ML20153G100

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Semiannual Radioactive Effluent Release Rept North Anna Power Station Jan-June 1988
ML20153G100
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/30/1988
From: Barnes W, Cruden D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-574, NUDOCS 8809080039
Download: ML20153G100 (27)
v • d • e


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SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION i JANUARY 01, 1988 TO JUNE 30, 1988 I

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I Assistant Supervisor i j Health Physics t q (Count Room & Environmental)

REVIEWED BY:

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l Supervisor Health Physics j (Technical Services)

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! REVIEWED BYt - us M -_

l Fe 4 Superintendent Health Physics APPROVED BY: 4_y 4.

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8809080039 8G0630 t/

POR ADOCK 05000338 q

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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 6.9.1.9.

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SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i FOR THE NORTH ANNA POWER STATION JANUARY 01, 1988 TO JUNE 30, 1988 l

INDEX j SECTION NO. SUBJECT PAGE 1 PURPOSE AND SCOPE . . . . . . . . . . . . . . . 1 2 DISCUSSION . . . . . . . . . . . . . . . . . . 2 l 3 SUPPLEMENTAL INFORMATION . . . . . . . . . . . 3 l Attachment 1 Effluent Release Data . . . . . . . . . . . . . . . . . 4 Attachment 2 Annual and Quarterly Doses . . . . . . . . . .. . . . . 5 i

Attachment 3 Revisions to Offsite Dose Calculation Manual (ODCM) . . 6 I Attachment 4 Revisions to Process Control Program (PCP) . . . . . . . 7 j

Attachment 5 Major changes to Radioactive Liquid, Gaseous, and l Solid Waste Treatment Systems . . . . .. . . .. . . . 8 1

Attachment 6 Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Inoperable . . . . . . . . . . . . . . . 9 Attachment 7 Unplanned Releases . . . . . . . . . . . . . . . . . . . 10 Attachment 8 Changes Required By The Land Use Census Evaluation . . . 11 Attachment 9 Lower Limits of Detection for Effluent Samp;e Analysis . 12/13 i

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Page 1 1.0 PURPOSE AND SCOPE, The Semi-Annual 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 3 thereof. 'fhe report also includes a list of unplanned releases during the reporting period.

As required by Technical Specification 6.15.2 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 i

documentation necessary to support the rationale for the changes as required by technical Specification 6.14.1.

l This report includes a lirting of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant

to Technical Specification 3.12.2.

Major changes to radioact4ve liquid, gaseous and solid waste treatment systems are reported as required by Technical Specification 6.16.1.

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Information to support the reason (s) for the change (s) and a sun: mary 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 a

treatment system may be submitted as part of the annual FSAR update in accordance to Technical Specification 6.16.

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Page 2 1.0 PURPOSE AND SCOPE (cont.)

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.

2.0 DISCUSSION l

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.

Technical Specification 3.11.2.1.b requires that the dos; 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 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 >

I l mrem /yr to the total body and less than or equal to 3000 mrem /yr to the '

l skin.

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

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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 i

liquid effluents to unrestricted areas . hall be limited to the 1 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 2.0E-4 micracuries/ml.

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

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Page 3 2.0 DISCUSSION (cont.)

Unplanned releases presented in Attachment 7 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 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 The typical Lower Limit of Detection (L.L.D.) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 9.

These Lower Limit of Detection values are based upon :onservative 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 j not detected when analyzing effluent samples, then the activity of that l radioisotope will be reported as Not Detectable (N/D) on Attachment 1 of I

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

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

( 01/88 - 06/88 )

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

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TABLE 1A NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR 1988 j

ESTIMATED TOTAL UNITS Ist QUARTER 2nd QUARTER PERCENT ERROR (7)

