ML20064A254

Radioactive Effluent Release Rept,North Anna Power Station,Jan-June 1990

ML20064A254
Person / Time
Site:	North Anna
Issue date:	06/30/1990
From:	Mary Johnson, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-497, NUDOCS 9008270267
Download: ML20064A254 (31)

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s VIRGINIA ELECTRIC AND POWER . COMPANY RICHMOND, VIRGINIA 202 63 August 20,1990 '

I U.S. Nuclear Regulatory Commission Serial No. 90-497=

Attention: Document Control Desk - NAPS /JHL Washington, D.C. /20555 l Docket Nos. 50-338' 50-339

. License Nos.' NPF N PF u Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2

. SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 4 JANUARY-JUNE 1990 l 1

Pursuant to Technical Specification 6.9.1.9, attached is the North Anna Power Station -

Semi-A.anual Radioactive Effluent Release Report for the period of January 1,1990 to' .j; Junc 30,1990. j

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

Very truly yours, 1 l

MLM W. L.~ Stewart l

Senior Vice President - Nuclear 1

' Attachment cc: 'U.S. Nuclear Regulatory Commission Region ll {

101 Marietta Street, N.W. i Suite 2900 l

' Atlanta, Georgia 30323  ;

L 3 Mr. M. S. Lesser '

- NRC Senior Resident inspector North Anna Power Station 9009270267 700630 PDR ADOCK 05000338 PDQ R  ;

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RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION

- (JANUARY 01, 1990 TO JUNE 30, 1990)

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PREPARED BY: h _% _

Supervisor- O [

Radiological Analysis REVIEWED BY:

• Supervisor Technical Services APPROVED BY: -

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Superintendent Radiological Prot ection r

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ThisL! report is submitted as required by Appendix A to operating License j

ri Nos. NPF-4 , and NPF-7; Technical Specifications for North Anna! Power - .

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. Station, Units 1 and 2, Virginia Electric' and ~ Power Company,' Docket -;

[' Nos. 50-338, 50-339, Section 6.9.1.9.

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r l-I RADIOACTIVE EFFLUENT RELEASE REPORT POR -THE NORTH ANNA POWER STATION (JANUARY 01, 1990 TO JUNE 30, 1990)

INDEX Section No. Subject Page 1 PURPOSE AND SCOPE....................... 1-2 2 DISCUSSION............................... 2-5 3 SUPPLEMENTAL INFORMATION................ 5 Attachment 1 -

Effluent Release Data.................... 6 Attachment 2 -

A ;.ual and Quarterly Doses. . . . . . . . . . . . . . . 7 Attachment 3 -

Revisions to Offsite Dose Calculation Manual (ODCM)............................ 8 Attachment 4 -

Revisions to Process Control Program '

(PCP).................................... 9 Attachment 5 -

Major changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems.................................. 10 Attachment 6 -

Inoperability of Radioactive Liquid and Gaseous Effluent Instrumentation........ 11-14 Attachment 7 -

Uplanned Releases....... 4 ............... 15 Attachment 8 -

Lower Limits of Detection (LLD) for Effluent Sample Analysis................ 16-17 l

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Page 1 1.0 PURPOSE AND SCOPE The Radioactive Effluent Release Report includes in Attachment 1, a summary of the quantities of radioactive liquid.and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21,

" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and  :

Gaseous Effluents of 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 3 of Appendix B thereof. The report submitted within 60 days after January ,

1 of each year includes an assessment of radiation doses to the maxiuum 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 after 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 7.

As required by Technical Specification 6.15.2 changes to the ODCM for the time period covered by this report are included in Attachment 3. 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 6.14.1, in Attachment i 4.

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Page 2 1;0 PURPOSE AND SCOPE (cont.)

Major changes to radioactive liquid, gaseous.and solid waste treatment systems are reported in Attachment 5, as required-by Technical Specification 6.16. Information to support the reason (s) for the change (s) and-a summary of the 10 CFR 50.59 cvaluation 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.

As required by Technical Specification 3.3.3.10.b and 3.3.3.11.b, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitors are .

provided in this report, in Attachment 6.

2.0 DISCUSSION The basis for the calculation of the percent of technical specification for the critical organ in Table 1A of Attachment 1, is Technical Specification 3.ll.2.1.b. Technical Specification 3.ll.2.1.b requires that the dose rate for iodine-131, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall '

be less than or equal to 1500 mrem /yr to the critical organ at or beyond the site boundary. The critical organ is the t.

child's thyroid; inhalation pathway.

o l- 1 The basis for the calculation of percent of technical specification for the total body and skin in Table 1A of

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Attachment 1, is Technical Specification 3.11.2.1.a. Technical i Specification 3.11.2.1.a requires that the dose rate for noble  !

