ML20082K815
| ML20082K815 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/30/1991 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20082K806 | List: |
| References | |
| NUDOCS 9109030045 | |
| Download: ML20082K815 (28) | |
Text
..
l 1
RADIOACTIVE EFFLUENT RELEASE REPORT NORTil ANNA POWER STATION (JANUARY 01, 1991 TO JUNE 30, 1991) i
'l PREPARED BY sC:,=
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u upervisor Radiological Analysis
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REVIEWED BY:
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T' Supervisor Technical Services APPROVED BY:/ 'd 3
Superinte(tulant
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Radiological Protection l
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9109030045 910823 l
PDR ADOCK 05000338 R
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i F 0 _ R W A - R 12 This report is submitted as required by Appendix A to Operating License Nos.
NPF-4 and NPP-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.
f i
l.
1 i
RADIOACTIVE
' EFFLUENT RELEASE REPORT I
t FOR THE i
NORTH ANNA POWER STATION JANUARY 01, 1991 TO JUNE 30, 1991 i
i I NDEX
- l, Section No.
Subject Page i
)
i 1
PURPOSE AND SCOPE........................
1-2 2
DISCUSS10N.................................
2-4 3
SUPPLEMENTAL INFORMATION..................
4 -5 Attachment 1-Effluent Release Data......................
6 Attachment 2-Annual and Quarterly Doses.................
7 Attachment 3-Revisions to Offsite Dose Calculation Manual (ODCM).............................
8
-Attachment 4-Revisions to Process Control Program (PCP)......................................
9 - 10 Attachment 5-Major changes to Radioactive Liquiil, Gasecca, and Solid Waste Treatment Systems....................................
11 Attachment 6-Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation............................
12 Attachment 7-Unplanned Releases.........................
13 Attachment 8-Lower Limits of Detection (LLD) for Effluent Sample Analysis...................
14 - 15 e
t i
Page 1
1.0 PURPOSE AND SCOPE The Radioactive Fffluent 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 maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year.
The report submitted within 60 days 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.c, changes to the Offsite Dose Calculation Manual (ODCM) for the time petiod covered by this report are included in Attachment 3.
Information is provided to support the changes along with a package of those i
pages of the ODCM changed.
l This report includes changes to the Process Control Program (PCP) l with information and documentation necessary to support the rationale for these changes in Attachment 4.
t
Page 2 f
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 j
the ODCM, Section 6.5.2.
Information to support the reason (s) for the change (s) and a summary of the 10 CFR 50.59 evaluation are included.
In lieu of reporting major changes in *his report, major changes to the radiaactive waste treatment systems may be
{
submitted as part of the annual PSAR update.
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?
As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list e
and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this t
report, in Attachment 6.
2.0 DISCUSSION j
f The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1 is the ODCM.
The ODCM, Section 6.3.1, requires that the dose l
rate for Iodine-131, for Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be l-less than or equal to 1500 mrem /yr to the critical organ at or l-beyond the site boundary.
The critical organ is the child's l
thyroid; inhalation pathway.
The basis for the calculation of percent of technical specification for the total body and skin in Table 1A of Attachment 1 is the
{
ODCM.
The ODCM, Section 6.3.1, requires that the dose rate for noble gases to areas at or beyond the site boundary shall be less than or equal to 500 mrem /yr to the total body and less than-or l
equal to 3000 mrem /yr to the skin.
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.s Page 3 2.0 DISCUSSION (cont.)
The basis -for the calculation of the percent of technical
[
-specification in - Table 2A of Attachment 1 is the ODCM.
The ODCM, Section 6.2.1, states-that the concentrations of radioactive material released.in liquid offluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B,
Table II, Column 2 for radionuclides othtr than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-4 microcuries/ml.
Percent of technical specification calculations are based on the total gaseous or 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 in the ODCM.
The beta and gamma air doses due to noble gases released frcm 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 f orm with half-lives greater than 8 days, is defined as an infant, exposed through l
l the grass-cow-milk pathway, with the critical organ being the thyroid.
The maximum exposed-member of the public from radioactive materials in liquid effluents in unrestricted areas is 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.
l
s Page 4 2.0 DISCUSSION (cont.)