A. Fission and Activation Cases:

1. Total Release. Curies 5.77E+1 2.50E+1 1.70E+1
2. Average Release Rate for Period. uCi/sec 7.34E+0 3.18E+0 B. Iodines:
1. Total Iodine-131 Release. Curies 4.26E-4 3.32E-4 1.70E+1
2. Average Release Rate for Period. pCi/sec 5.41E-5 4.22E-5 l C. PARTICULATES (Th > 8 days):
1. Total Particulate (Tb > 8 days) Release. Curies 5.63E-4 8.72E-6 1.70E+1
2. Average Release Rate for Period. pCi/sec 7.16E-5 1.11E-6
3. Gross Alpha Radioactivity Release. Curies 7.07E-6 1.54E-5 1.70E+1 D. Tritium:
1. Total Release. Curies 1.04E+1 9.28E+0 1.70E+1
2. Average Release Rate for Period. pCi/sec 1.33E+0 1.18E+0 i

! E. Percentage of Technical Specification Limits:

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1. Total Body Dose Rate.  % 3.82E-3 1.51E-3 I
2. Skin Dose Rate.  % 1.50E-3 5.99E-4
3. Critical Organ Dose Rate. I 1.38E-3 9.91E-4 N/D is Not Detectable & N/A is Not Applicable

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TABLE IB NORTH ANNA POWER STATION SEMI-ANNUAL RAD 10ACT!VE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR 1988 Page 1 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNITS let QUARTER l 2nd QUARTER lst QUARTER l 2nd QUARTER Fission and Activation Cases:

M pton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 C1 N/D N/D N/D N/D Xenon - 133 Ci 2.93E+0 3.2SE+0 2.69E-1 3.69E-1 Xenon - 135 C1 4.10E-2 7.15E-2 N/D N/D Xenon - 135m Ci N/D N/D N/D N/D Xenon - 138 C1 N/D N/D N/D N/D Other (Spec 11y)

Total for Period l Ci l 2.97E+0 l 3.33E+0 l 2.69E-1 l 3.69E-1 Iodines:

Iodine - 131 Ci 1.02E-5 I 5.llE-6 4.09E-7 4.53E-7 Iodine - 133 Ci 4.37E-5 1.81E-5 N/D 1.64E-7 Iodine - 135 Ci N/D N/D N/D N/D Other (Specity)

Total For Period l Ci l 5.39E-5 l 2.33E-5 l 4.09E-7 l 6.17E-7

Perticulates

l Strontium - 89 Ci l N/D N/D N/A N/A l Strontium - 90 Ci N/D N/D N/A N/A Cesium - 134 1 Ci N/D N/D N/D N/D Cesium - 137 C1 1.63E-8 4.25E-8 N/D N/D Barium - 140 Ci N/D N/D N/D N/D Lanthanum - 140 C1 N/D N/D '

N/D N/D Other (Specify) iron - 55 Ci 1.75E-7 2.20E-7 N/A F/A Cobalt - 58 Ci 4.69E-7 1.04E-7 N/D N/D Cobalt - 60 Ci l 1.31E-6 9.17E-7 N/D N/D N/D is Not Detectable & N/A is Not Applicable

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l TABLE IC NORM! ANUL POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT G.ROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1988 Page 1 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNITS ist QUARTER l 2nd QUARTER 1st QUARTER l 2nd QUARTER Fission and Activation Gares:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 133 Ci N/D 2.13E+1 5.45E+1 2.57E-3 Xenon - 135 Ci N/D N/D N/D n/D X:non - 135m Ci N/D N/D N/D ND Xenon - 138 Ci N/D p N/D N/D F)/_L Other (Specify) ,

Total for Period l Ci l N/D l 2.13E+1 l 5.45E+1 l 2.57E-3 Iodines:

Iodine - 131 Ci 2.1/E-4 3.26E-4 1.98E-4 1.34E-8 Iodine - 133 C1 2.44E-3 4.33E-3 4.76E-5 5.12E-9 Iodine - 135 C1 N/D N/D 1.20E-5 N/D ,

Other (Specify)