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Page 3 2.0 DISCUSSION (cont.)

gases to areas at or beyond site boundary shall be less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.

The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1, is Technical Specification 3.11.1.1. Technical Specification 3.11.1.1 states that the - concentration of radioactive material released in 14, quid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the l concentration shall be limited to 2.0E-4'microcuries/ml. }

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

The annual and quarterly doses, as reported in Attachment 2 of the report submitted within 60 days after January 1 of each year, are calculated according to the methodology presented I'

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 from the releases of

-airborne iodine-131, tritium and all radionuclides in particulate form with half-lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid. The

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r Page 4 2.0 DISCUSSION (cont.)

maximum exposed member of the public from radioactive materials I in liquid effluents in unrestricted areas is 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. .

Unplanned releases presented in Attachment 7 are defined j according to the criteria presented in 10 CPR 50.73, as those j gaseous radioactive releases that exceed 2' times the applicable concentrations of the limits specified in Appendix B, Table 11, of 10 CFR 20 in unrestricted areas, when averaged over a time period of one hour, and/or as those liquid radioactive releases that exceed 2 times the limiting combined Maximum Permissible Concentration (MPC) specified in Appendix B, Table II, of 10 CFR 20 in unrestricted areas for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.

The typical Lower Limit of- Detection' (LLD). capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 8. These Lower Limit of Detection values are based upon conservative conditions (i.e., minimum sample volume and maximum delay time prior to analysis). Actual Lower Limit of Detection values may be lower. If a radioisotope is not detected when analyzing effluent samples, then the activity of the radiolosotope will be reported as Not Detectable (N/D)

Page 5 l:

2.0 DISCUSSIONS (cont.)

on Attachment 1 of this report. When all radioisotopes listed on Attachment 1 for a particular quarter and release mode are less than the Lower Limits of Detection, teen the totals for this period will be designated as Not Applicable (N/A).

3.0 SUPPLEMENTAL INFORFATION As required by Technical Specification 3.12.2 and 6.9.1.9, Evaluation of the Land Use Census is to be made for identifying the new location (s) for dose calculation 3.12.2 requirements.

No ' new location (s) for dose calculations and/or environmental monitoring pursuant to Technical Specification 3.12.2 requirements were identified by the evaluation of the Land Use Census conducted during 1989.

As required by Technical Specification 3.12.1.c., the identification of the causes of the unavailability of milk or_ leafy vegetation samples, required by Technical Specification Table 4.12-1, and the identification of the new location (s) for obtaining replacement samples are listed. No unavailability of milk or green leafy vegetation samples, as required by Technical Specification Table j 4.12-1, occurred during the time period covered by this report.

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Page 6 ATTACHMENT 1 EFFLIIENT RELEASE DATA (01/90 -

06/90) '

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This attachment includes a summary of the quantities of 1 radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21.

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I TABLE 1A .

NORT71 ANNA POWER STATION

• SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR lst and 2nd QUARTER 1990

~

ESTIMATED TOTAL UNITS lst QUARTER 2nd QUARTER PERCENT ERROR (%)

A. Fission and Activation Gases:

1. Total Release. Curies 2.29E+2 2.02E+2 1.8E+1

2. Average Release Rate for Period. pC1/see 2.94E+1 2.57E+1 B. Iodines:

1. Total Iodine-131 Release. Curies 3.29E-4 2.48E-4 2.8E+1

2. Average Release Rate for Period. pCi/see 4.23E-5 3.15E-5 C. PARTICULATES (T > 8 days):

1. Total Particulate (T > 8 days) Release. Curies 9.07E-5 2.72E-5 2.8E+1

2. Average Release Rate for Period. pCi/sec l* 1.17E-5 3.46E-6

3. Gross Alpha Radioactivity Release. Curies 4.71E-10 N/D D. Tritium:

1. Total Release. Curies 2.04E+1 4.39E-1 3.1E+1-

2. Average Release Rate for Period. uCi/sec 2.62E0 5.58E-2 E. Percentage of Technical Specification Limits:

1. Total Body Dose Rate. I 5.91E-3 5.33E-3

2. Skin Dose Rate.  % 2.15E-3 1.86E-3

3. Critical Organ Dose Rate. I 2.23E-3 3.10E-4 N/D is Not Detectable & N/A is Not Applicable ,

TABLE IB

• NORTH ANNA POWER STATION ,

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR 1990 .