Unplanned releases presented in Attachment 7 are defined according to the criteria presented in 10 CPR 50.73, as those gaseous radioactive releases that exceed 2
times the applicable concentration limits specified in Appendix D,
Table II, 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 Attacnment 8.
These LLD values are based upon conservative conditions (i.e.,
minimum sample volume and maximum delay time prior to ani'usie).
Actual LLD values may be lower.
If a
radioisotope is not detected when analyzing effluent
- samples, then the activity of that radioisotope will be reported as Not Detectable (N/D) on Attachment 1 of this report.
On Attachment 1,
an entry of "N/A",
not applicable, indicates that no analysis-is performed for that isotope.
When used in conjunction with
- totals, such an entry indicates that all radioisotopes for that particular quarter and release mode are less than LLD.
3.0 SUPPLEMENTAL INFORMATION As required by the ODCM, evaluation of the Land Use Census is to be made for identifying the new location (s) for the l
environmental monitoring program pursuant to the ODCM, Section 6.5.2, requirements.
~
Page 5 3.0 SUPPLEMENTAL INFORMATION (cont.)
No new location (s) for dose calcu?.ations and/or environmental monitoring were identified by the evaluation of the Land Use Census conducted in 1990.
As required by the ODCM, the identilicatior, of the causes of the unavailability of milk or leafy vegetation samples, required by the ODCM, Section 6.5 and Attachment 21, and the identification of the new location (s) for obtaining replacement samples are listed.
Milk samples, as required by the ODCM, Section 6.5 and 1, were available during the time period covered by this report.
The leafy vegetation semples for vegetation stations 14, 15, 16, 21 and 23 were not collected for the months of January and February 1991 due to seasonal unavailability.
All other samples were obtained and analyzed as required during the timt period covered by this report.
I i
l
Page 6 i
ATTACllMENT 1
EFPLUENT RELEASE DATA z
(01/91 06/91) l t
s This attachment includes a summary of the quantities of radioactive
[
liquid and gaseous effluents and solid waste, as outlined in Regulatory i
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 1991 1st 2nd ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)
A. Fission and Activation Gases:
1.
Total Release.
Curies 2.62E+2 7.99E+2 1.80E+1 2.
Average Release Rate for Period.
pCi/sec 3.37E+1 1.02E+2 B.
lodines:
- 1. Total Iodine-131 Release.
Curies 4.03E-4 3.72E-4 2.80E+1
- 2. Average Release Rate for Period.
pCi/sec 5.18E-5 4.73E-5 C.
Particulates (T
> 8 days):
- 1. Total Particulate (T
> 8 days) Release.
Curies 7.15E-5 9.92E-6 2.80E+1
- 2. Average Release Rate for Period.
pCi/sec 9.19E-6 1.26E-6
- 3. Gross Alpha Radioactivity Release Curies N/D N/D D.
Tritium:
1.
Total Release.
Curies 1.95E+1 1.36E+1 3.10E+1
- 2. Average Release Rate for Period.
pCi/sec 2.51E+0 1.73E+0 i
E. Percentage of Technicial Specification Limits:
7.02E-3 4.08E-2 1.
Total Body Dose Rate.
2.72E-3 1.51E-2 2.
Skin Dose Rate.
2.24E-3 1.63E-3
- 3. Critical Organ Dose Rate.
