PURPOSE AND SCOPE The Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as i

outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents of Light-Water-Cooled Nuclear Power Plants "

Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The report also includes a list of 4

unplanned releases during the reporting period.

1 As required by Technical Specification 6.15, changes to the 00CM for i the time period covered by this report are included. Information is provided to support the changes along with a package of those pages of the 00CM changed.

This report includes changes to the PCP with information and documentation necessary to support the rationale for the changes as required i

by Technical Specificaiton 6.14.

Major changes to radioactive solid waste treatment systems are reported i

as required by Technical Specification 6.16. Information to support the ,

! reason for the change and a summary of the 10 CFR Part 50.59 evaluation are included. In lieu of reporting major changes in this report, major changes to the radioactive solid waste treatment systems may be submitted as part of the annual FSAR update.

1 As required by Technical Specificatton 3.3.3.10.b and 3.3.3.11.b a list and explanation for the inoperability of radioactive liquid and/or gaseous i

2 effluent monitors is provided in this report.

2.0 DISCUSSION The basis for the calculation of the percent of technical specification 4

j for the critical organ in Table 1A is Technical Specification 3.11.2.1.b.

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Page 2 ,

Technical Specification 3.11.2.1.b requires that the dose rate for t iodine-131, for tritium, and for all radionclides in particlate form with l i half lives greater than 8 days shall be less than or ecual to 1500 mrem /yr to the critical organ at and beyond the site boundary. The critical organ .

I is the child's thyroid, inhalation pathway.

1 The basis for the calculation of percent of technical specification for the total body and skin in Table 1A is Technical Specification 3.11.2.1.a.

Technical Specification 3.11.2.1.a requires that the dose rate for noble i gases to areas at or beyond site boundary shall be less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin.

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

i in Table 2A is Technical Specification 3.11.1.1. Technical Specification 3.11.1.1 states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for. radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcuries/ml.

s Percent of technical specification calculations are based on the total gaseous or liquid effluents released for that ' respective quarter.

Unplanned releases presented in Attachment 6 are defined according to i

the criteria presented in 10 CFR Part 50.73. Gaseous unplanned releases are )

those radioactive releases that exceed 2 times the applicable concentrations.

i of the limits specified in Appendix B, Table II of.10 CFR Part 20 in l unrestricted areas, when averaged over a time period of one hour. Liquid unplanned releases are those effluent releases that exceed 2 times the-i 5 (

. Page 3 limiting combined Maximum Permissible Concentration (MPC) specified in Appendix B. Table II of 10 CFR Part 20 in unrestricted areas for all i radionuclides except tritium and dissolved noble gases, when averaged over a i time period of one hour.

3.0 SUPPLEMENTAL INFORMATION There are no inclusions for the time period covered by this report. ,

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' . Page 4 ATTACHMENT 1 EFFLUENT RELEASE DATA 1/85-6/85 4

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

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TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

CASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NORTH ANNA POWER STATION EST. TOTAL UNITS 1stQUARTER 2ndQUARTER % ERROR A. Fission and Activation Cases:

1. Total Release Ci 7.28E+1 2.40E+2 1.50E+1
2. Average Release Rate for Period pCi/sec 9.36E+0 3.05E+1 B. Iodines:
1. Total Iodine-131 Release Ci 9.36E-3 3.38E-2 1.50E+1
2. Average Release Rate for Period: uCi/see 1.20E-3 4.30E-3 C. PARTICULATES (T > 8 days) 2
1. Total Particulate (T > 8 days) Release Ci 2.83E-5 1.94E-3 1.50E+1
2. Average Release Rate for Period pCi/sec 3.64E-6 2. 4 7E-4

, 3. Cross Alpha Radioactivity Release Ci 1.71E-5 6.64E-5 D. Tritium:

1. Total Release Ci 5.43E+O 2.25E+0 1.50E+1
2. Average Release Rate for Period pCi/see 6.98E-1 2.86E-1

! E., Percentage of Technical Specificatton Limits:

1. Total Body Dose Rate 2 3.24E-2 1.34E-1
2. Skin Dose Rate Z 9.24E-3 3.82E-2
3. Critical Organ Dose Rate 2 1.35E-3 3.OllE-3