Page 1 of 2 CONTINUOUS MODE BATCH MODE .

NUCLIDES RELEASED UNITS QUARTER 2nd QUARTER 1st QUARTER 2nd-QUARTER Fission und Activation Gases:

Krypton - 85 Ci N/D N/D 3.63E-1 N/D 1.28E-2 Krypton - 85m Ci N/D N/D 2.36E-2 Krypton - 87 Ci N/D N/D 3.61E-3 1.46E-2 Krypton - 88 Ci N/D N/D 1.84E-2 2.01E-2 '

Xenon - 131m Ci N/D N/D 8.29E-1 w/D Xenon - 133 Ci 1.62E+2 1.72E+2 5.39E+1 2.53E-1 Xenon - 133m C1 2.98E-1 N/D 5.36E-1 5.48E-3 Xenon - 135 Ci 1.97E0 1.96EO 7.30E-1 8.87E-2 i Xenon - 135m Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N(D Other (Specify)

Argon - 41 Ci N/D N/D 1.50E-2 6.03E-2 Total for Period Ci 1.64E+2 1.74E+2 5.64E+1 4.59E-1 Iodines:

Iodine - 130 Ci N/D N/D N/A N/A Iodine - 131 Ci 5,95E-6 1.31E-5 N/A N/A Iodine - '

132 Ci N/D N/D N/A N/A Iodine - 133 Ci 3.21E-6 9.15E-6 N/A N/A Iodine - 134 Ci N/D N/D N/A N/A j Iodine - 135 Ci N/D N/D N/A N/A l Total for Period Ci 9.7.7E-6 2.23E-5 N/A N/A I Particulates:

_ Manganese - 54 Ci N/D N/D N/A N/A

( Iron - 55 Ci 1.66E-6 1.39E-6 N/A N/A Cobalt - 58 C1 2.23E-8 2.20E-8 N/A N/A Iron - 59 Ci N/D N/D N/A N/A Cobalt - 60 Ci 1.14E-5 4.82E-6 N/A N/A Zinc - 65 C1 4.02E-8 N/D N/A N/A Strontium - 89 Ci N/D N/D N/A N/A Strontium - 90 Ci N/D N/D N/A N/A Molybdenum - 99 Ci N/D N/D N/A N/A Silver - 110m Ci N/D N/D N/A N/A N/D is Not Detectable & N/A is Not Applicable

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

TABLE IB '

NORTH ANNA POWER STATION .

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR 1990 .

Page 2 of 2 .

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNITS ist QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER-Particulates (cont): ,

Cesium - 134 Ci 3.05E-6 1.38E-6 N/A N/A Cesium - 136 Ci N/D N/D N/A N/A ~

Cesium - 137 Ci 9.G8E-6 4.62E-6 N/A N/A Barium - 140 Ci N/D N/D N/A N/A Cerium - 141 C1 N/D N/D N/A N/A i Cerium - 144 Ci N/D N/D N/A N/A '

Other (Specify) Stronium - 85 Ci 3.56E-9 N/D N/A N/A Sodium - 24 (T < 8 days) Ci N/D N/D N/A N/A Rubidium - 88 (T < 8 days) Ci N/D N/D N/A N/A Rubidium - 89 (T < 8 days) Ci N/D N/D N/A N/A Technetium - 99m (T < 8 days) C1 N/D N/D N/A N/A  ;

Antimony - 122 (T < 8 days) Ci 3.30E-7 4.51E-8 N/A N/A Tellurium - 131m (T < 8 days) di N/D N/D N/A N/A Cesium - 138 (T < 8 days) Ci N/D N/D N/A N/A Total for Period (T > 8 days) Ci 2.53E-5 1.23E-5 N/A N/A Total for Period (T < 8 days) C1 3.30E-7 4.51E-8 N/A N/A l

Total for Period Ci 2.56E-5 1.09E-5 N/A N/A GROSS ALPHA: Ci 4.71E-10 N/D N/A N/A TRITIUM: Ci 4.19E-1 4.37E-1 2.83E-4 3.29E-5 1

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

- -. -- _ _ .- ____ - . _ _ . - . _ - _ _ _ - _ . _ _ _ _ _ _ = _ _ _ _ _ _ - - _ - _ _ _ - _ _ _ _ -

TABLE IC -

NORTH ANNA POWER STATION .