Iodine - 132 l Ci l N/D l N/D l 6.65E-6 l N/D l

l l Total For Period l Ci l 2.66E-3 ' l 4.66E-3 l 2.64E-4 l 1.85E-8 Pcrticulates:

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

! Strontium - 90 Ci N/D N/D N/A N/A l Cesium - 134 _

Ci N/D N/D 1.44E-4 N/D l Ccsium - 137 Ci N/D 2.24E-6 3.85E-4 N/D l Barium - II.0 Ci N/D N/D N/D N/D Lenthanum - 140 Ci N/D N/D N/D N/D Other (Specify)

Manganese - 54 Ci N/D N/D 2.07E-6 I N/D Iron - 55 Ci N/D ,5.17E-6 N/A N/A Cobalt - 58 Ci N/D N/D I 7.04E-6 N/D N/D is Not Detectable & N/A is Nat Applicable 1

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1ABLE IC NORTH ANNA POWER STATION SEMI-ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT

  • GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1988 Page 2 of 2 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNITS 1st QUARTER l 2nd QUARTER 1st QUARTER l 2nd QUARTER

! Particulates (cont):

Cobalt - 60 Ci N/D N/D i 2.22E-5 2.81E-8 Niobium - 95 Ci N/D N/D 5.75E-10 N/D Antimony - 122 (Tb < 8 days) C1 N/D N/D 1.80E-5 N/D Te31urium - 131m (IS < 8 days) Ci N/D N/D 5.33E-9 N/D Cesium - 138 (T < 8 days) Ci N/D __ N/D N/D 9.19E-5 C1 Ci C1 C1 Ci Ci Ci Total For Period (T > 8 days) Ci N/D 7.41E-6 5.61E-4 2.81E-8 Total for Period (T < 8 days) Ci N/D N/D 1.80E-5 9.19E-5 Total for Period l Ci l N/D I 7.41E-6 i 5.79E-4 l 9.19E-5 CROSS ALPHA: l Ci l 7.07E-6 l 1.54E-5 l N/D l N/D l

l TRITIUM: l Ci _l 7.32E+0 l 6.01E+0 l 2.10E+0 l 1.79E-5 l

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

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TABLE 2A NORTH ANNA POWER STATION SEMI-A*iNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

  • SUMMATION OF ALL LIQUID EFFLUENT RELEASES FOR 1988 ESTIMATED TOTAL UNITS Ist QUARTER 2nd QUARTER PERCENT ERROR (%)

A. Fission & Activation Products:

1. Total liquid effluent release (not including tritium, noble gases and gross alpha). Curies 1.63E-1 9.14E-2 1.70E+1
2. Avercge diluted concentration of liquid effluents during the period. pCi/ml 2.67E-10 1.08E-10
3. Percent of applicable Tech. Spec. limit.  % 1.19E-3 4.13E-4 B. Tritium:
1. Total liquid effluent rel-ase of tritium. Curies 3.92E+2 4.75E+2 1.70E+1 1

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! tritium during the period. uCi/ml 6.4"E-7 5.61E-7 i

3. Percent oi" applicable Tech. Spec. limit.  % 2.14E-2 1.87E-2 f

l C. Dissolved and Entrained Noble Cases:

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l 1. Total liquid effluent release of

! noble gases. Curies 3.36E-2 5.43E-2 1.70E+1 g

2. Average dilutai concentration of l noble gases during the period. uCi/ml 5.50E-11 6.42E-Il
3. Percent of applicable Tech. Spec. limit. I 2.75E-5 3.21E-5 l D. Cross Alpha Radioactivity:
1. Total liquid eff" :nt release of gross alpha. Curies N/D N/D 1.70E+1 l '

I E. Total volume of liquid effluent released (prior to dilution) during the period. Liters 7.14E+7 8.39E+7 2.00E+0 F. Total volume of dilution water used during the period. Liters 6.10E+11 8.47E+11 2.00E+0 N/D is Not Detectable & N/A is Not Applicable