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985) i CASEOUS EFFLUENTS MIXED HODE RELEASES NORTH ANNA POWER STATION Page 1 of 2 i CONTINUOUS H0DE BATCH HODE NUCLIDES RELEASED UNIT lst QUARTER 2nd QUARTER latQUARTER 12nd QUARTER l Fission and Activation Oceas:

Ci * * * .*

Krypton - 85 Krypton - 85m Ci * *

  • 1.64E-2
Krypton - 88 Ci . * *
  • 1.14E-1 Xenon - 131m Ci *
  • 9.71E-2
  • Xenon - 133 C1 2.49E+1 3.16E+1 8.46E+0 3.38E+1
Xenon - 133m Ci *
  • 6.04E-2 6.59E-1 Xenon - 135 C1 3.02E+0 7.61E+0
  • 4.03E+0 Xenon - 133m Ci * * *
  • Other (Specify) C1 Argon - 41 Ci * *
  • 6.86E-2 Ci Ci
Total for Period C1 2.79E+1 3.92E+1 8.62E+0 3.88E+1 Ci Iodines: Ci Iodine - 131 '

Ci 1.63E-5 4.15E-5 4.23E-6 4.21E-6 Iodine - 132 C1 * *

  • 2.48E-7 Iodine - 133 Ci 6.18E-5 1.37E-4 3.57E-7 6.82E-6 Iodine - 134 Ci * * *
  • 2.42E-6 Ci Total for Period' Ci 7.81E-5 1.79E-4 4.59E-6 1.37E-5 Ci Particulates: Ci Strontium - 89 C1

, Cesium - 134 Ci

  • 1.33E-8 *
  • 3.03E-8 *
  • l Barium - 140 Ci * * *
  • Lanthanum - 140 Ci * * *
  • Other (Specify) Ci Manganese - 54 C1
  • 1.09E-8
  • 4.64E-9 Iron - 55 Ci
  • 5.97E-8 Cobalt - 60 Ci 5.22E-8 * *
  • I
  • Less than lower limits of detection

)

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

GASEOUS EFFLUENTS MIXED MODE RELEASES NORTH ANNA POWER STATION Page 2 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT Ist QUARTER 2nd QUARTER 1st QUARTER 2nd QUAI;TER

Particulates (cont)

Rubidium - 88 (Th ( 8 days) Ci * *

  • 2.03E-3
Cesium - 138 (Th < 8 days) Ci * *
  • 1.58 &-7 l Ci Total For Period (T4 > 8 days) Ci 5.22E-8 1.l?E-7 = 4.04t-v Total For Period (Th < 8 days) Ci . . , z . 03E

.s

! Total For Period Ci 5.22E-8 1.19E-7

Ci

! GROSS ALPHA: Ci 3.IIE-10 * *

  • Ci l TRITIUM: Ci 5.20E-2 4.58E-3 7.68E-5 6.74E-4
C1 Ci Ci C1 Ci C1 Ci
Ci C1 Ci C1 C1 C1 C1 C1 Ci

) C1 C1 C1 C1 C1 C1 Ci Ci Ci

  • Less than lower limits of detection

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

CASE 0US EFFLUENTS-CROUND-LEVEL RELEASES NORTH ANNA POWER STATION Page 1 of 2 CONTINUOUS NODE BATCH MODE NUCLIDES RELEASED UNIT lst QUARTER 2nd QUARTER ist QUARTER 2nd QUARTER Fission and Activation Cases:

  • * * =

Krypton - 85 Ci Krypton - 85m C1 3.76E-1 1.64E+0 *

9.30E-1 4.llE+0 *

  • Xenon - 133 C1 1.86E+0 2.66E+1 1.64E-5 1.91E-4 Xenon - 133m Ci * * *
  • Xenon - 135 Ci 1.67E+1 6.06E+1 . 6. 34 E-2 1.23E-1 Xenon - 153m Ci 9.42E+0 3.80E+1 2.32E-2 6.24E-2 Xenon - 138 C1 4.34E+0 2.llE+1 *
  • Other (Specify) Ci Argon - 41 Ci 1.75E+0 6.38E+0 5.26E-6 2.12E-5 C1 Ci Total for Period Ci 3.62E+1 1.62E+2 8.65E-2 1.86E-1 Ci Iodines: C1 Iodine - 131 Ci 6.62E-4 2.18E-3 2.61E-6 1.37E-5 Iodine - 132 C1
  • 3.43E-5 1.04E-5 9.23E-5 Iodine - 133 Ci 8.56E-3 3.09E-2 1.87E-5 1.07E-4 Iodine - 134 Ci *
  • 9.70E-6 1.55E-4 Iodine - 135 Ci
  • 2.96E-5 2.06E-5 1.39E-4 Ci

~

Total for Period di 9.22E-3 3.31E-2 6.20E-5 5.07E-4 Ci Particulates: Ci Strontium - 89 C1

  • 1.66E-5 8.18E-7 3.09E-6 Cesium - 137 Ci 1.74E-5 6.56E-5 1.40E-6 5.79E-6 Barium - 140 Ci * * * *

. Other (Specify) Ci Lanthanum - 140 Ci * * *

  • Niobium - 95 Ci *
  • 1.12E-7 9.31E-7 i Iron - 55 Ci 3.69E-10 4.27E-5 Cobalt - 58 Ci 3.20E-6 2.25E-6 5.50E-7 3.92E-6 Cobalt - 60 C1 4.51E-6 1.12E-5
  • 3.lbE-U
  • Less than lower limits of detection

TABLE IC EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

CASEOUS EFFLUENTS-GOUND-LEVEL RFT.RARES NORTH ANNA POWER STATION Page 2 of 2 l CONTINUOUS MODE BATCH MODE l NUCLIDES RELEASED UNIT Ist QUARTER 2nd QUARTER let QUARTER 2nd QUARTER j Particulates (cont): '

i Yttrium - 91 Ci

  • 1.79E-3 *
  • l Sodiam - 24 Ci *
  • 6.38E-7 5.I7E-6 Rubidium - 88 (T% < 8 days) Ci 5.64E-3 5.50E-2
  • a.

Rubidium - 89 (1% < 8 days) C1 4.75E-3 2.50E-2 3.73E-7

  • Tellurium - 131m (T% < 8 days) * *
  • Ci 4. 7f.E-5 Tellurium - 132 (Th < 8 days) Ci 8.65E-5 2.26E-4 *
  • Cesium - 138 (Th < 8 days) Ci 1.76E-2 9.40E-2 8.52E-4 4.41E-4 Ci Total For Period (Th > 8 days) Ci 2.54E-5 1.93E-3 2.88E-6 1.3BE-5 Total For Period (T% < 8 days) Ci 2.81E-2 1.74E-I 8.53E-4 4.46E-4 Total Por Period Ci 2.81E-2 I.76E-1 8.56E-4 4.60E-4 Ci GROSS ALPHA: Ci 1.71E-5 6.64E-5 a a

, Ci l TRITIUM: Ci 5.37E+0 2.ZIE+0 5.15E-3 3.04E-Z

} Ci I Ci Ci C1 Ci Ci Ci j Ci j Ci ~

Ci l Ci 4

I Ci Ci j Ci l '

Ci j Ci 1 Ci l Ci l Ci Ci l

j Ci __

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES NORTH ANNA POWER STATION EST. TOTAL UNIT lst QUARTER 2nd QUARTER ERROR % .

A. Fission & Activation Products

1. Total release (not including tritium, .

gases, alpha) Ci 1.34E-1 2.40E-1 1.50E+1

2. Average diluted concentration during perlod pCi/ml 1.90E-10 3.38E-10
3. Percent of applicable limit (T.S.)  % 4.55E-3 5.92E-3 B. ' Tritium
1. Total release activity. Ci 4.37E+2 4.01E+2 1.50E+1
2. Average diluted concentration during period. pC1/ml 6.21E-7 5.64E-7
3. Percent of applicable limit (T.S.)  % 2.07E-2 1.88E-2 C. Dissolved and entrained gases
1. Total release activity. Ci 6.05E-1 2.27E-1 1.50E+1
2. Average diluted concentration during period. UCi/ml 8.59E-10 3.20E-10
3. Percent of applicable limit (T.S.)  % 4.30E-4 1.60E-4 D. Cross Alpha Radioactivity
1. Total release activity. Ci <MDA <MDA 1.50E+1 1