SEMI-ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT l GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1990 ,

Page 1 of 2 CONTINUOUS MODE BATCH MODE ,

NUCLIDES RELEASED UNITS 1st QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER Fission and Activation Gases:

Krypton - 85 Ci N/D N/D 8. ole-6 5.38E-2

• Krypton - 85m Ci 1.01E-2 2.79E-2 N/D 2.67E-2 I

Krypton - 87 Ci 8.64E-3 3.18E-2 N/D 9.19E-6 l Krypton - 88 Ci 1.35E-2 3.61E-2 N/D 8.56E-4

• Xenon - 131m Ci N/D N/D N/D 1.27E-1 Xenon - 133 Ci 2.02E-1 1.83E+1 N/D 7.57E0 Xenon - 133m Ci N/D N/D N/D 8.22E-2 Xenon - 135 Ci 7.23E0 3.42E-1 N/D 2.75E-1 Xenon - 135m Ci 1.50E-1 2.52E-1 .

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N/D N/D Xenon - 138 Ci 6.0?E-3 3.71E-2 N/D N/D Other (Specify)

Argon - 41 Ci 2.15E-1 5.35E-1 N/D 1.59E-3 Total for Period Ci 7.83E0 1.95E+1 8. ole-6 8.14E0 Iodines:

Iodine - 130 Ci N/D N/D N/D N/D

lodine - 131 C1 3.23E-4 2.35E-4 2.51E-8 8.97E-9 Iodine - 132 Ci N/D N/D 9.70E-8 1.63E-8 Iodine - 133 Ci 6.55E-4 4.31E-4 1.82E-7 4.12E-8 i lodine - 134 Ci N/D N/D 1.70E-9 1.26E-8 Iodine - 135 Ci N/D N/D 1.91E-7 2.46E-8 Total for Period Ci 9.78E-4 6.66E-4 4.97E-7 1.04E-7 Particulates

Manganese - 54 Ci N/D N/D 2.78E-10 N/D Iron - 55 Ci 6.40E-5 N/D N/A N/D Cobalt - 58 Ci 1.31E-5 5.55E-6 7.42E-9 4.78E-10 Cobalt - 60 Ci 5.21E-5 9.34E-6 9.43E-8 5.14E-9 Strontium - 89 Ci N/D N/D N/A N/D Strontium - 90 Ci N/D N/D N/A N/D Silver - Il0m Ci N/D N/D N/D N/D Cesium - 134 Ci N/D N/D 5.88E-9 N/D Cesium - 136 Ci N/D N/D N/D N/D Cesium - 137 Ci t 1.74E-6 N/D 4.05E-8 2.13 E-9 N/D is Not Detectable & N/A is Not Applicable

TABLE IC ~

NORTH ANNA POWER STATION .

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEQUS EFFLUENT RELEASES FOR 1990 .

Page 2 of 2 l

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNITS lst QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER Particulates (cont): ^

Barium - 140 Ci N/D N/D N/D N/D i

Niobium - 95 Ci N/D N/D N/D N/D Strontium - 85 C1 N/D N/D N/D N/D ~

1ron - 59 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Molybdenum - 99 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (Specify)

Sodium - 24 (T < 8 days) Ci N/D N/D 4.13E-9 N/D Rubidium - 88 (T < 8 days) Ci N/D N/D N/D N/D Rubidium - 89 (T < 8 days) Ci N/D N/D N/D N/D Technetium - 99m (Th < 8 days) Ci N/D N/D N/D N/D Antimony - 122 (Th < 8 days) Ci N/D N/D N/D 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 N/D Cerium - 143 (T < 8 days) Ci N/D N/D N/D N/D Total For Period (T > 8 days) Ci 1.31E-4 1.49E-5 1.48E-7 7.75E-9 Total for Period (T < 8 days) Ci N/A N/A 4.13E-9 N/A Total for Period Ci 1.31E-4 1.49E-5 1.52E-7 7.75E-9 GROSS ALPHA: Ci N/D N/D N/A N/A TRITIUM: C1 2.0E+1 6.82E-6 2.67E-3 1.85E-3 i

