ML20082N409
| ML20082N409 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1994 |
| From: | Bowling M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 95-200, NUDOCS 9504250214 | |
| Download: ML20082N409 (110) | |
Text
VINGINIA ELucTHIC AND Powen COMi%NY HIcnwown, VIRGINIA 20261 i
April 20, 1995 United States Nuclear Regulatory Commission Serial No.95-200 Attention: Document Control Desk NAPS /JHUCMC Washington, D. C. 20555 Docket Nos.
50-338 50-339 l
License Nos. NPF-4 NPF-7 1
Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS.1 AND 2 RADIOACTIVE EFFLUENT RELEASE REPQBI Pursuant to Technical Specification 6.9.1.9, enclosed is the Radioactive Effluent Release Report for North Anna Power Station Unit Nos.1 and 2 for the reporting period of January 1,1994 to December 31,199(
i If you have any questions or require additional information, please contact us.
Very truly yours, M. L. Bowling, Ma ager l
Nuclear Licensing and Programs Enclosure cc:
U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station I
955425'o$14 941233 DR ADOCK 0500033g 8
7
/
(
- 1. '
I J
i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION 1
1 (JANUARY
- _01, 1994 TO DECEMBER 31, 1994) l i
1 6
i i
PREPARED BY:n Supervisor Radiological Analysis i
E*
/
[
REVIEWED BY:
l Supervisor Technical Services APPROVED BY:
Superintendent Radiological Protection
=
i FORWARD This report is submitted as required by Appendix A.to operating License Nos. NPF-4 and NPF-7, Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-338, 50-339, Section 6.9.1.9.
I i
1
..y ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
)
-FOR.THE NORTH-ANNA PONER STATION JANUARY 01, 1994 TO
. DECEMBER 31, 1994 INDEX Section No.
Subject Paae 1
EXECUTIVE
SUMMARY
1 2
l 3
i 2
PURPOSE AND SCOPE.....................
2 5
l 3
DISCUSSION............................
4 4
SUPPLEMENTAL INFORMATION..............
6 Effluent Release Data.................
7 Annual and Quarterly Doses............
8 i
l Revisions to Offsite Dose Calculation Manual (ODCM).........................
9 i
Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems...............................
10 l
l Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation.......................
11 l
Unplanned Releases....................
12 l
Lower Limits of Detection (LLD) for Effluent Sample Analysis.............
13
- 14 i
l j
.1.0 EXECUTIVE
SUMMARY
The Annual Radiological Effluent Release Report describes the radiological effluent control program conducted at the North Anna Power station during the 1994 calendar year.
This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station in accordance with R.G. 1.21 during the period January 1 through December 31, 1994, and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents.
There were no unplanned liquid or gaseous effluent releases classified according to the criteria in the Offsite Dose Calculation Manual during this reporting period.
Based on the 1994 effluent release data, 10 CFR 50, Appendix I dose calculations were performed in-accordance with the Offsite Dose Calculation Manual.
The results of these pathway dose calculations indicate the following:
1.
The total body dose due to liquid effluents was 3.95E-01 mrem, which is 6.58% of the dose limit and the critical organ (liver) dose due to liquid effluents was 4.21E-01 mrem, which is 2.1% of the dose limit.
2.
The air dose due to noble gases was 4.01E-02 mrad gamma, which is 0.2% of the annual gamma dose limit, and 1.62E-02 mrad beta, which is.04% of the annual beta dose limit.
1
1.O EXECUTIVE
SUMMARY
(cont.)
3.
The critical organ dose for I-131, I-133, H-3, and Particulates with half-lives greater than 8 days was 2.38E-02 mrem, which is
.08% of the annual dose limit.
There were no major changes to radioactive liquid, gaseous, and solid waste treatment systems during this reporting period.
There were changes to the Offsite Dose Calculation Manual, VPAP-2103, during this reporting period which were implemented in Revisions 5 and 6 on January 1, 1994 and December 1, 1994 respectively.
provides the changes to VPAP-2103.
Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1 and 2 have resulted in negligible dose consequences to the maximum exposed member of the public in unrestricted areas.
2.0 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 from 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 2
2.0 PURPOSE AND SCOPE (cont).
3 of Appendix B thereof.
The report submitted before May 1st 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 also includes a list of unplanned releases during the reporting period, in Attachment 6.
As required by Technical Specification 6.15, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3.
Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, section 6.7.2.a.4.
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 this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update.
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 Attachment 5 of this report.
3
3.0 DISCUSSION i
l The basis for the calculation of.the percent of technical specification l
for the critical organ in Table 1A of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for iodine-131 & iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 arem/yr to the critical organ at or beyond the site boundary.
The critical organ i
is the child's thyroid via the 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, section 6.3.1, which requires that the dose rate for noble gases to areas at or r
beyond site boundary shall be less than or equal to 500 mrem /yr to the I
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 in Attachment 1 is the ODCM, section 6.2.1, which states f
that the concentrations of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited l
to 2.0E-4 microcuries/ml.
Percent of technical specification calculations are based on the total i
gaseous or liquid effluents released for that respective quarter.
4 N-
3.0 DISCUSSION (cont.)
The annual and quarterly doses, as reported in Attachment ' 2, were calculated according to the methodology presented 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 & iodine-133, 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 gland.
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.
Presented in Attachment 6 is a list of unplanned gaseous and liquid releases meeting the requirements of 6.7.2.a.3 of the ODCM.
The typical Lower Limit of Detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in i.
These LLD values are based upon conservative conditions i
(i.e., minimum sample volume and maximum delay time prior to analysis).
Actual LLD values may be lower.
If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report.
If an analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A).
j i
5
4.0 SUPPLEMENTAL INFORMATION As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is made to determine if new location (s) have been identified for the radiological environmental monitoring program pursuant to the ODCM, Section 6.6.2 requirements. Evaluation of the Land Use Census conducted in 1994 identified no change in sample locations for the radiological environmental monitoring program.
Section 6.6.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. Milk samples, as required by the ODCM, section 6.6.1, were available during the time period covered by this report.
The leafy vegetation samples for vegetation station-14, 15, 16, 21 and 23 were not collected for the months of January, February, March, November and December 1994 due to seasonal unavailability.