E. Volume of waste released (prior to dilution) Liters 8.61E+7 7.69E+7 F. Volume of dilution water used during perfod Liters 7.04E+11 7.1IE+11

g TABLE 2B i EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1985)

{ LIQUID EFFLUENTS 1 NORTH ANNA POWER STATION Page 1 of 2 1

CONTINUOUS MODE BATCH HODE

NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER l Fission and Activation Products -

, Strontium - 89 Ci *

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Casium - 134- Ci 3.05E ,2 5.50E-2 1.09E-5

  • Casium - 137 Ci 6.14E-2 1.16E-1 2.40E-5 5.69E-6 1

Iodine - 131 Ci 6.32E-3 3.'32E-3 3.36E-5

  • Ccbalt - 58 Ci 1.59E-2 3.66E-3 1.28E-5 2.81E-4 Cebelt - 60 Ci 1.08E-2 2.32E-2 1. 33E-6 1.49E-3 i Iron - 59 Ci * * *
  • Zinc - 65 Ci * * *
  • Chromium - 51 Ci * * *
  • Manganese - 54 Ci
  • 5.67E-4 2.88E-8 l 8.79E-5

. Niobium - 95 Ci

  • 1.12E-3 1.71E-8 1.77E-5

! Zirconium - 95 Ci * * * * .

I Molybdenus - 99 Ci * * *

  • Tachsetic - 99 Ci *
  • 6.36E-6
  • Barium - 140 Ci * * *
  • Lcnthanum - 140 Ci * * *
  • a Carium - 141 Ci * * *
  • Other (Specify) Ci l Sodium - 24 C1 2.12E-3 1.40E-2 8.08E-6
  • l Ccbalt - 57 Ci *
  • 1.26E-8 7.87E-6
Silver - 110m C1 2.15E-4 5.46E-3 7.15E-8 5.26E-5 Antimony - 122 Ci ' l.93E-3 6.28E-3 2.94E-8
  • 1.19E-4
  • j Iodine.- 133 C1 3.33E-3 6.88E-3 2.16E-4
  • 1.20E-4
  • 1.72E-3 2.71E-4 *

} Tallurfua - 131m Ci *

  • 3.87E-6
  • 7.40E-5
  • Ci ,

C1 Ci

C1

} Ci

! Total for Period Ci 1.JJr.-1 z.Jan-1 v . u t e.-4 C94E-3 i a less than lower limits of detection

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I TABLE 3 (1/85 - 6/85) j- EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT ,

i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l 1

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) j 6-MONTH E51. IUTAL j 1. Type of Waste UNIT PERIOD ERROR, %

i a. Spent resins, filter sludges, m3 1.24E+2 1.0 E+1 evaporator bottoms, etc. C1 1.00E+2 1.0 E+1 l

b. Dry compressible waste, ma 1.40E+2 1.0 E+1 i coritaminated equipment, etc. Ci 1.28E+1 1.0 E+1

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

, d. Other(describe) m3 0. E . E i Ci 0. E . E

2. Estimate of major nuclide composition (by type of waste)
a. H 3  % 38.6 ,. 0 E+1 >

Ni 63 -  % 22.4 .. 0 E+1 Fe 55  % 12.95 1. 0 E+1  !

1 Co 60  % 6.8 1. 0 E+1 Cs 137  % 5.94 1. 0 E+1  ;

C 14  % 2.76 1. 0 E+1 q Cs 134  % 2.75 1. 0 E+1

! Cm 242  % 2.I1 1. O E+1

Co 58  % 1.72 1. 0 E +1 i Cm 244  % 1.02 1. 0 E+1 Pu 241  % 1.01 1. 0 E+1 ,

I 131  % .8 1. 0 E+1 i '

Mn 54  % .71 1. 0 E+1 -

! Sb 122  % .13 1. 0 E +1 Pu 239 .  % .08 1. 0 E+1 l

{ Ca 144  % .04 1. 0 E+1 4 la 140  % .03 1. O E +1 >

! Ba 140  % .03 1. O E + 1 Sr 90  %' .01 1. 0 E +1 l Xe 133  % .01 1. O E +1 j l Nb 95  % .007 1. 0 E +1 i i Zr 95  % .003 1. C E +1  !