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i TABLE 2B l NORTH ANNA PO'4ER STATION SEMI-ANIiUAL RA910 ACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR 1988 Page 1 of 2 CONTINUOUS MODE BATCl4 MODE NUCLIDES RELEASED UNITS Ist OUARTER l 2nd QUARTER 1st QUARTER l 2nd QUARTER Fiesion and Activation Products: ~

Chromium - 51 Ci N/D N/D N/D N/D Manganese - 54 C1 9.68E-4 3.61E-4 N/D N/D Cobalt - 58 Ci 1.16E-2 1.78E-3 N/D N/D j Iron - 59 Ci N/D N/D N/D N/D l Cobalt - 60 C1 4.93E-2 3.98E-2 N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strentium - 89 Ci N/D N/D N/A N/A Strontium - 90 ,

Ci N/D N/D N/A N/A Niobium - 95 Ci 2.31E-3 l.03E-3 N/D N/D Zirconium - 95 C1 4.27E-4 N/D N/D N/D Molybdenum - 99 (T < 8 days) Ci N/D N/D N/D N/D Tcchnetium - 99m(Th ( 8 days) Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D l

Cesium - 134 C1 1.62E-3 1.39E-3 N/D 3.46E-8 Cesium - 137 Ci 4.92E-3 3.90E-3 N/D 7.58E-8 B:rium - 140 Ci N/D N/D N/D N/D Lanthanum - 140 Ci N/D N/" N/D N/D Cerium - 141 Ci N/D Nf, N/D N/D Other (specify)

Sodium - 24 ( T < 8 days ) Ci 1.46E-3 5.99E-5 N/D N/D Iron - 55 Ci N/D N/D N/A N/A Strontium - 85 C1 5.99E-5 N/D N/D N/D Zirconium - 97 (T < 8 days) C1 2.30E-3 5.80E-4 N/D N/D Rhodium - Ruthenium - 106 Ci 1.30E-2 1.17E-3 N/D N/D Silver - Il0m Ci 7.46E-2 3. 22 E-2 N/D N/D Antimony - 124 C1 3.08E-4 N/D N/D N/D Antimony - 125 C1 N/D 9.19E-3 N/D N/D Iodine - 133 C1 1.94E-4 2.55d-5 N/D N/D C1

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Total f or Period (Th > 8 days) Ci 1.59E-1 9.08E-2 N/A 1.10E-7 Total for Period (T < 8 days) C1 3.76E-3 6.40E-4 N/A N/A Total for Period i Ci l 1.63E-1 l 9.14E-2 l N/A l 1.10E-7 N/D is Not Detectable & N/A is Not Applicable

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a TABLE 3 NORTH ANNA POWER STATION SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT  !

SUMMATION OF SOLID RADI0 ACTIVE WA5TE AND IRRADIAltU FUEL SHIPMENTS FOR 01-01-88 THROUGH 06-30-88 -

Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)  !

6-MONTH E5TIMATED TOTAL i

1. Type of Waste UNIT PERIOD PERCENT ERROR (%) {

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a. Spent resins, filter sludges, m3 7.03E+1* 2.50E+1 evaporator bottoms, etc. Ci 7.66E+2 2.50E+1
b. Dry compressible waste, m3 9.37E+1** 2.50E+1 contaminated equipment, etc. Ci 2.08E+0 2.50E+1 i
c. Irradiated components, control m3 0.00E+0 0.00E+0 -

rods, etc. Ci 0.00E+0 0.00E+0

d. Other(describe) Dry Sewage l m3 1.19E+1*** 2.50E+1 ,

Sludge & Contaminated Oil Ci 1.81E-2 2.50E+1  !

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

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a. Cobalt - 60  % 4.57E+1 2.5 E+1  !

Iron - 55  % 1.80E+1 2.5 E+1 l Cesium - 137  % 1.02E+1 2.5 E+1 i Nickel - 63  % 1.78E+1 2.5 E+1 Cesium - 134 1 3.60E+0 2.5 E+1 Cobalt - 58 1 2.39E+0 2.5 E+1 Panganese - 54  % 1.77E+0 2.5 E+1  !