All other samples were obtained and analyzed as required during the time period covered by this report.
6
ATTACHMENT 1
EFFLUENT RELEASE DATA
.LO1/94 12/94)
This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21, Appendix B.
i e
r i
I 1
7 i
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TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT PFT F U E REPORT SUMMATION OF ALL GASEOUS EFFLUENT PRT.FUES FOR (01/94 - 12/94)
Page 1 of 2 l
1ST 2ND ESTIMATED TOTAL l
UNITS OUARTER OUARTER PERCENT ERROR f%i' t
A.
Fission and Activation Gases:
j
- 1. Total Release.
Curies 5.33E+0 1.09E+1 1.80E+1 l
- 2. Averace Release Rate for Period uCi/sec 6.85E-1 1.39E+0 B.
- 1. Total Iodine-131 Fg), ease.
Curies 1.42E-6 7.72E-7 2.80E+1
- 2. Averace Release Rate for Period uCi/sec 1.83E-7 9.82E-8 C.
Particulates (Th > 8 days):
- 1. Total Particulate (T
> 8 days)
Release Curies 2.54E-5 1.81E-6 2.80E+1 2.
Averace Release Rate for Period uCi/sec 3.27E-6 2.30E-7 3.
Gross Aloha Radioactivity Release Curies 2.58E-5 6.19E-5 D.
Tritium:
- 1. Total Release Curies 1.78E+1 4.14E+1 3.10E+1 2.
Averace Release Rate for Period uCi/sec 2.29E+0 5.27E+0 E.
Percentage of Technical Soecification Limits
- 1. Total Body Dose Rate 6.11E-3 1.09E-3 2.
Skin Dose Rate 1.49E-3 2.78E-4
- 3. Critical Orcan Dose Rate 1.22E-3 3.46E-3
TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE RE* ORT SUlefATION OF Ar r.
GASEOUS EFFLUENT pur.wasES FOR (01/94 - 12/94)
Page 2 of 2 3rd 4th-ESTIMATED TOTAL-UNITS QUARTER QUARTER PERCENT ERROR f%)
A.
Fission and Activation Gases:
1.
Total Release.
Curies 1.26E+1 1.39E+1 1.80E+1
- 2. Averace Release Rate for Period uCi/sec 1.59E+0 1.75E+0 B.
1.
Total Iodine-131 Release.
Curies 3.90E-4 3.24E-7 2.80E+1
- 2. Averace Release Rate for Period uCi/sec 4.91E-5 4.08E-8 C.
Particulates (Th > 8 days):
- 1. Total Particulate (T\\ > 8 days)
Release Curies 3.58E-5 7.57E-6 2.80E+1
- 2. Averace Release Rate for Period uCi/sec 4.50E-6 9.52E-7
- 3. Gross Aloha Radioactivity Release Curies 6.76E-5 4.20E-5 D.
Tritium:
- 1. Total Release Curies 4.40E+1 6.36E+0 3.10E+1
- 2. Averace Release Rate for Period uCi/sec 5.54E+0 8.00E-1 E.
Percentage of Technical Snecification Limits
- 1. Total Body Dose Rate 9.77E-4 2.22E-2 2.
Skin Dose Rate 3.05E-4 5.42E-3 l
3.
Critical Oraan Dose Rate 4.27E-3 5.31E-4 l
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TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT pTT FME REPORT LIQUID EFFLUENTS-SUMMATION OF ATT-PFT TMES FOR (01/94 - 12/94)
Page 1 of 2 l
1st 2nd ESTIMATED TOTAL UNITS OUARTER QUARTER PERCENT ERROR f4) l l
A.
Fission and Activation Products:
- 1. Total release (not including tritium, noble gas, and gross aloha).
Curies 1.19E-1 2.12E-1 2.00E+1
- 2. Average diluted concentration durina the oeriod, uCi/ml 2.33E-10 2.92E-10 3.
Percent of aDolicable limit (T.S.)
1.62E-3 5.07E-4 B. Tritium:
1.
Total release activity.
Curies 1.23E+2 6.73E+2 2.00E+1
- 2. Average diluted concentration durina the oeriod.
uCi/ml 2.41E-7 9.26E-7 3.
Percent of acolicable limit (T.S.)
2.41E-3 9.26E-3 C.
Dissolved and Entrained Gases:
1.
Total release activity.
Curies 3.16E-4 N/D 2.00E+1
- 2. Average diluted concentration durina the oeriod.
uCi/ml 6.18E-13 N/D 3.
Percent of aDolicable limit (T.S.)
3.09E-7 0.00E+0 D.
Gross Alnha Radioactivity:
- 1. Total release activity.
Curies 1.15E-4 N/D 2.00E+1 E.
Volume of waste released: (prior to dilution).
Liters 7.31E+7 7.12E+7 3.00E+0 F.
Total volume of dilution water used durina the neriod.
Liters 5.11E+11 7.27E+11 3.00E+0
l:
TABLE. 2A NORTH ANNA POWER STATION I
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLumnis-SinetATION OF 17 r.
pur.r1AES FOR (01/94 - 12/94)
Page 2 of 2 3rd 4th ESTIMATED TOTAL UNITS OUARTER OUARTER' PERCENT ERROR (4)-
A.
Fission and Activation Products:
- 1. Total release (not including tritium, noble gas, and gross aloha)..
Curies 6.48E-2 1.40E-1 2.00E+1 l
- 2. Average diluted concentration durina the neriod.
uCi/ml 8.31E-11 2.10E-10 3.
Percent of anolicable limit (T.S.)
1.38E-4 1.43E-4 B.
Tritium:
- 1. Total release activity.
Curies 2.99E+2 1.44E+2 2.00E+1
- 2. Average diluted concentration durina the neriod.
uCi/ml 3.83E-7 2.16E-7 3.
Percent of anolicable limit (T.S.)
3.83E-3 2.16E-3 C.
Dissolved and Entrained Games:
- 1. Total release activity.
Curies 2.22E-4 6.14E-5 2.00E+1
- 2. Average diluted concentration durina the neriod.
uCi/ml 2.85E-13 9.22E-14 3.
Percent of anolicable limit (T.S.)
1.42E-7 4.61E-8 D.
Gross Alnha Radioactivity:
1.
Total release activity.