! Pu 238  % .002 1. 0 E +1 I I Tc 99  % .001 1. O E +1 i

! I 129  % .0006 1. 0 E +1  !

l  % . E  !

b.  % . E [

Fe 55  % 51.05 1.OE+1 i H 3  % 15.1 1.OE+1 l Co 60  % 10.4 1.OE+1 l 4

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TABLE 3-CONTINUED PAGE 2

2. Estimate of major nuclide composition (by type of waste)
b. (con't)  % ,

. E Cs 137  % 5.1 1.0 E +1 Ce 144  % 5.08 _ 1 0 E +1 Ni 63  % 3.21 1.0 E +1 Pu 241  % 2.2 1 0 E +1 C 14  % 1.5 1.0 E +1 Cs 134  % 1.45 1 0 E +1 Zr 95  % 1.40 1 0 E +1 Nb 95  % 1.35 1.0 E +1 Co 58 _

Z 1.1 1.0 E +1 Sr 90  % 1.0 1 0 E +1

) On 242  % .5 1 0 E +1 Mn 54  % .3 1.0 E +1 Ru 103  % .1 1.0 E +1 Pu 238  % .01 1 0 E +1 Pu 239  % .01 1 0 E +1 Am 241  % .005 1 0 E +1 cm 243  % .003 1 0 E +1 cm 244  % .003 1.0 E +1 Sb 122  % .002 1 0 E +1 Tc 99  % .001 1 0 E +1 Pu 242  % .0009 1 0 E +1 I 129  % .000006 1 0 E +1

% . E

% . E

% . E

% . E

% . E

% . E

% . E

% . E

% . E

% . E

% . E
3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 32 Privste Vehicle Barnwell, SC B. IRRADIATEDFUELSHIPMENTS(Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION O

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

Page 5 i

j ATTACHMENT 2

(01/85-06/85)

REVISIONS TO OFFSITE CALCULATION MANUAL (00CM)

I i i No changes were made to the Offsite Dose Calculation

)

Manual (00CM) for the time period covered by this report.

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  • Page 6 ATTACHMENT 3 (01/85-06/85)

REVISIONS TO PROCESS CONTROL PROGRAM (PCP)

No changes were made to the Process Control Program (PCP) for the time period covered by this report.

Page 7 ATTACHMENT 4 (01/85-06/85)

MAJOR CHANGES TO RADIOACTIVE SOLID WASTE TREATMENT SYSTEMS

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

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ATTACHMENT 5 (01/85-06/85)

RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION INOPERABLE None of the radioactive effluent monitors met the requirements of Technical Specification 3.3.3.10.b and 3.3.3.11.b. for providing an account due to in' operability.

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I Page 9 ATTACHMENT 6 (01/85-06/85)

UNPLANNED RELEASES No unplanned releases, as defined according to the criteria presented in 10 CFR Part 50.73, occurred during the time period covered by this report.

VINGTNIA EtucTnic ann Pownu CourAxy Ricitwoxn,VinotNIA 20261 _;

e=

W.L.STnwAar N Vice Paastoswr O

Noctuaa Oramations m

I August .10, 1985 -

a l Dr. J. Nelson Grace Serial No.85-625" l Regional Administrator N0HP/FLT:pb U. S. Nuclear Regulatory Commission DocketNos.50-338b Region II 50-339 101 Marietta Street, Suite 2900 Licens? Nos. NPF-4 Atlanta, Georgia 30323 NPF-7

Dear Dr. Grace:

Enclosed is the Radioactive Effluent Release Report for Neeth Anna Power Station for the period January 1, 1985 to June 30, 1985.

Very truly yours, m

W. L. Stewart Enclosure (2 copies) cc: Mr. Edward J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing Mr. M. W. Branch NRC Resident Inspector North Anna Power Station DESIC ATED ogingygg, Certified OI 3 Oh hu () &&

Y> n' Syy

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