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b. Cobalt - 60  % 2.72E+1 2.5 E+1 ~~~

Iron - 55  % 2.12E+1 2.5 E+1  !

Cobalt - 58  % 1.56E+1 2.5 E+1 -

Cesium - 137  % 1.44E+1 2.5 E+1 ~

, Cesium - 134 1 5.63E+0 2.5 E+1 I Niobium - 95  % 3.63E+0 2.5 E+1 i l Manganese - 54  % 3.10E+0 2.5 E+1 i Nickel - 63 5 2.76E+0 2.5 E+1 i

Zirconium - 95  % 2.49E+0 2.5 E+1 l 1 Chromium 51  % 2.33E+0 2.5 E+1 [

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Tritium t 1.44E+0 2.5 E+1

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l TABLE 3 NORTH ANNA 70ER STATION SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT SUWTION OF SOLID RADI0 ACTIVE WA5TE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-88 THROUGH 06-30 88 Page 2 of 2 .

2. Estimate of ma; or nuclide composition (by type of 6-MONTH ESTIMATED TOTAL ,

waste) (con.t) UNIT PERIOD PERCENT ERROR (%)

d. (Sewage)

Iron - 55 1 7.80E+1 2.5 E+1 Cobalt - 60  % 1.13E+1 2.5 E+1

~

Cerium - 144 1 4.02E+0 2.5 E+1 l Cesium - :.3'7  % 3.60E+0 2.5 E+1 Cesium - :.34  % 3.10E+0 2.5 E+1 (011) '

Iron - 55  % 8.10E+0 2.5 E+1

Cesium - 134  % 8.26E+0 2.5 E+1 r Tritium  % 3.22E+1 2.5 E+1 _

3. Solid Waste Disposition  ;

i NUMSER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION  !

9 Truck Barnwell SC 5 Truck Oak Ridge TN  ;

B. IRRADIATEDFUEL$HI.'MENTS(Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 0 N/A N/A I l

1 shipment of powdex resin was shipped from North Anna to a licensed waste )

i processor for volume reduction. Therefore the volume as listed for this I waste type is not representative of the actual volume buried. Total volume I buried for the reporting period was 52.79 m3

    • 2 shipments of dry compressible waste were shipped from North Anna to a licensed waste processor for volume reduction. Therefore the volume as listed for this waste type is not representative of the actual volume buried. Total volume buried for the reporting period was 62.56 m3
      • 1 shipment of contaminated oil was shipped from North Anna to a licensed waste processor for incineration. Therefore the volume as listed for this waste type is not representative of the actual volume buried. Total volume buried for the reporting pcriod was 2.97 m8

Page 5 ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES 2

( 01/88 - 06/88 )

l I

An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report along with an annual total of each effluent pathway will be made pursuant to Technical Specification 6.9.1.9 in the Semi Annual Radioactive Effluent Release Report submitted within sixty ( 60 ) days af ter January 01, 1989.

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Page 6 l

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ATTACHMENT 3 l

( 01/88 - 06/88 )

REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM1 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 ODCH ace attached.

No revisions to the OTTSITE DOSE CALCULATION MANUAL (ODCM) were required for the time period covered by this report.

1

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Page 7 ATTACHMENT 4

( 01/e8 - 06/88 )

As required by Technical Specification 6.14 revisions to to the PCP for the time period covered by this report are synopsized l below. Supporting documentation and affected pages of the PCP are attached.  :

No revisions to the Process Control Program (PCP) were required for 1 i

the time period covered by this report. -

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I Page 8 L

ATTACHMENT 5 f

l ( 01/88 - 06/88 )

l l MAJOR CHANCES TO RADI0 ACTIVE LIQUID, CASEOUS. AND SOLID l

WASTE TREATMENT SYSTEMS i

i As required by Technical Specification 6.16, major changes to radioactive liquid, gaseous and solid vaste  !

treatment systems for the time period covered by this report are reported below. Supporting information as to the reason (s) for the change (sf and a summary of the  !

i 10 CFR Part 50.59 evaluation are included.