Curies N/D N/D 2.00E+1 E.
Volume of waste released: (prior to dilution).
Liters 6.74E+7 7.12E+7 3.00E+0 F.
Total volume of dilution water used durina the nariod.
Liters 7.80E+11 6'.66E+11 3.00E+0 4
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TABLE 3
NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-94 THROUGH 12-31-94 Pace 1 of 2 A.
f*0 LID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-Month Estimated Total 1.
Type of Waste Unit Period Percent Error (%)
a.
Spent resins, sludges, m8 9.65E+1*
2.50E+1 filters, filter sludge, Ci 9.82E+2 2.50E+1 evaDorator bottoms etc.
b.
Dry compressible waste, m8 2.08E+2**
2.50E+1 contaminated equipment, Ci 3.61E+0 2.50E+1 etc.
c.
Irradiated components, m8 0.00E0 0.00E0 control rods, etc.
Ci 0.00E0 0.00E0 d.
Other (describe) m3 3.61E+0***
2.50E+1 Waste Oil Ci 1.13E-3 2.50EF1 2.
Estimate of major nuclide composition (by type of waste) a.
Ni-63 34.1%
3.33E+2 2.50E+1 Co-60 28.30%
2.76E+2 2.50E+1 Cs-137 12.3%
1.20E+2 2.50E+1 Fe-55 9.3%
9.11E+1 2.50E+1 Cs-134 7.8%
7.65E+1 2.50E+1 Co-58 5.5%
5.33E+1 2.50E+1 Mn-54 2.2%
2.10E+1 2.50E+1 b.
Cs-137 34.4%
1.21E0 2.50E+1 Co-58 25.6%
9.02E-1 2.50E+1 Fe-55 13.6%
4.77E-1 2.50E+1 Co-60 12.1%
4.26E-1 2.50E+1 Cr-51 4.0%
1.40E-1 2.50E+1 Ni-63 3.7%
1.30E-1 2.50E+1 Nb-93 2.5%
8.81E-2 2.50E+1 Cs-134 2.3%
8.15E-2 2.50E+1 Zr-95 1.8%
6.21E-2 2.50E+1 c.
TABLE 3
NORTH AMMA POWER STATION RADIOACTIVE EFFLUENT DRLRASE REPORT SUMMATION OF SOLID RADIOACTIVE WAMTE AND IRRADIATED FUEL SHIPNRMTS FOR 01-01-94 THROUGH 12-31-94 Pace 2 of 2 2.
Estimate of major nuclide composition (by type of 12-Month Estimated Total waste) (cont.)
Unit Period Percent Error (%)
d.
Ce-144 71.3%
8.06E-4 2.50E+1 Cs-137 15.1%
1.72E-4 2.50E+1 Co-60 13.6%
1.54E-4 2.50E+1 3.
Solid Waste Disposition Nit =her of ShionCDtS.
Mode of Transportation Destination 15 Truck Barnwell, SC 9
Truck Oak Ridge, TN (SEG)
B.
Irradiated Fuel Shipments (Disposition)
Nii=her of Shinnents Mode of Transoortation Destination N/A N/A N/A 2 shipments of resin and 2 shipments of sludge were shipped from North Anna to a Licensed Waste Processor for volume reduction. Therefore, the volume listed for this type is not representative of actual volume buried.
The total volume buried for this reporting period was 126.1 m8 e*
6 shipments of dry compressible waste / contaminated equipment were shipped from North Anna to a Licensed Waste Processor for volume reduction.
Therefore, the volume listed for this type is not representative of the actual volume buried. The total volume buried for 8
this reporting period was 97.5 m.
ee*
3 shipments of waste oil were shipped from North Anna to a Licensed Waste Processor for incineration. Therefore, the volume listed for this type is not representative of the actual volume buried.
The total volume buried for this reporting period was 0.00 m8
g ATTACHMENT 2
ANNUAL AND OUARTERLY DOSES 12/94)
(01/94 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 cnnual total of each effluent pathway will be made pursuant to the ODCM S ction 6.7.2.
i Ligitid Effluents:
1st 2nd 3rd 4th Annual Ouarter Ouarter Ouarter Ouarter Total Total Body Dose (aren) 6.87E-2 1.91E-1 8.52E-2 4.96E-2 3.95E-1 Critical Organ Dose (aren) 8.33E-2 1.95E-1 8.73E-2 5.51E-2 4.21E-1 Gaseous Effluents:
1st 2nd 3rd 4th Annual Ouarter Ouarter Ouarter Quarter Total Noble Gas cm--
Dose (arad) 7.91E-3 1.44E-3 1.36E-3 2.94E-2 4.01E-2
__ Noble Gas
_ Beta Dose furad) 2.90E-3 7.95E-4 1.96E-3 1.05E-2 1.62E-2 Critical Organ Dose for I-131, I-133, H-3, 8.84E-4 2.21E-3 2.03E-2 3.46E-4 2.38E-2 Particulates with Th > 8 days furen) 8
I AT2'Acamum r 3
i L
REVISIONS TO OFFSITE DOSE N-CULATION MANUAL (ODCM)
(01/94 12/941 l
As required by Technical Specification 6.15, revisions to the. ODCM, effective for the time period covered by this report, are summarized in this j
l attachment.
l 6
There were two procedure revisions and one procedure change to Revision-5 l
implemented during the period January 1 through December 31, 1994.
Included in this attachment is Revision 6 of the ODCM, effective December 1, 1994.
All changes which were implemented by Revision 5, effective January 1,
- 1994, and one procedure change, effective June 16, 1994, are included in Revision 6.
The specific changes are summarized on the cover sheet of the ODCM.
Revision 5 implemented the changes in support of the revised 10 CFR 20 requirements and the change in reporting frequency of the radioactive effluent release report from semiannual to annual.
Revision 6 implemented' I
the criteria for classifying unplanned liquid and gaseous effluent releases to include the NRC's Health Physics Position on the Definition of Unplanned Releases.
In addition there were miscellaneous editorial changes and corrections addressed in Revision 6.