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

TABLE 2A EFFLUENT AND WASTE DISPOSAL SDil-ANNUAL REPORT (1990) ,

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 2.11E-1 1.11E-1 2.0E+1

2. Average diluted concentration during period. pCi/ml 3.30E-10 1.37E-10

3. Percent of applicable limit (T.S.).  % 2.10E-3 2.35E-3 B. Tritium

1. Total release activity. Ci 5.36E+2 4.31E+2 2.0E+1

2. Average diluted concentration during period. pCi/ml 8.40E-7 5.33E-7

3. Percent of applicable limit (T.S.). I 2.80E-2 1.78E-2 C. Dissolved and entrained gases

1. Total release activity. Ci 1.32E+1 7.02E0 2.0E+1

2. Average diluted concentration during

, period. pCi/ml 2.07E-8 8.69E-9 l,

3. Percent of applicable limit (T.S.).  % 1.03E-2 4.34E-3 l

l D. Cross Alpha Radioacti [g[

1. Total release activity. -

Ci N/D N/D 2.0E+1 j' E. Volume of waste released (prior to dilution) Liters 9.17E+7 9.10E+7 3.0E0

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F. Volume of dilution water used during period Liters 6.38E+11 8.08E+11 3.0E0 l

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

-5 TABLE 2B NORTH ANNA POWER STATION .

SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR 1990 .

Page 1 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNITS lst QUARTER 2nd QUARTER 1st QUARTER 2nd' QUARTER I Fission and Activation Products:

Manganese - 54 C1 4.96E-3 7.31E-4 N/A N/A Iron - 55 Ci N/D N/D N/A N/A Cobalt - 58 Ci 3.51E-2 2.33E-2 N/A N/A '

Cobalt - 60 C1 1.36E-1 6.31E-2 N/A N/A

' N/A N/A Strontium - 89 Ci N/D N/D Strontium - 90 Ci N/D N/D N/A N/A Silver - 110m Ci 1.23E-2 4.13E-3 N/A N/A Iodine - 131 C1 1.53E-3 2.97E-3 N/A N/A Iodine - 132 Ci N/D N/D N/A N/A l Iodine - 133 '

Ci 3.16E-3 6.34E-3 N/A N/A Iodine - 134 Ci N/D N/D N/A N/A Iodine - 135 Ci N/D N/D N/A N/A Cesium - 134 Ci N/D 3.92E-4 N/A N/A i Cesium - 136 Ci N/D N/D N/A N/A Cesium - 137 C1 9.94E-4 2.17E-3 N/A N/A i Cerium - 144 Ci N/D N/D N/A N/A Niobium - 95 C1 2.88E-3 8.60E-4 N/A N/A Zirconium - 95 Ci N/D N/D N/A N/A Chromium - 51 C1 1.53E-3 1.62E-3 N/A N/A Iron - 59 Ci 4.77E-4 N/D N/A N/A Rhodium / Ruthenium - 106 Ci N/D N/D N/A N/A Antimony - 124 Ci N/D N/D N/A N/A Antimony - 125 C1 1.06E-2 5.48E-3 N/A N/A Cesium - 138 Ci N/D N/D N/A N/A Zinc - 69m Ci N/D N/D N/A N/A Zinc - 65 Ci 9.20E-5 N/D N/A N/A Copper - 64 C1 N/D N/D N/A N/A Other (specify) Br - 84 Ci 1.59E-4 N/D N/A N/A Sodium - 24 (T < 8 days) Ci N/D N/D N/A N/A Technetium - 99m (Th < 8 days) Ci N/D N/D N/A N/A l Antimony - 122 (Th < 8 days) Ci N/D N/D N/A N/A Lanthanum - 140 (T < 8 days) Ci N/D N/D N/A N/A Barium - 139 Ci 1.24E-3 N/D N/A N/A Strontium - 85 C1 1.40E-4 N/D N/A N/A Total for Period C1 2.llE-1 1.11E-1 N/A N/A N/D is Not Detectable & N/A is Not Applicable

TABLE 2B _

NORTH ANNA POWER STATION .

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR 1990 .

Page 2 of 2

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CorTINUGUS MODE BATCH MODE NUCLIDES RELEASED UNITS lst QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER Dissolved and Entrained Noble Gases: ~

Xenon - 131m Ci 1.81E-1 7.91E-2 N/A N/A Xenon - 133 C1 1.29E+1 6.90E0 N/A N/A Xenon - 133m Ci 6.51E-2 3.34E-2 N/A N/A ,

Xenon - 135 C1 1.67E-2 1.08E-2 N/A N/A --

Xenon - 135m Ci 4.94E-5 1.57E-4 N/A N/A Other (Specify) Krypton - 85 Ci 3.23E-2 N/D N/A N/A Argon - 41 Ci N/D N/D N/A N/A Total for Period: Ci 1.32E+1 7.02E0 N/A N/A Tritium Ci 5.36E+2 4.31E+2 N/A N/A Gross Alpha Ci N/D N/D N/A N/A N/D is Not Detectable & N/A is Not Applicable

L .,

L TABLE 3 NORTH AGIPDER STATION RADI0 ACTIVE EFFLUENT RELEASE REPORT Su mATION OF SOLID RADI0 ACTIVE WA5TE AND IRRADIAltu FUEL SHIPMENTS FOR 01/01/90 THROUGH 06/30/90 Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATE _D FUEL) 6-MONTH ESTIMATED TOTAL  !

