Text

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1985
	ML20215K264
Person / Time
Site:	North Anna
Issue date:	12/31/1985
From:	Barnes W, Hickman O, Stafford A; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20215K253	List: ML20215K250; ML20215K264; ML20215K268; ML20215K273;
References
	NUDOCS 8610280075
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SEMI-ANNUAL EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JULY 01, 1985 TO DECEMBER 31, 1985 PREPARED BY: ///[MO8.N+af[

William C. Barnes III' Assistant Supervisor Health Physics.

(Count Room & Environmental)

REVIEWED BY: d q,

O. E. Hickman, Jr. '//

Supverisor Health PNfsics (Technical Services)

REVIEWED BY: /

A~. H. Srafffyt!

Superintendent Health Ph sics APPROVED BY:

1 E. Wayne Harrpfl

/

Station Manager 8610280075 860228 PDR ADOCK 05000338'-

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FORWARD i

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

h7F-4 and hTF-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 9, i

i i

I 1

I I

r RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JULY 01, 1985 TO DECEMBER 31, 1985 INDEX SECTION NO.

SUBJECT PAGE 1

PURPOSE AND SCOPE.

1 2

DISCUSSION 1

3 SUPPLEMENTAL INFORMATION 3

........... Effluent Release Data 4

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

5

.............. Revisions to Offsite Dose Calculation Manual (ODCM) 6

.. Revisions to Process Control Program (PCP)......

7

. Major changes to Radioactive Solid Waste Treatment Systems 8

........................ Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Inoperable.

9

.............._ Unplanned Releases.

10

]

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Page 1 1.0 PURPOSE AND SCOPE i

The Radioactive Effluent Release Report' includes a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting 1

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 I

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 ODCM changed.

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

l 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 sumary 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.

l As required by Technical Specification 3.3.3.10.b and 3.3.3.11.b a list l

and explanation for the inoperability of radioactive liquid and/or gaseous i

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.

1

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

The basis for the calculation of percent of technical specification for the total body and skin in Table 1A 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 calculation of the percent of technical specification in Table 2A is Technical Spec.ification 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/nl.

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

I l

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.

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

Page 4 ATTACHMENT 1 EFFLUENT RELEASE DATA 7/85 - 12/85 This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste, l

as outlined in Regulatory Guide 1.21.

l

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

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NORTH ANNA POWER STATION i

EST. TOTAL UNITS 3rd QUARTER 4th QUARTER

% ERROR A.

Fission and Activation Gases:

1.

Total Release Ci 6.69E+3 1.05E+3

1. 50E+1 2.

Average Release Rate for Period pCi/sec 8.42E+2 1.32E+2 B.

Iodines:

i 1.

Total Iodine-131 Release Ci 1.53E-2 6.22E-3 1.50E+1 2.

Average Release Rate for Period:

pCi/sec 1.92E-3 7.83E-4 C.

PARTICULATES (Th < 8 days) 7 1

1.

Total Particulate (T < 8 days) Release Ci 5.69E-3 1.34E-2 1.50E+1 2.

Average Release Rate for Period pCi/sec 7.16E-4 1.69E-3 3.

Cross Alpha Radioactivity Release Ci 1.64E-5 1.65E-4 1

e D.

Tritium:

i 1.

Total Release Ci 1.25E-1 1.12E+0 1.50E+1 2.

Average Release Rate for Period pCi/see 1.57E-2 1.41E-1 j

4 i

E.

Percentage of Technical Specificaiton Limits:

1.

Total Body Dose Rate 5.94E-1 1.75E-1 f:I 2.

Skin Dose Rate 2.17E-1 4.92E-2

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Critical Organ Dose Rate 1.89E-2 7.95E-3 I

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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 3rd QUARTER 4th QUARTER

% ERROR A.

Fission & Activation Products 1.

Total release (not including tritium, gases, alpha)

C1 3.96E+0 7.31E-1 1.50i+1 2.

Average diluted concentration during period uCi/ml 5.18E-9 1.31E-9 3.

Percent of applicable limit (T.S.)

3.55E-1 1.89E-2 B.

Tritium 1.

Total release activity.

Ci 3.77E+2 2.66E+2 1.50E+1 2.

Average diluted concentration during period.

UCi/ml 4.93E-7 4.77E-7 3.

Percent of applicable limit (T.S.)

'l.64E-2 1.59E-2 l

C.

Dissolved and entrained gases 1.

Total release activity.

Ci 1.41E+0 2.90E-1 1.50E+1 2.

Average diluted concentration during i

period, pCi/ml 1.85E-9 5.21E-10 3.

Percent of applicable limit (T.S.)

6.15E-5 1.74E-5 D.

Gross Alpha Radioactivity 1.

Total release activity.

Ci 7.87E-4

< LLD 1.50E+1 E.

Volume of waste released (prior to dilution)

Liters 8.30E+7 6.85E+7 i

l F.

Volume of dilution water used during period Liters 7.64E+11 5.57E+11

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

LIQUID EFFLUENTS NORTH ANNA POWER STATION Page 1 of 2 i

CONTINUOUS MODE BATCH MODE I

NUCLIDES RELEASED UNIT 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER Fission and Activation Products l

Strontium - 89 Ci 8.02E-3 l

Strontium - 90 Ci Cesium - 134 Ci 3.80E-1 1.80E-1 2.01E-6 2.20E-6 Cesium - 137 Ci 8.llE-1 3.32E-1 6.07E-6 1.06E-5 l

Iodine - 131 C1 3.87E-1 8.70E-3 1.72E-8 1.43E-7 Cobalt - 58 Ci 1.46E-2 3.29E-2 7.46E-9 3.86E-7 l