9
1 9
Station Administrative Procedure VIRGINIA P09WR l
C 1993 by Vuguna Power. All Rights Reerv d
Title:
Offsite Dose Calculation Manual Lead Department: Radiological Protection Procedure Number Revision Number Effective Date VPAP-2103 5
01/01/94 Revision Summary
. Implement revised 10 CFR 20 requirements RECEIVED
~
. Change effluent reporting requirements from semi-annual to anr.ual
. Add liquid and gaseous release permits from VPAP-2101 Jun ;
i Incorporate Surry P1 -replacement of dairy sample location for Surry Attachme)ntband 22 and editorial change to Attachment 21, page 5, line 4 I
. Incorporate P2 -replacement of Poole's Garden for Surry AttachO[nf 3[OCUMENT MGT.
. Change variables in liquid efnuent monitor setpoint calculations Changed 10 ECW to ACW
. Replaced 10 (ECW)i with ACW in applicable equation i
i Removed Surry LW-108 instrument from the effluent monitoring instrumentation attachments
. Removed Bacons Castle and Jamestown as sources of SPS Wellwater samples
. Incorporate Surry P-1 to HP-7.3A.20 to allow liquid transfers to the Surry Radwaste Facility without requiring a Liquid Waste Batch Release Permit (see 6.4.1.a)
. Miscellaneous editorial changes and corrections (no change bars)
Surry Power Station North Anna Power Station Approved by:
Approved by:
AkA Il41-A3 0
li l'lk f MOC Chairm%/
Date SNSOC Chairman Dat'e Ap ved ved by:
2%ff$s/n Manager ~AL
/)
ll $T
/ Vate
'Statio'n hTiinager~
~ Da'te U
Approved by:
a
/24 92 i
V Vice President-Nuclear Operations
' Date' '
9 Station Administrative Procedure VIRGINIA POWER C 1994 by Virpau Power. All Rapu Renew
Title:
Offsite Dose Calculation Manual Lead Department: Radiological Protection Procedure Number Revision Number VPAP-2103 Effective Date 5-PN & S1 See Par Revision SummaryE-PAR Implement revised 10 CFR 20 requirements Change effluent reporting requirements from semi-annual to annual
. Add liquid and gaseous release permits from VPAP-2101 editorial change to Attachment 21, page 5,line 4Incorperate Su Incorporate P2 -replacement of Poole's Garden for Surry Attachment 22
. Change variables in liquid effluent monitor setpoint calculations Changed 10 ECW to ACW
. Replaced 10 (ECW); with ACW in applicable equation i
. Removed Bacons Castle and Jamestown as sour
. Incorporate Surry P-1 to HP-7.3A.20 to allow liquid transfers to th without requiring a Liquid Waste Batch Release Permit (see 6.4.1.a)
. Miscellaneous editorial changes and corrections (no change bars)
. {PN & SI) Add information to various section for the addition ofI-1 Surry Power Station North Anna Power Station Approved by:
Approved by:
ProcedureChance-See Attached ParN/A SNSOC Chamnan ProcedureChance-See Attached Par -
N/A Date SNSOC Cheirman Date Approved by:
Approved by:
ProcedureChance-See Attached ParN/A ProcedureChance-See Attached Par Station Manager Date N/A Station Manager Date Approved by:
ProcedureChance-See Attached Par N/A Vice President-Nuclear Operations Date
O uneemm u nessa NONH ANNA POWER STATIONProcedure Action Request ADM21 VPAP-0502 instructons for complet no this form are included in VPAP-0502
- 1. Procecure Numoer
- 2. Revisen
- 3. Prococure ChEge Numoer VPAP-2103 5
- 4. Page
- 5. Procecure Trtie PN1
. Offsite Dose Calculanon Manual 1 ef 154
- s. Expiraten Date N/A
- 7. TyDeof Request [ New Procedure @ProcedureCe. lProcedureRevision
~
Procedur e Deletion lVendor Proceoure v
- 8. Duration or Extent of Usage
@ Permanent
] Temporary
]One Time Only
- 9. Reason For Cnange incorporate response to N-94-610 and S-94-1058
- 10. Desenpton of Cnange (PN & S1) E-Par Add inforrnation to various section for the addition ofI-133.
NOTE: Station Manager must sign prior to implementation.
- 11. Requested By Name (Please Pnnt)
- 12. Date C. Tarantino 5-19-94
- 13. It this PAR is for a dowton to an Aaministratrve Proceeurs, enter the effective date of the deletion.
14
!! this PAR is for a Prococure Change, the Cognizant Supervisor is not required to sign Blodc 15. The
- 15. Lead /Responsole Dept. Cognizant Supervisor (Signature)
- 16. Date sgnature in Block 27 constitutes approval Procedure Chanoes On6y - Chany of inton' Chockiist # Do a y of the following staterT1ents apply to the procedur
- 17. A change to the stated Purpose of the procedure.
e b Yes E No
- 18. A change in the stated initial Conditions that must be satisfied prior to performing the procedure.
b Yes l No
- 19. AchangehthestatedAcx:eptance Crttona that must be satisfied for satisfactory completion o ocedure.
- 20. A modification or deletion of setpoints, independent, or simultaneous verification.
Yes E No YesENo
- 21. A change that affects specific actions that are required to be accomplished to ensure t completon of the task. This includes changes that affect personnel safety, decrease fire protection Yes M No cffcetiveness, affect ecuipment oualification, or involve a less conservative method of performi IM
- 22. A change that relocates or deletes a required hold point. This does not include deleting a sect of a procedure which includes a hold point.
Yes E No
- 23. A change to CAUTION or WARNING statements. This does not inclu:le adding CAUTION o stat 5ments or deleting a section of a procedure which includes CAtJTION or WARNING statements.
Yes E No 2
- 4. A change that modifies or deletes the method for meeting a commttment identified in the proced h Yes b No 2
- 5. A change that results in a "Yes' answer to any of the questions on the PAR Activity Screen byes.
No
- 6. Do:s the cover sheet of this procedure indicate ' infrequently Conducted or Complex Test or 2
- Soocial Test,* or is this procedure an emergency olan implementino prg. dure?