N/D is Not Detectable N/A is Not Applicable L
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TABLE IC NORTH ANNA POWER STATION-SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REFORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1991 Page 1 of 2 CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission and Activation Gases:
Krypton - 85 Ci U/D N/D N/D N/D Krypton - 85m Ci 2.93E-3 1.71E-3 N/D 5.83E-3 Krypton - 87 Ci 3.91E-3 N/D N/D N/D Krypton - 88 Ci 4.14E-3 2.74E-3 N/D 6.41E-3 Xenon - 131m Ci N/D N/D N/D N/D Xenon - 133 Ci 6.86E+1 3.64E+2 3.02E-1 2.33E+0 Xenon - 133m Ci U/D N/D N/D 8.'1 9 E - 3 Xenon - 135 Ci 6.23E-2 1.33E+1 N/D 1.14E-1 Xenon - 135m Ci 4.62E-2 5.29E-2 N/D N/D Xenon - 138 Ci 1.07E-2 N/D N/D N/D Other (Specify)
Argon - 41 Ci 1.42E-1 2.63E+0 N/D 5.25E-3 Total for Period Ci 6.89E+1 3.80R+2 3.02E-1 2.47E+0 Iodines:
Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci 3.94E-4 3.59E-4 5.85E-8 5.98E-8 Iodine - 132 Ci N/D N/D N/D 9.72E-10 Iodine - 133 Ci 1.70E-4 6.08E-4 1.16E-8 6.13E-8 Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D M/D N/D N/D Total for Period Ci S.64E-4 9.67E-4 7.01E-8 1.22E-7 Particulates:
Manganese - 54 Ci N/D N/D N/D 1.89E-9 Iron - 55 Ci 2.09E-5 N/D N/D N/D Cobalt - 58 Ci 3.06E-5 4.08E-6 N/D 1.18E-9 Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci 6.55E-6 N/D NfD 7.65E-8 Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver - 110m Ci N/D N/D N/D N/D Cesium - 134 Ci N/D N/D 2.71E-8 N/D Cesium - 136 Ci N/D N/D N/D N/D N/D is Not Detectable N/A is Not Applicable
TABLE 1C
~
NORTU ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1991 Page 2 of 2 CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd NUCLlDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates (cont.):
Cesium - 137 Ci 9.50E-6 N/D 1.40E-7 2.31E-19 Cerium - 141 Ci N/D N/D N/D N/D Barium - 140 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 N/D N/D Bromine - 84 (T
< 8 days)
Ci N/D N/D N/D 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 Molybdenum - 99 (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 (T
< 8 days)
Ci N/D N/D N/D N/D Tellurium - 131m (T
< 8 days)
Ci U/D N/D N/D N/D Cesium - 138 (T
< 8 days)
Ci N/D N/D N/D N/D Barium - 139 (Th < 8 days)
Ci N/D N/D N/D 2.50E-5 Total for Period (T
> 8 days)
Ci 6.76E-5 4.08E-6 1.67E-7 7.98E-8 Total for Period (T
< 8 days)
Ci N/A N/A N/A 2.50E-5 Total for Period Ci 6.76E-5 4.08E-6 1.67E-7 2.51E-5 Ci N/D N/D N/D N/D GROSS ALPHA:
Ci 1.91E+1 1.30E+1 4.02E-2 9.03E-2 TRITIUM:
N/D is Not Detectable N/A is Not Applicable
\\
TABLE 2A NORTH ANNA POWER STATION SEMI ANNUAL RADIOACTIVE EPPLUENT RELEASE REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES FOR (1991) 1st 2nd ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)-
Ao Fission and Activation Products:
- 1. Total release (not including tritium, noble gases, and gross alpha).
Curies 1.29E-1 3.19E-2 2.00E+1
- 2. Average diluted concentration during the period.
pCi/ml 2.82E-10 4.15E-ll 3.
Percent of applicable limit (T.S.).
6.05E-3 1.66E-3 B. Tritium:
- 1. Total release activity.
Curies 2.25E+2 3.20E+2 2.00E+1
- 2. Average diluted concentration during the period.
pCi/ml 4.91E-7 4.16E-7 3.
Percent of applicable limit (T.S.).
1.64E-2 1.39E-2 1
C. Dissolved and Entrained Gases:
- 1. Total release activity.
Curies 1.23E+0 7.29E-1 2,00E+1
- 2. Average diluted concentration during the period.
pCi/ml 2.69E-9 9.49E-10 3.
Percent of applicable limit (T.S.).
1.34E-3 4.74E-4 D. Gross Alpha Radioactivity:
+
- 1. Total release activity.
Curies 2.18E-4 N/D 2.00E+1 E. Volume of waste released: (prior to dilution).
Liters 7.00E+7 8.02E+7 3.00E+0 F. Volume of dilution water used during period.