Cobalt - 60 Ci 1.04E-2 1.83E-2 8.22E-10 9.36E-6 Iron - 59 Ci Zinc - 65 Ci Chromium - 51 Ci 2.31E-3 9.61E-8 Manganese - 54 Ci 2.49E-3 2.50E-3 1.17E-9 5.51E-8 Niobium - 95 Ci 8.16E-5 5.50E-4 1.09E-8 Zirconium - 95 Ci 8.48E-5 Molybdenum - 99 Ci 1.57E-8 Technetium - 99 Ci 3.75E-3 1.77E-4 1.33E-8 Barium - 140 Ci 1.18E-2 2.43E-4 3.53E-7 Lanthanum - 140 Ci 1.06E-2 5.56E-3 Cerium - 141 Ci Other (Specify)

Ci Phosphorus - 32 Ci Iron - 55 Ci 1.54E-1 Strontium - 91 Ci 8.21E-4 Silver - 110m Ci 1.34E-4 9.88E-4 3.54E-8 Antimony - 124 C1 2.96E-4 2.24E-3 Cesiun - 136 Ci 8.07E-3 3.75E-3 Iodine - 130 Ci 3.15E-4 Iodine - 132 Ci 9.34E-2 5.15E-8 Iodine - 133 C1 1.17E+0 8.77E-3 7.38E-8 Iodine - 134 Ci 8.69E-3 1.28E-4 3.92E-8 Iodine - 135 Ci 5.65E-1 1.57E-3 1.28E-7 l

Sodium - 24 Ci 2.08E-1 1.10E-1 3.98E-8 Antimony - 122 Ci 4.llE-2 2.05E-2 2.68E-7 Tellurium - 131m Ci 6.70E-4 Lanthanum - 142 Ci 7.35E-2 j

Ci Total for Period Ci 3.96E+0 7.31E-1 8.47E-6 2.35E-5

less than lower limits of detection

2 fo R

2 ET e

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f TABLE 3 (7/85 - 12/85)

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) l 1.

Type of Waste UNIT E OD ERRbR %

a.

Spent resins, filter sludges, m3 1.37E+2 1.0 E+1 evaporator bottoms, etc.

Ci 1.25E+2 1.0 E+1 I

b.

Dry compressible waste, m3 2.01E+2 1.0 E+1 contaminated equipment, etc.

Ci 4.89E+1 1.0 E+1 c.

Irradiated components, control m3 E

E rods, etc.

Ci E

E d.

Other (describe) m3 4.80E+1 1.0 E+1 Absorbed Oil Ci 3.13E+0 1.0 E+1 2.

Estimate of major nuclide composition (by type of waste)

a. H 3 28.99%

1.0 E+1 Cs 137 15.84%

1.0 E+1 Ni 63 14.97%

1.0 E+1 Cs 134 10.95%

1.0 E+1 Fe 55 9.50%

1.0 E+1 Co 60 5.51%

1.0 E+1 l

Co 58 5.07%

1.0 E+1 l

Cm 242 3.94%

1.0 E+1 Cm 244 2.04%

1.0 E+1 l

Mn 54 1.27%

1.0 E+1 Pu 241 1.18%

1.0 E+1 Sb 122 0.73%

1.0 E+1 Pu 239 0.01%

1.0 E+1 E

E E

b. Fe 55 64.41%

1.0 E+1 H 3 9.69%

1.0 E+1 Co 60 7.76%

1.0 E+1 Pu 241 5.85%

1.0 E+1 Cs 137 4.72%

1.0 E+1 l

C 14 2.88%

1.0 E+1 Sr 90 1.78%

1.0 E+1 Cs 134 1.76%

1.0 E+1 1

Ni 63 0.57%

1.0 E+1 l

l Mn 54 0.32%

1.0 E+1 Cm 242 0.19%

1.0 E+1 Tc 99 0.1 %

1.0 E+1 E

c. None E

e

1 TABLE 3-CONTINUED PAGE 2 1

\\

2.

Estimate of major nuclide composition (by type of waste)'

d.

Fe 55 76.54 %

1.0 E+1 Ni 63 11.63 %

1.0 E+1 Pu 241 10.28 %.

1.0 E+1 -

C 14 1.23 %

1.0 E+1 H 3 0.10 %,

1.0 E+1 Pu 238 0.08 %

1.0 E+1 Pu 239 0.04.%

1.0 E+1 1

Cs 137 0.03 %

1.0 E+1 Cm 242 0.01 %

1.0 E+1 E

E

~%

E.

~

E E

~

E E

E

l

~

E

~

E E

E E-E E

'~

E I

E E

E

-E

.E T

E 3.

Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION

' DESTINATION 27 Private Vehicle Barnwell, SC 2

Private Vehicle Richland, WA B.

IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None

Page 5 1

i ATTACHMENT 2 I

ANNUAL AND QUARTERLY DOSES (1/85 - 12/85)

)

l This attachment includes an assessment of radiation doses to the I

maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site.

l

Liquid Effluents:

1st 2nd 3rd 4th Annual-Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 0.08 0.15 0.47 0.56 1.26 Critical Organ Dose (mrem) 0.11 0.21 0.66 0.78 1.76 Caseous Effluents:

1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 0.04 0.18 0.88 0.27 1.37 Noble Gas Beta Dose (mrad) 0.03 0.12 2.14 0.33 2.62 Critical Organ Dose for I-131, H-3, Particulates 0.03 0.10 0.83 0.29 1.25 with T < 8 days (mrem) 2

Page 6 l

I l

l ATTACHMENT 3 (7/85 - 12/85)

REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

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

Supporting documentation and affected pages of the ODCM are attached.

i l

l 12-19-85:

Revisions were made to the ODCM to reflect the capability to throttle the circulating water pump discharge valves.

I I

ML20215K264

Text

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