Yes E No n or M any at theemaemenes aseve propoemd prosedwo ensom., m
- 27. Lead /Re nsele Dept.
ntzant Supervisor (Sgnature)
- 28. Date d
Weh*Prierte masi irt 31 h
/
P
- 29. Shift Supervisor (Sgnature) h rocessure Change. Deleton. and Station s
- 30. Date
- 31. SNSOG Approval Required:
Prior-to-use Within 14 Days
- 32. Sg; gairmat)(Signature)
- 33. Dese 34 Swo C o M4 anegyr, As A7-No PA%"icMure Actson Request; WAteson Muoteer sepoty one CA Ner.Ek (Sgnature) 35.Dyre (ss-( M V l(ey:
MM [
-U l-Form too. 73oes2 (jay 93)
Procedure Action Request
.y 1
A.
Willthis activity require a chanhe to the Technical Specifcations? Emlain.r/c 7 c'F sor /s terra,rp ray,4 esf NA C s.c; s* seed AAsuranest sow vrotr oroved w fire ofest pas a pers. sea rcs:. r*ne A ve srerers.es ? No 1/t. ts,s. g c f /~5 1; 5. Vr os. t.1 CFFedrss'e F n L e"
(t crsvu srsriu C.$. v. E N ft/Mn se.teruJ m doord s.cf* ders w n.* r.s. nonow 7"s orsn.
13 6.V. 4 C- *7 0- 4' l
B.
Does this activity involve a revision to design bases? Explain.
/W
/ttvt5 w d5 Tv / f 5t& 4) AAs t> s.u r w s e4 Yes k No C.
Does this activity involve a temporary modifcation? Explain.
byes i No sue renArx.s ex re wexssy +es, f,s ar,. ss in.a...ts.
l D. Does this activity involve a change to the Environmental Protection Plan or a change, test, or bYeshNo_.
experiment 1 hat may affect the environment? Explain. ye ryga e ys y,,e ge,ve,,eparase
/Kerrerse V
/s A-U.
A/C' tr/A M rs, Tests, et d'x/tst ser rosr5 rsraer soens e//rer Tit t n'Netacn ew y /Msus.ves.
1 ~ > 10 srrd10.SBft0 Cst 72.48 Screenleur(Sedety Anelpeds "
i(SAft)Cos.gsteseinterenetior DefinedinV"M.3co1.A il A.
indicate Safety Analysis Report documents / sections reviewed. jegDoe no
{
j,,yj,,s, y,s,,,, s de, am e
rare fat s s
- TY f.Hro v'te yy j tts / e's c.do a es w 3A A.
j1/4o7ro.o ei s.,oa..se /cA.
i.ut s ass osu
.-?h. re Jos e en tu er so.as ossia s
9' S L V. 't E 7 * *?
AAst e w srese iz B.
the Safety Analysis Report? Eglain and indicate Safety Analysis R rs er, wr.*3 cf v/cd Ar e v.0, 2"!Sr o/ esA rttu e,ves s4 s Jrscduto w nye SAA Axe suer Asrested est-e nis.uced.
C.
Does the change modify safety related structures, systems, equipment, or components not describe A) c S A f ery A e. A rf d !!/ ve r V'tfin the Safety Analysis Report? Explain and indicate Safe Yes % No
/tdd' f ot A !"ot.VS Yt4A r fi A t sur 4 f>rstodre s
Tire
- s. rt.d.
Aer
/.UVrs. o rb. AAA /Tr**V CP Net **de f rA. !MhfC Je
!A t*'s.*r e.so o.s; cos !-
o D.
Explain and indicate Safety Analysis Report documents / sections reviewe O ves E no Tesr 4 we/s,e r,e n,c, p,,5
,vy, p c > s.,g,;,.s i.u,,,,, sgx g,s,
,,.,,, yes,j, i
E.
Will operation of another system that is described in the Safety Analysis Report be adversely a as a result of this change? Explain and indicate Safety Analysis Report documents / sections reviewed.
O Yes B u.
^'%'
ADVr<st t //*eis on e rs, tag sistrks h A Arsesr o& Tirs a ens.na. C.
it any response in item 1 or2 le "Yesf; ttach the Safety Evolustion Antheb pedonersSafetyEvolustion inaccontence A
' t Seelieseer! reference heteestion84MMMIM% Sately Eystsetions.g;gl
- 3. Pre t' r Name (Please n 4.
Title i c.* A n "A h D A rtt i e v 9'TAFF NeAsm Yes.c, W l
n l
- 5. prep:ryrSepparur ) v,,/ &(\\ g 6.
Date f LJ R -
,Yb ReWow'sT Name (Only if Noh-Auti$ued PPoparor Piease Pnnt) fe ~ 15 c ~f.
l 7.
r 8.
Tsue I
- 9. R: viewer Sgnature
- 10. Dato K"y: PAR-Procedure Action Request Form % 730862 puly 93)
(BadQ
O Procedure Action Request vmomurenen ADM 21 VPAP-0502 Instructons for completino this form are included in VPAP-0502
- 1. Prococure Numoer
- 2. Revisen
- 3. Procoeure Change Numoer
- 4. Page VPAP-2103 5
PS1 1 of 154
- 5. Procecure Tsue Offsite Dose Calculanon Manual
- 6. Expiraten Dme N/A
(-]New Procedwe @Procedurehp ]ProcedureRevision ]ProceaneDeintion
~
Vemor Proceaure
- 7. Typeof Recrsest
- 8. Duraton or Extent of Usage
@ Permanent
[ Temporary
[ One Time Only D. Reason For Gnange Incorporate response to N-94-610 and S-94-1058
- 10. Descnoton of Change
{PN & SI) E-Par Add information to various section for the addition NOTE: Station Manager must sign prior to implementation.
i NW 2 6 set,
WGS i
- 11. Requesteo By Name (Psease Pnnt)
- 12. Date
- 13. It the PAR a for a ce6etson to an Acministrauvo Proceoura, C. Tarantino 5-19-94 enter the effective date of the deleton.
14 11 ths PAR s for a Proceours Change, tne Cognizant
- 15. Lead /Responsm6e Dept. Cognizant Supervisor
- 16. Date Supervsor is not required to sign Block 15. The (Signature) sgnature in Block 27 constitutes approval hauem uunv. om.
Omn or inw : o
,:,ea n o w tonorna m:cmon't.ippiv to rtw procedum M
- 17. A change to the stated Purpose of the procedure.
C Yes [ No
- 18. A change in the stated initial Conditions that must be satisfied pnor to performing the procedure.