Liters 4.58E+11 7.68E+11 3.00E+0 l
N/D is Not Detectable N/A is Not Applicable 1
1 m
--.-. a
T%LE 2B NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR 1991 Page 1 of 2 4
CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission and Activation Products:
Manganese - 54 Ci 8.89E-4 N/D N/D N/D 1ron - 55 Ci N/D N/D N/D N/D Cobalt - 58 Ci 2.02E-2 5.39E-3 N/D N/D 1
Cobalt - 60 Ci 4.23E-2 7.85E-3 N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver - 110m Ci 2.10E-2 5.73E-4 N/D N/D Iodine - 131 Ci 6.12E-3 3.42E-3 N/D N/D lodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci 4.41E-3 8.20E-4 N/D 1.74E-8 Iodine - 134 Ci N/D N/D N/D N/D lodine - 135 Ci 1.40E-4 N/D N/D N/D Cesium - 134 Ci 2.70E-4 N/D N/D N/D Cesium - 136 Ci N/D N/D N/D N/D Cesium - 137 Ci 3.72E-3 6.32E-4 N/D N/D Barium - 140 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (specify)
Sodium - 24 (Th < 8 dc/s)
Ci 4.95E-5 N/D N/D N/D Chromium - 51 Ci 4.74E-3 N/D N/D N/D Iron - 59 Ci 4.05E-3 N/D N/D N/D Niobium - 95 Ci 2.31E-3 9.03E-5 N/D N/D Tecnnetiem - 99m (T
< 8 days)
Ci N/D N/D N/D N/D Antimony - 122 (T
< 8 days)
Ci N/D N/D N/D N/D Antimony - 124 Ci 8.63E-4 4.78E-4 N/D N/D Antimony - 125 Ci 1.73E-2 1.26E-2 N/D N/D Tellurium - 129m Ci 3.80E-4 N/D N/D N/D Barium - 139 (T
< 8 days)
Ci 4.27E-4 N/D N/D N/D Lanthanum - 140 (Th < 8 days)
Ci N/D N/D N/D N/D Total for Period Ci 1.29E-1 3.19E-2 N/A 1.74E-8 N/D is Not Detectable N/A is Not Applicable
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TABLE 3
NO!1Til ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND 1RRADI ATED FUEL SillPMENTS FOR 01-01-91 TilROUGil 06-30-91 Page 1 of 2 A.
SOLID WASTE SillPPED OFFSITE FOR BURI AL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTil ESTIMATED TOTAL 1.
Type of Waste UNIT PERIOD PERCENT ERROR
(%)
a.
Spent resins, filter m'
8.51E+1 2.50E+1 sludges, evaporator Ci 1.48E+2 2.50E+1 bottoms, etc.
b.
Dry compressible waste, m'
6.54E+2*
2.50E+1 contaminated equipment, Ci 1.31E+1 2.50E+1 etc.
c.
Irradiated components, m'
O 00E0 0.00E+0 control rods, etc.
Ci 0.00E0 0.00E+0 d.
Other (describe) m' 3.63E+1**
2.50E+1 Dry Innocuous Waste Ci 4.02E-3 2.50E+1 2.
Estimate of major nuclide composition (by type of waste) a, Fe-55 5.45E+1 2.50E+1 Co-58 9.94E0 2.50E+1 Co-60 1.83E+1 2.50E+1 Ni-63 1.35E+1 2.50E+1 1
b.
Cr-51 2.75E0 2.50E+1 Mn-54 1.45E0 2.50E+1 Fe-55 2.71E+1 2.50E+1 Co-58 3.02E+1 2.50E+1 Co %
1.42E+1 2.50E+1 Ni-63 3.92E0 2.50E+1 l
Zr-95 5.10E0 2.50E+1 Nb-95 4.24E0 2.50E+1 Cs-134 1.53E0 2.50E+1 Cs-137 7.84E0 2.50E+1 1
9 TABLE 3
NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELIMSE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SIIIPMENTS-FOR 01-01-91 TilROUGil 06-30-91 Page 2 of 2 2.
Estimate of major 6-MONTil ESTIMATED TOTAL nuclido composition UNIT PERIOD PERCENT ERROR (by type of waste)
(t)
(cont.)
c.
NOND d.
Co-58 6.00E0
3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination 13 Truck Barnwell,S.C.
11 Truck Oak Ridge,T.N.
(SEG) 3 Truck Oak Ridge,T.N.
(Quadrex)
B.
IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination 0
N/A N/A 13 shipments of Dry Active Waste waste were shipped from North Anna to a 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 this reporting period was 69.8 m'.
l.