1. Type of Waste UNIT PERIOD PERCENTERROR(%)

a. Spent resins, filter sludges, m3 5.30E+1 2.50E+1 evaporator bottoms, etc. . C1 3.05E+2 2.50E+1 Dry compressible waste, 1.70E+2* 2.50E+1  !

b. m3 contaminated equipment, etc. Ci 1.04E0 2.50E+1  !

c. Irradiated components, control m3 0.00E0 0.00E0 ,

rods, etc.- Ci 0.00E0 0.00E0  ;

i

d. Other(describe) m3 0.00E0 0.00E0 i Ci 0.00E0 0.00E0 i

l

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

a. Ni - 63  % 4.54E+1 2.50E+1 k Co - 60  % 2.88E+1 2.50E+1  !

( Fe - f5  % 1.51E+1 2.50E+1  ?

Co - 58  % 2.62E0 2.50E+1

~ '

Cs - 137  % 2.39E0 2.50E+1

!. Ce - 144  % 2.07E0 2.50E+1 i

Cs - 134  % 1.25E0 2.50E+1

b. Fe - 55  % 4.17E+1 2.50E+1 Co - 60  % 3.34E+1 2.50E+1

! Cs - 137  % 1.14E+1 2.50E+1 ~

1' Ni - 63  % 5.86E0 2.50E+1 Cs - 134  % 3.63E0 2.50E+1 Mn - 54  % 1.39E0 2.50E+1 Sb - 125  % 1.31E0 2.50E+1 T

TABLE 3 NORTH A@O%TR STATION RADI0 ACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADI0 ACTIVE WA5TE AND IRRADIAIED FUEL SHIPMENTS FOR 01/01/90 THROUGH 06/30/90 Page 2 of 2

2. Estimate of major nuclide composition (b 6-MONTH ESTIMATED TOTAL waste) (con.t)y type of UNil PERIOD PERCENT ERROR (%)

c. NONE  % .E . E

% . E . E

% . E . E

% . E . E

% . E . E

% . E . E

d. NONE  % . E . E

% . E . E l

% . E . E

% . E . E

%- . E . E

% . E . E

% . E . E

% . E . E

% . E . E-

~ ~ ~ ' '

% . E . E

~~

% . E . E

~~

% . E . E i

% . E . E I

"~  % E E

% ? E . E

% . E . E l

3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 8 Truck Barnwell, SC 5 Truck Oak Ridge, TN (SEG)

L B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION O N/A N/A l..

• 5 shipments of Dry Compressible waste were shipped from North Anna to a t-

! licensed waste processor for Volume Reduction. Therefore, the volume as listed for this type is not representative of the actual volume buried. The total volume buried for the reporting period was 32.24 m3

I

,, Pcga 7 ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/90 -

06/90) ,

i An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year for this report along with an annual total of each effluent pathway will be made pursuant to Technical Specification 6.9.1.9'in the Radioactive Effluent Release Report submitted within ,

sixty (60) days after January 01, 1991.

[

r,

, d ,

u 9 Page 8 ATTACHMENT 3 (01/90 -

06/90)

TIEVISIONS 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 effected pages of the ODCM are attached.

The Offsite Dose Calculation Manual has been rewritten to include the Radiological Effluent Technical Specifications-per Generic Letter 89-01. The content is unchanged, it j has only been reformatted and relocated to Virginia Power Administrative Procedure VPAP-2103. The revised documents are not included here as they were attached to our response to the Generic Letter, Serial Number 90-234 dated May 21, 1990. l l

1 1

i

Page 9 ATTAP.HMENT 4 (01/90 -

06/90)

REVISIONS TO PROCESS CONTROL PROGRAM (PCP)

As required'by Technical Specification 6.14, revisions to the PCP for the time period covered by this report are synopsized below. Supporting documentation and effected.

pages of the PCP are attached.

t I

i.