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No major chanEes to the radioactive liquid, gaseous, and solid vaste treatment systems were made for the time period i l

covered by this report.  !

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Page 9 l ATTACIIMENT 6

.( 01/88 - 06/88 )

l KAD 0 ACTIVE LIQUID K.?O GASEOUS EFFLUENT HONITORING INSTRL' MENTATION INOPERABLE As required by Technical Specification 3.3.3.20.b and 3.3.3.11.b. a list and explanation for the inoperability l

of radioactive liqv.id and/or gaseous effluent monitors  ;

is provided in this report.

l On April 11. 1987. 1-RM-SW-108 ( radiation monitor for  !

I service water discharged to Lake Anna) was declared l l inoperable. The service water itne to 1-SW-P-10 (service i water pump) was found clogged, which prevented flow  !

l through the radiation monitor. Attempts to maintain the I service water line free from debris and return the monitor I

to service have been unsuccessful. The 1-RM-5W-108 ,

(service water radiation monitor) was inoperable greater than thirty (30) days, because of difficulty in cleaning  !

the service water supply line. Engineering Work Request

  1. 85-123 has been initiated to solve the radiation monitor j i

check source and meter spiking problem and the flow line to the radiation monitor clogging problems.

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Page 10 l

1 i ATTACHMENT 7  ;

( 01/88 - 06/88 ) l i  !

i UNPLANNED RELEASES f

. I i

j i As required by Technical Specification 6.9.1.9  ;

i a list of unplanned releases, defined according to the criteria presented in 10 CFR part 50.73, s

from the site to unrestricted areas of radioactive l l

) materials in gaseous and itquid effluents made  !

l 4

during the reporting period is made below, i

i i

) - i I

i No unplanned releases, as defined according to the  :

j criteria presented in 10CFR Part 50.73, occurred l during the time period covered by this report. (

1  !

)

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\

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Page 11 Attachment 8

( 01/88 - 06/88 )

Changes Required By The Land Use Census Evaluation As required by Technical Specification 3.12.2 and 6.9.1.9. Evaluation of the Land Use Census is to be made for identifing the new location (s) for dose calculations and/or environmental monitoring pursuant to Technical Specification 3.12.2 requirements.

No Attachment required for this Semi Annual Radioactive Effluent Release Report, s

1 i

Page 12 i i ATTActDfENT 9 i

l Lower Limits of Detection For Effluent Sample Analysis

( 01/88 - 06/88 ) i Caseous Effluents f 3

^

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

J Radioisotope (pC1/ml) (pC1/ml) i Krypton - 87 1.0E-4 8.56E-1 - 1.21E-6 f a

, Krypton - 88 1.0E-4 1.0?t-6 - 1.29E-6 l I Xenon - 133 1.0E-4 7.38E-7 - 8.36E-7 I

Xenon - 133m 1.0E-4 3.63E-6 - 4.57E-6  !

Xenon - 135 1.0E 4 3.61E-7 - 4.99E-7 I i Xenon - 135m 1.0E-4 5.84E-7 - 8.97E-7 i

] Xenon - 138 1.0E-4 1.43E-6 - 2.12E-6 --

i l

Iodine - 131 1.0E-12 8.42E 1.00E-13 l Manganese - 54 1.0E-11 5.79E 7.40E-14 l 1 i j Cobalt - 58 1.0E-11 6.21E 9.16E-14 l

]

Iron - 59 1.0E-11 7.33E 8. QE-14 l i

I Cobalt - 66 1.0E-11 1.20E 1.78E-13 I Zine - 65 1.0E-11 1.44E 2.83E-13 l

J Strontium - 89 1.0E-11 4.00E 6.00E-15 l 1

1.0E-11 l 1 Strontium - 90 6.00E 1.00E-15 .