1 shipment of dry sewage sludge (Dry innocuous waste) was 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.
The processed waste (i.e.,
after volume reduction) was not buried during the time period covered by this
- report, i
Page 7 f
ATTACllMENT 2
r ANNUAL AND QUARTERI.Y DOSES (01/91 06/91)
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 offlaent pathway, will be made pursuant to the ODCM, Section 6.6.2 requirements, in the Radioactive Effluont Release Report submitted within sixty (60) days after January 01, 1992.
l Page 8 i
7 4C11 MENT 3
REVISIONS TO OPA DOSE CALCULATION MANUAL (ODCM)
(01/91 06/91)
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, if applicable.
Revision 1 to the Virginia Power offsite Dose Calculation Manual is effective July 01,
- 1991, As such, these changes will be reported in the accond Semi-Annual Radioactive Effluent Relcase Report of 1991.
Page 9 i
ATTACl! MENT 4
REVISIONS TO PROCESS CONTROL PROGRAM (PCP)
(01/91 06/91)
Revisions to the Process Control Program (PCP) for the time-period covered by this report are synopsized below.
Supporting documentation and affected pages of the PCP are attached, if applicable.
A revision was made to Virginia Power Administrative Procedure (VPAP)
- 2104,
" Radioactive Waste Process Control Program",
effective May 10, 1991.
A summary of changes to the PCP is provided here, and a copy of Revision 1 of VPAP-2104, with changes denoted, is attached for reference.
In the reference section of the PCP, the following changes were made:
A.
Reference 3.1.6 was changed to reflect Rev. l date of January 1991 to Branch Technical Position on Waste Form.
D.
Reference 3.1.17 was added for US Ecology Topical Report USE 002-P, NRC Docket No. Wm-102, " Stability of Low-Level Radioactive Wastes Solidified with High Strength Asphalt, Rev.
0".
In the definitions section of the PCP, the following changes were made:
A.
. Definition 4.5 for "Non-Corrosive Liquid" was changed to reflect new sub-section of Rev. 1 of Branch Technical Position on Waste Form.
In the instructions section of the PCP, the f ollowing. changes were made:
A.
Sub-step 6.1.2.a. was changed to add "and/or evaporator bottoms".
~-,
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Page 10 ATTACitMENT 4
REVISIONS TO PROCESS CONTROL PROGRAM (PCP)
(01/91 06/91)
(cont.)
B.
Sub-step 6.1.4.b was deleted, with the contents incorporated into sub-step 6.1.4.a.
l C.
Sub-step 6.1.4.a was changed to remove " Health Physics".
D.
" NOTE" was added to Step 6.2, concerning solidification of wet waste, to provide reference to US Ecology Topical Report (Reference 3.1.17) for solidification performed at Surry Power Station's Radwaste Facility.
In the Table of Contents section of the PCP
.srenced _page numbers were changed for sub-sections 6.3 and 6.4 to reflect Revision 1 pages containing the applicable sub-sections and their respective steps.
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Page 11 ATTAcilMENT 5
MAJOR CilANGES TO IUsDIOACTIVE L10UJD
- GASEOUS, AND SOLID 3
WASTE TREATMENT SYSTEMS (01/91 06/91)
As required by the ODCM, Section 6.6.2, major changes to radioactive liquid,- gaseous and solid waste treatment systems for the time period covered by this report are reported below.
Supporting information as to the reason (s) for the change (s) and a summary of the 10 CPR 50.59 l
evaluation are included, as applicable.
i l
No major changes to the radioactive liquid, gaseous and solid waste treatment systems were made for the time period covered by this report.
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Page 12 ATTACIIMENT 6
INOPERABILITY OF RADIDACTIVE LIQUID AND GASEOUS EPPLUENT MONITORING INSTRUMENTATION 101/91 06/91)
As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this report.
No extended periods of inoperability occurred with any of the Liquid or Gaseous Effluent Monitoring Instrumentation for the time period covered by this report.
I 1
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PAGE 13 A'1"I'ACllM ENT 7
UNPLANNED RELEASES (01/91 06/91)
As required by the ODCM, Section 6.6.2, a list of unplanned releases, as defined by the criteria presented in 10 CFR 50.73, from the site to unrestricted
- areas, of radioactive material in gaseous and liquid offluents occurring during the reporting period, is made below, t
No unplanned releases, as defined by the criteria presented in 10 CFR 50.73, occurred during the time period covered by this report.