The. Process Control Program has been rewritten to include the Radiological Effluent Technical Specifications per Generic Letter 89-01. The content is unchanged, it has only been reformatted and relocated to Virginia Power' I Administrative Procedure VPAP-2104. The revised documents-are not included here as they were attached to our response to the Generic Letter, Serial Number 90-234 ,

dated May 21, 1990.

i ,

Pogs 10 t

ATTACHMENT 5 (01/90 -

06/90) i I

MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS I

L As required by Technical Specification 6.16, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are reported below. Supporting information as to the reason (s) for'the change (s) and a summary of the 10 CFR Part 50.59 evaluation are included.

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

l i

i l

I r _44 -u . .

h Page 11 r

ATTACHMENT 6 (01/90 -

06/90)

IMOPERABILITY OF RADIOACTIVE LIQUID AND GASBOUS EFFLUENT INSTRUMENTATION t

As required by Technical Specification 3.3.3.10.b'and 3.3.3.11.b, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitors is provided in this report.

Liquid Waste Proportional Sampling System The liquid waste proportional sampling pump, 1-LW-P-28, was-officially removed from service and replaced by a flow orifice and metering valve, 1-LW-ll30 in March 1990. Additional problems resulted from clogging of the metering valve causing restricted flow. Short ,

term resolutions included procedural changes to allow the metering valve to be flushed as required and additional surveillance on -the system. Long term enhancements being investigated to preclude futher

'_ inoperability include additional filtering of liquid waste to remove suspended solids which cause the clogging, and alternating flow direction through the metering valve periodically to provide 'self-flushing' capabilities.

~ "

, 1 Page 12 ATTACHMENT 6 101/90 -

06/90)

INOPERABILITY OF R'DIOACTIVE LIQUID AND GASBOUS EFFLUENT INSTRUMENTATION (cont.)

Liquid Waste Flow Monitoring Device (1-LW-FR/FT-104)

.Inoperability revolved around erratic flow indications. The suspected cause of the erratic indications is air entrapped within the liquid waste system. Investigation is being performed to .

eliminate the entrapped air and possibly replacing the existing transmitter with a new transmitter which is more suitable for this application.

PROCESS VENT (1-GW-RI-178-1,2) KAMAN RADIATION MONITOR VENT VENT "A" (1-VG-RI-179-1,2) KAMAN RADIATION MONITOR Extended inoperability occurred due to system modifications performed as field changes to Design Change Package DCP 37C. The modifications included replacing the chlorine-36 check source with an LED to reduce check source failures and upgraded heat tracing on sample' lines to reduce moisture build-up within the system.

r 3 ,

1 Page 13 i

ATTACHMENT 6 (01/90 -

06/90) I i INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS 1 EFFLUENT INSTRUMENTATION (cont.) .

i l

WASTE GAS DECAY TANK HYDROGEN & OXYGEN ANALYEERS (1-GW-H A-O A-102) .I r

Extended inoperability occurred due to the monitors being isolated 1 in conjunction with maintenance being performed on other components )

within the Gaseous Waste System, or other interfacing systems /

components. This maintenance' included location and repair l l

of numerous 1Mks in the Gaseous Waste System, rebuilding of 1-GW-PCV-lllD, and component cooling water outages. No further actions are planned and extended operation of the system is expected. i OVERVIEW )

l Because of the extended inoperabliity of Radiation Effluent Monitors during the first ar.d second quarter 1990, Virginia Power Management  !

has taken the following action steps:

a. Radiation Monitor operability continues to be trended by Plant 1

Management through the Daily Plant Status Report.  !

l

b. A Radiation Monitoring System Status Report is distributed to Plant Management on a weekly basis.

1

~ ~

_~.. . 1

. i Ptg3 14 ATTACHMENT 6 (01/90 -

06/90)

INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS i

EFFLUENT INSTRUMENTATION l

(cont.)

l

c. Station Deviation Reports issued against 38 Rad Monitors used for Emergency Response purposes are being trended by the Emergency Planning Group.

d. A Radiation Monitoring System Scoping Study was completed on December 15, 1989 to evaluate problems related to NAPS Unit 1 and 2 Radiation Monitoring Systems. Based on this study, improvements on selected Radiation Monitors have been performed and are in progress.

i, l

l 2

.. . 1 Page 15 r ATTACHMENT 7 l (01/90 -

06/90)

UNPLANNED RELEASES As required by Technical Specification 6.9.1.9, a list of unplanned releases, defined according to the criteria presented in 10 CFR part E .73, from the site to unrestricted areas of radioactive materials in gaseous a nd liquid effluents made during the reporting period is made below.