C Yes h No 19: AchangentheststedAs.p^uance Cnteria that must be satsfied for satrsfactory completion of the procedure.
C Yes [ No
- 20. A modttcanon or deloton of setpoints, independent. or simultaneous verification.
Yes h No
- 21. A change that affects specific actions that are reouired to be accomplished to ensure the satisfactory Yes No completion of the task. This includes changes that affect personnel safety, decrease fire protection effectiveness. affect eouioment oualification. or invohre a less cmneervative method of performing the task.
- 22. A change that relocates or deletes a required hold point. This does not include deleting a secten of a crocedure which includes a hold point.
Cyes No
- 23. A change to CAUTION or WARNING statements. This does not indude adding CAUTION or WARNING Yes b No statements or deleting a section of a orwure which includes CAUTION or WARNING statements.
- 24. A change that modifies or deletes the method for meeting a commitment identifed in the procedure.
C Yes ] No
- 25. A change that results in a "Yes' answer to any of the questions on the PAR Activity Screening Cheddist.
Yes [ No
- 26. Does the cover sheet of this procedure indicao " infrequently Conducted or Complex Test or Evolution
- or "Soecial Test." or is this procedure an emeroency plan implementing procedurs?
Yes No lierryetshoomesmeen '
-^
a.
- 27. Lean /Responsc6e Dept. --- ~ 4 Supervm. or (Sgnature)
- 28. Date
~..s_m mm YeIDb eesksisenUh
[
Procedure Change Delet#on and Station f. i nager Approval
- 29. Shift Supervisor (Senature)
- 30. One 31.SNSOC Approval a
Required.
Prippto-use Within 14 Days
- 32. SNS harman (Sgnature) 33 Date 34.Sta (Sgnature) 35 ney: eA oameueen sequest; emaaoen reusener seseer one operseone
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- 3. Preparer Name (Please Pnnt)
M " a,"r'eelarenestaisestisurfGWWMDNGRW:asuRh WPAP 3088;Se 4g 4 Tale MEMWsw
- 5. PreparerSgnature g
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- 7. Dewer Name (On Autnonzed Preparor-P6 ease Pnnt)8.
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- 9. ReviewerSgnature
- 10. Dato Key: PAPh=ure Actson Request gs=Jaossawysa)
i.evel 2 ControNed Distribution Maint0ined by this Department Do not remove this document for field work O~
Station Administrative Procedure VIRGINM POWB C 1994 by Vsryuus Power. All Raphis Rese#wed
Title:
Offsite Dose Calculation Manual Lead Department: Radiological Protection Procedure Number Revision Number Effective Date VPAP-2103 6
12/01/94 Revision Summary
. Reference commitment 3.2.2 in Step 6.6.1.a.2 and Attachment 23 to ensure the commitment is not deleted a date.
. Correct page numberreferenced in Attachment 6 page I of 5 definitions fi and Ai. Add definition of"21"i Ai on Attachment 6 page 2 of 5.
On Attachment 7 corrected " Total Body Ai and Critical Organ Ai" to " Total Body Bi and l_iver Bi".
. Added alphabetic identifiers to first three items in first column on Attachment 10 and 11.
. Changed note I on Attachment 17 page 3 of 3 from " Automatic isolation of this pathway" to " Automatic actuat of the valves in this pathway'.
. Change step 6.7.2.a.3 to include classification of unplanned liquid and gaseous effluent releases for the Annual Radioactive Effluent Release Report.
. Delete Bi-monthly River Water samples from Attachment 22 page 3 of 4.
Change location of sample points for Oysters.
i
. Delete sediment requirements at Burwell's Bay rd Newport News
. Delete sample point of clams at.lamestown. The number of required samples was reduced from 5 to 4.
. Change collection frequency for fish and invenebrates in sections a and b on Attachment 20 page 2 of 3 fro monthly to Semi-Annually, Correct distance location of R.D on Attachment 22 page I of 4 from.331o.29 miles.
i
. Incorporate PN&S t. Change equipment mark numbers to new format.
. Changed Attachments 14 and 16 to include mark numbers for VG.RM.104 and ventilation flow rate rnonitors j
Surry Power Station North Anna Power Station 1
Approv y:
Approved by:
n 7 -'M M.T.W u
/,JNSOCCpairman Da'te/
SNSOC Chairman Date U
/
Appro d by:
(
Approved by:
O Y e h-
//-5-PF J
"-7 Station Manager Date Station Manager Date Approved by:
//-M - 9W Vice Pr'esident-Nuclear Operations Date Form >#o 7237584Apr SI)
VPAP-2103 POWER REVISION 6 PAGE 2 OF 156 2
Intentionally Blank 4
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VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 3 OF 156 TABLE OF CONTENTS Section Page t
i 1.0 PURPOSE l
7 2.0 SCOPE 7
3.0 REFERENCES
/ COMMITMENT DOCUMENTS 8
4.0 DEFINITIONS 9
5.0 RESPONSIBILITIES 13 6.0 INSTRUCTIONS 15 6.1 Sampling and Monitoring Criteria 15 6.2 Liquid Radioactive Waste Emuents 15 6.2.1 Liquid Effluent Concentration Limitations.
15 6.2.2 Liquid Monitoring Instrumentation 16 6.2.3 Liquid Effluent Dose Limit
)
20 6.2.4 Liquid Radwaste Treatment 23 6.2.5 Liquid Sampling 24 6.3 Gaseous Radioactive Waste Effluents 24 6.3.1 Gaseous Effluent Dose Rate Limitation 24 6 3.2 Gaseous Monitoring Instrumentation 27 6.3.3 Noble Gas Effluent Air Dose Limit 30 6.3.4 I-131,1-133, H-3, and Radionuclides In Particulate Form Effluent Dose Limit 33 6.3.5 Gaseous Radwaste Treatment 36 6.4 Radioactive Liquid and Gaseous Release Permits 38 6.4.1 Liquid Waste Batch Release Permits 38 6.4.2 Continuous Release Permit 39 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit 39 6.4.4 Reactor Containment Release Permits 40 6.4.5 Miscellaneous Gaseous Release Permit 40 1
. VIRGINIA VPAP-2103 POWER REVISION 6 3
PAGE 4 OF 156.