I I l Molybdenum - 99 1.0E-11 4.1PE 4.95E-13 ,

1 l

Cesium - 134 1.0E-11 6.67E 8.46E-14 l 1

l Cesium - 137 1.0E-11 6.91E 7.33E-14  !

! l Cerium - 141 1.0E-11 8.04E 1.04E-13 i i

l I ,

j Cerium - 144 1.0E-11 3.01E 4.25E-13 '

i j ,

Cross Alpha 1.0E-11 1.34E 2.17E-14 8 t J

l Tritium 1.0E-6 1.29E-7 - 1.44E-7  !

1 i 1  !

Page 13 ATTACHMENT 9 Lower Limits of D4tection For Effluer.t Sample Analysis  !

( 01/68 - 06/88 ) l

( cont. )

Liquid Fffluents  !

, Required L.L.D. Typical L.L.D. I l Radioisotope (uci/ml) (uC1/ml) t Krypton - 87 1.0E-5 8.38E-8 - 1.11E-7 Krypton . 88 1.0E-5 1.51E-7 - 1.93E-7 t

Xenon - 133 3.0E-5 1.08E-7 _ 1.38E-7 Xenon - 133m 1.0E-5 4.29E-7 - 5.37E-7 Xenon - 135 ,

1.0E-5 4.56E-8 - 6.31E-8  ;

i Xenon - 135m 1.0E-5 7.92E-8 ,,1.78E-7 Xenon - 138 1.0E-5 2.38E-7 - 4.34E-7 f Iedine - 131 1.0E-6 5.12E-8 - 6.74E-8 Manganese - 54 5.0E-7 4.15E-8 - 7.30E-8 i Iron - 55 1.0E-6 9.00E-7 - 1.00E-6 Cobalt - 58 5.0E-7 2.86E-8 - 7.61E-8  ;

Iron - 59 5.0E-7 8.90E-8 - 1.30E-7 Cobalt - 60 5.0E-7 8.55E-8 - 8.88E-8 Zine - 65 5.0E-7 1.06E-7 - 1.19E-7 I 1

Strontium - 89 5.0E-8 3.00E-8 - 4.00E-8 i Strontium - 90 5.0E-8 8.00E-9 - 1.00E-8 Molybdenum - 99 5.0E-7 2.67E-7 - 3.29E-7 l

Cesium - 134 5.0E-7 5.10E-8 - 6.41E-8 '

Cesium - 137 5.0E-7 3.15E-8 - 7.07E-8 Cerium - 141 _ 5.0E-7 6.72E-8 - 9.89E-8 Cerium - 144 5.0E-7 2.96E-7 - 4.22E-7 Gross Alpha 1.0E-7 7.73E-9 - 1.25E-8 Tritium 1.0E 5 3.57E-6 - 3.96E-6 l

1 l l

l Viunixir 1: .uctuic Axn l'ownw coversy l Hicnwoxo.V woix A MHMhl l

l August 26, 1988 a n.c.....

Ytt e l'assipan, Net tae n United States Nuclear Regulatory Comission Serial No. 88 574 Attention: Document Control Desk N0/DJV:Jmj Washington, D.C. 20555 Docket Nos. 50-338 50 339 License Nos. NPF 4 NPF 7 Gentlemen:

11RGJMIA ELECTRIC AND POWER COMPANY NORTH AMA POWER STATION UN11S 1 AND 2 SENI-ANNUAL RADIDACTIVE EFFLUENT RELEASE.EE20RI Enclosed is the North Anna Power Station Semi-Annual Radioactive Effluent Release Report for January 1, 1988 through June 30, 1988. The report, submitted pursuant to North Anna Station Technical Specification 6.9.1.9, includes a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the previous six months, as outlined in Regul.atory Guide 1.21, Revision 1, June 1974.

Very truly yours, j M

0. S. uden Enclow e cc: U. S. Nuclear Regulatory Comission 101 Marietta Street, N.W.

Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station WS

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