No unplanned releases, as defined according to the +

criteria presented in 10 CFR part 50.73, occurred during the tita period' covered by this report.

i l

-~ Pcg2 16- l

x. . .

.' " " ~ ' ATTACHMENT 8 l

' Lower Limits of Detection For- Effluent Sample Analysis ,

(01/90 - 06/90)  !

j c -

r Gaseous Effluents  !

~

Required L.L.D. Typical L.L.D. j Radioisotcpe (uCi/ml)' (UCi/ml) ,

1 Krypton - 87 1,. 0E-4 3.23E - 4.31E-7' 1

KryptonJ - 88 1.0E-4 3.67E-7 - 5,74E-7

. i Xenon -

133: 1.0E-4 2.52E-7 -

3.94E-7 ___ .

Xenon -

, ;l9 1.0E 1.11E-6 '- 1.53E-6' Xenon - -135 1.0E-4 1.26E ,1 95E-7 Xenon - 135m 1.UE-4 6.05E-7 -

8.15E-7 Xenon - 138 140E-4 1.57E-6' - 2.59E-6 ,

lodine - 131 '1,0E 5.56E 6.41E-14 Manganese - 54 1.0E-11 3.92E-14 ' 5.87E-14 Cobalt -

58 1.0E-11 4.23E 4.70E-14

}

__," Iron - 59 1.0E-11 8.29E 1.14E-13 Cobalt - 60 1.0E-11 5.50E 9.89E-14 -

Zinc - 65 l '^

1.0E;11 9.67E 1.26E-13 Strontium -

89 1.0E-11 5.0E-15 -

3.0E-13 l

Strontium - 90 1.0E-11 9.0E-16 -

6.0E-14

-Molybderium --

99 1.0E-11 -2.54E 4.08E-13  ;

Cesium.- 134 1. 0E -11 4.33E 6.35E-14 Cesium - 137- 1.0E-11 4.72E 5.60E-14 Caxium - 141 1. G E-1,1, 4.47E 5.22E-14 Cerium - 144 1.00-11 1.80E 2.54E-13 Gross Alpha 1.0E-11 5.13E 1.34E-14 Tritium 1.0E-6 1.19E-7 -

1.31E-7

-4

.Y wW

.% 9 M. 'f

r l an /

ffE 9- 4> o *

~.

}; *?(-*

.;p Page 17-( ,

ATTACHMENT 8 1

fi)

Gl";}g Lower Limits of ' Detection For Effluent Sample Analysis 1 (01/90 - 06/90) $, '

, , , .sn .

( cont. )

. Liquid Effluents' Required L.L.D. Typical L.L.D. .

Radioisotope (UCi/ml) (uC1/ml) l

} -Krypton' - 87 1.0E-5 5.32E-8 -

7.01E-8

=:> : Krypton - 88 1.0E-5 7.81E-8 -

9.63E-8 l

.cf Xenon -

'133 1.0E-5 6.84E-8 -

7.95E-8

, Xenon -

133m 1.0E-5 2.28E-7 -

2.67E-7 1 Xenon - 135 .1.0E-5 2.68E-8 - 3.24E-8 Xenon -

135m~ 1.0E-5 1.08E 1.34E-7 Xenon -

138 1.0E-5 3.20E-7 - 4.27E-7 t 4

-Iodine -

~ 13? 1.0E-6 2.77E-8 - 3.28E-8 .l 11 Manganese -

54 5.0E-7 2.49E-8 -

3.63E-8 ',

Iron ;, 55 1.0E-6 1.0E-6 i Cobalt - ' 58 5.0E-7 2.89E-8 -

2.92E-8 Iron - 59 5.0E-7 5.27E-8 -

7.03E-8 q Cobalt ,- 5.0E-7 3.40E-8 -

5.66E-8 g Zinc -

. 5.0E-7 5.67E 8.0E-8  :

d Stroi _um -

89 5.0E-8 3.0E-8 -

4.0E-8 Stro:.< r -

5.0E-8 5.0E-9 -

6.0E-9  !

I

- Mol- .

c" 5.0E-7 1.75E-7 - 2.60E-7 Cesi: 4 . 5.0E-7 2.96E-8 -

3.95E-8 s-  ;

cesium - ' - '

5.0E-7 3.33E 3.67E-8 Cerium - 141 5.0E-7 3.79E-8 -

4.14E-8 Cerium - 1- 5.0E-7 1.67E 2.08E-7 j Gross Alpha 1.0E-7 2.95E 7.74E-9 Tritium 1.0E-5 3.29E-6 -

3.61E-6 b

y

,