)
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Page 14 i
ATTACitMENT 8
LOWER LIMITS OF DETECTION FOR EPPLUENT SAMPLE ANALYSIS (01/91 - 06/91)
Gaseous Effluents:
Required L.L.D.
Typical L.L.D.
~~
Radioisotope (pCi/ml)
(pCi/ml)
Krypton - 87 1.00E-4
__2.76E-8 4.07E-7 Krypton - 88 1.00E-4 2.60E-8 6.13E-7
' Xenon - 133 1.00E-4 4.07E-8 4.22E-7 Xenon - 133m 1.00E-4 8.99E-8 1.36E-6 Xenon - 135 1.00E-4 2.26E-8 1.69E-7 Xenon - 135m 1.00E-4 5.80E-8 7.70E-7 Xenon - 138 1.00E-4 1.20E-7 2.09E-6 Iodine - 13) 1.00E-12 3.55E-14 7. 2 4 E-14 l
Manganese - 54 1.00E-ll 2.14E 4.97E-14 Cobalt - 58 1.00E-ll 2.54E-14 4.95E-14 Iron - 59 1.00E-ll 6.29E-14 1.03E-13 l
l Cobalt - 60 1.00E-11 3.00E 9.26E-14 l
Zinc - 65 1.00E-ll 5.02E 1.14E-13 l
Stroritium - 89 1.00E-ll 3.00E 5.00E-15 Strontium - 90 1.00E-ll 6.00E 1.00E-15 Molybdenum - 99 1.00E-ll 1.69E 3.40E-13 Cesium - 134 1.00E-ll 2.64E-14 5.92E-14 Cesium - 137 1.00E-ll 2.74E 4.85E-14
-Cerium - 141 1.00E-ll 2.27E 5.09E-14 Cerium - 144 1.00E-11 9.61E 2.22E-13 Gross Alpha 1.00E-ll 1.75E 1.80E-14 Tritium 1.00E-6 1.41E-7
l'a g o 15 ATTACllMEMT H
1,0Witit 1.l MI T!1 OP DETECTION POlt EPPl.UENT
!1 AMI't.l!
ANAL.Y!;lli 0Q91)
~
(01/91 (cont.)
Liquid I?ffluontna itequired 12. L. D.
Typical
- 1.. l.. D.
Itadioi rot ope (pcifml)
( pt'if ml )
Krypton - 87 1.000-5 3.39E-8 6.840-8 Krypton - 08 1.000-5
,3.32E-8 1.1 91:-7 Xenon - 133 1.00E-5 6.441-8 8.550-8 Xenon - 133m 1.001:- 5 1.111:-7 2.551:-7 Xenon - 135 1.00E-5 1.293-8 3.11E-8 Xenon - 135m 1.001>5 7.170-8 1.26E-7 3.82D-7 Xenon - 138 1.00E-5_
1.460-7 lodine - 131 1.001:-6 1.52E-H 3. 2 31 - 8 54 5.00E-7 1.270-8 3.05E-8 Manganese Iron - 55 1.00E-6 1.00E-6 2.99E-H Cobalt - 58 5. 0 01:-7 1.52H-8 6.131 -H 1ron - 59 5.001'-7 3.45E-8 Cobalt - 60 5.00E-7 1.611 -8 4.940-8 6.31E-H Zine - 65 5.00E-7 2.7 51:- 8 Strontium - 89 5. 0 011-H 2.000-8 3.001'-8 7.000-9 Strontium - 90 5.001'-8 6.00E-9 Molybdenum - 99 5.00E-7 1.051;-7 2.16E-7 Cesium - 134 5.00E-7
.1.59E-8 3.50E-8 3.80E-8 Cesium - 137 5.00E-7 1.77E-8 5.51E-8 Cerium - 141 5.00E-7 1.77E-8 Cerium - 144 5.00E-7 7.721:-8 2.4 01:-7 Gross Alpha 1.00E-7 1.01E-8 1.04E-8 Tr i t.i um 1.00E-5 3.90E-6
..