- TABLE OF CONTENTS (continued)
Section Page i
6.4 Radioactive Liquid and Gaseous Release Permits (continued) 6.4.6 Radioactive Liquid and Gaseous Release Controls 40
'6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 41 6.6 Radiological Environmental Monitoring 43 6.6.1 Monitoring Program 43 6.6.2 Land Use Census 45 6.6.3 Interlaboratory Comparison Program
' 46 6.7 Reporting Requirements 47 6.7.1 Annual Radiological Environunental Operating Report 47 6.7.2 Annual Radioactive Emuent Release Report 48 6.7.3 Annual Meteorological Data 49 6.7.4 Changes to the ODCM 50 i
7.0 RECORDS 51 ATTACHMENTS 1 Surry Radioactive Liquid Effluent Monitoring Instrumentation 53 2 North Anna Radioactive Liquid Emuent Monitoring Instrumentation 55 3 Surry Radioactive Liquid Effluent Monitoring Instrumentation 57 Surveillance Requirements 4 North Anna Radioactive Liquid Effluent Monitoring Instrumentation 59 Surveillance Requirements 5 Liquid Ingestion Pathway Dose Factors for Surry Station Units 1 and 2 61 6 North Anna Liquid Ingestion Pathway Dose Factor Calculation Units 1 and 2 63 7 North Anna Liquid Pathway Dose Commitment Factors for Adults 69 8 Surry Radioactive Liquid Waste Sampling and Analysis Program 71 9 North Anna Radioactive Liquid Waste Sampling and Analysis Program 75 10 Surry Radioactive Gaseous Waste Sampling and Analysis Program 79 11 North Anna Radioactive Gaseous Waste Sampling and Analysis Program 85 12 Gaseous Effluent Dose Factors for Surry 89 13 Gaseous Emuent Dose Factors for North Anna 93 l
l
VIRDINIA POWER VPAP-2103 REVISION 6 i
PAGE 5OF 156 i
i TABLE OF CONTENTS (continued)
Section Page ATTACHMENTS (continued) 14 Surry Radioactive Gaseous Emuent Monitodtg Instrumentation.
97 i
15 North Anna Radioactive Gaseous Emuent Monitoring Instrumentation 99 16 Surry Radioactive Gaseous Effluent Monitoring Instrumentation 105 Surveillance Requirements 17 North Anna Radioactive Gaseous Effluent Monitoring Instrumentation 107 I
Surveillance Requirements 18 Critical Organ and Inhalation Dose Factors for 5e ry til 19 Critical Organ Dose Factors for North Anna 113 l
20 Surry Radiciogical Environmental Moisitoring Program 115 I
21 North Anna Radiological Emhismental Monitoring Program i19 i
22 Surry Environmental Sampling Locations 125 23 North Anna Environmental Sampling Locations 129 24 Detection Capabilities for Surry Environmental Sample Analysis 133 25 Detection ~ Capabilities forNorth Anna EnvironmentalSample Analysis 135 26 Reporting Levels for Radioactivity Concentrations in Envimnmental 137 Samples at Surry
?
27 Reporting Levels for Radioactivity Concentrations in Envimnmental 139 Samples at North Anna 28 Surry Meteorological, Liquid, and Gaseous Pathway Analysis 141 e
29 North Anna Meteorological, Liquid, and Gaseous Pathway Analysis 149 i
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i VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 6 OF 156 l
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- VIRGINIA '
VPAP-2103
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= REVISION 6 PAGE 7 OF 156 1.0 PURPOSE The ' ffsite Dose C"alculation Manual (ODCM) establishes requirements for the Radioactive O
Effluent and Radiological Environmental Monitoring iYograms. Methodology and parameters are provided to calculate offsite doses resulting from radioactive gaseous and liquid effluents, to calculate gaseous and liquid effluent monitoring alarm / trip setpoints, and to conduct the l
Environmental Monitoring Program. Requirements are established for the Annual.
Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Station Technical Specifications. Calculation of offsite doses due to radioactive liquid and gaserms emuents are performed to assure that:
. Concentration of radioactive liquid emuents to the unrestricted area will be limited to ten times the effluent concentration values of 10 CFR 20, Appendix B. Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases and 2E-4 Ci/ml for dissolved or entrained noble gases.
. Exposure to the maximum exposed member of the public in the unrestricted area from radioactive liquid effluents will not result in doses greater than the liquid dose limits of 10 CFR 50, Appendix I
. Dose rate at and beyond the site boundary from radioactive gaseous effluents will be limited to:
.. Noble gases'-less than or equal to a dose rate of 500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin
.1333, 1133, and H, and all radionuclides in particulate form with half-lives greater than 8 3
days -less than or equal to a dose rate of 1500 mrem /yr to any organ
. Exposure from radioactive gaseous effluents to the maximum exposed member of the public in the unrestricted area will not result in doses greater than the gaseous dose limits of 10 CFR 50, Appendix I, and
. Exposure to a real individual will not exceed 40 CFR 190 dose limits 2.0 SCOPE This procedure applies to the Radioactive Effluent and Environmental Monitoring Programs at Surry and North Anna Stations.
I
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- VIRGINIA VPAP-2103 l
POWER REVISION 6
'l PAGE 8 OF 156 3
3.0 REFERENCES
/ COMMITMENT DOCUMENTS t
3.1 References
~
3.1.1 10 CFR 20, Standarcis for Protection Against Radiation 3.1.2 10 CFR 50, Domeuic Licensing of Production and Utilization Facilities 3.1.3 ' 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations 3.1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites ~
i 3.1.5 Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Rev.1, U.S. NRC, June 1974 3.1.6 Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Releases of Reactor Eftluents for the Purpose of Evaluating Compliance With 10 CFR 50, Appendix I, Rev.1, U.S. NRC, October 1977 l
3.1.7 Regulatory Guide'l.111 Methods for Estimating Atmospheric Transport and l
Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Rev.1, U.S. NRC, July 1977 3.1.8 Surry and North Anna Technical Specifications (Uni:s I and 2) 3.1.9 NUREG-0324, XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Eeleases at Nuclear Power Stations, U.S. NRC, September 1977 3.1.10 NUREG/CR-1276, Users Manual for the LADTAP II Program, U.S. NRC, May,1980 3.1.11 NUREG-0597, User's Guide to GASPAR Code, U.S. NRC, June,1980 3.1.12 Radiological Assessment Branch Technical Position on Environmental Monitoring, November,1979, Rev.1 3.1.13 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for l.
Nuclear Power Stations, October,1978 3.1.14 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 3.1.15 NUREG-0472, Standani Radiological Effluent Technical Specifications for Pressurized Water Reactors, Rev. 3, March 1982 3.1.16 Environmental Measurements Laboratory, DOE HASL 300 Manual 3.1.17 NRC Generic 1.etter 89-01, Implementation of Programmatic Controls for l
Radiological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of
'j RETS to the Offsite Dose Calculation Manual or to the Process Control Program l
3.1.18 UFSAR (Surry and North Anna) l l
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VIRGINIA VPAP-2103 '.
. POWER.
REVISION 6 L
- PAGE 9 OF 156' 4
3.1.19 Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual,.
IWL-0032-361 3.1.20 VPAP-2802, Notifications and Reports 3.1.21 NAPS Circulating Water System Modifications
- a. DC-85-37-1 Unit 1 1
- b. DC-85-38-2 Unit 2 i
3.2 Commitment Documents 3.2.1 ' Quality Assurance Audit Report Number C 90-22, Management Safety Review i
Committee, Observation 03C, January 17,1991.
3.2.2 Quality Assurance Audit Report Number 91-03, Observation 08N-i 3.2.3 Quality Assurance Audit Report Number 92-03, Observation 02N -
l 3.2.4 Quality Assurance Audit Report Number 92-03, Observation 04NS (Item 2) 4.0 DEFINITIONS 4.1 Channel Calibration Adjustment, as necessary, of the channel output so it responds with the necessary range and accuracy to known values of the parameter the channel monitors. It encompasses the entire channel, including the sensor and alarm and/or trip functions and the Channel Functional Test.
i The Channel Calibration can be performed by any series of sequential, overlapping, or total i
channel steps so the entire channel is calibrated.
e 4.2 Channel Check A qualitative assessment, by observation, of channel behavior during operation. This assessment includes, where possible, comparison of the channel indication and/or status with
{
uther indications and/or status derived from independent instrumentation channels measuring the same parameter.
i 4.3 Channel Functional Test There are two types of Channel Functional Tests.
4.3.1 Analog Channel Injection of a simulated signal into a channel, as close to the sensor as practicable, to i
verify Operability, including alarm and/or trip functions.
> VIRGINIA VPAP-2103 -
- POWER REVISION 6 '
PAGE 10 OF 156 4.3 -
Channel Functional Test (continued) -
4.3i ' Bistable Channel Injection of a simulated signal into a sensor to verify Operability, including alarm and/
or trip functions.
.4.4 Critical Organ That organ, which has been determined to be the maximum exposed organ based on an effluent pathway analysis, thereby ensuring the dose and dose rate limitations to any organ will not be exceeded.
4.5 Dose Equivalent I-131 l
That concentration of1131 (microcune/ gram) that alone would produce the same thyroid dose
,and1 actually present. Thyroid f
as the quantity and isotopic mixture of1131, 1132,g133,1134 135 dose conversion factors for this calculation are listed in Table III of TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites. Thyroid dose conversion factors from NRC Regulatory Guide 1.109, Revision 1, may be used (Surry).
4.6 Frequency Notations NOTE: Frequencies are allowed a maximum extension of 25 percent.
NOTATION FREQUENCY D - Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W - Weekly At least once per 7 days M - Monthly At least once per 31 days Q - Quarterly At least once per 92 days S A - Semi-annually At least once per 184 days I
R - Refueling At least once per 18 months S/U - Start-up Prior to each reactor start-up
[
P - Prior to release Completed prior to each release N.A. - Not app,licable Not applicable DR - During the release At least once during each release t
p
- VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 11 OF 156 4.7 Gaseous Radwaste Treatment System A system that reduces radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing delay or holdup to reduce total radioactivity l
prior to release to the environment. The system comprises the waste gas decay tanks, regenerative heat exchanger, waste gas charcoal filters, process vent blowers, waste gas surge tanks, and waste gas diaphragm compressor (North Anna).
4.8 General Nomenclature x = Chi: concentration at a point at a given instant (curies per cubic meter)
D = Deposition: quantity of deposited radioactive material per unit area (curies per square meter)
Q = Source strength (instantaneous; grams, curies)
= Emission rate (continuous; grams per second, curies per second)
= Emission rate (continuous line source; grams per second per meter) 4.9 Lower Limit of Detection (LLD)
The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that can be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
s 4.10 Members of the Public Individuals who, by virtue of their occupational status, have no formal association with the Station. This category includes non-employees of Virginia Power who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with Station l
functions. This category does not include non-employees such as vending machine servicemen or postal workers who, as part of their formal job function, occasionally enter an area that is controlled by Virginia Power to protect individuals from exposure to radiation and radioactive materials.
4.11 Operable-Operability A system, subsystem, train, component, or device is operable or has operability when it is capable of performing its specified functions and all necessary, attendant instmmentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or l
device to perform its functions are also capable of performing their related support functions.
i
VIRGINIA VPAPo2103 POWER REVISION 6 FAGE 12 OF 156 4.12 Purge - Purging -
Controlled discharge of air or gas ' rom a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, so that replacement air or gas is required to purify the confinement.
4.13 Rated Thermal Power Total reactor core heat transfer rate to reactor coolant.
. Surry-2441 Megawatt Thermal (MWt)
. Nonh Anna-2893 MWt 4.14 Site Boundary The line beyond which Virginia Power does not own, lease, or otherwise control the land.
4.15 Source Check A qualitative assessment of channel response when a channel sensor is exposed to radiation.
This applies to installed radiation monitoring systems.
4.16 Special Report A report to NRC to comply with Subsections 6.2,6.3, or 6.5 of this procedure. Also refer to VPAP-2802, Notifications and Reports.
4.17 Thermal Power Total reactor core heat transfer rate to the reactor coolant.
4.18 Unrestricted Area Any area at or beyond the site boundary, access to which is neither limited nor controlled by Virginia Power for purposes of protection of individuals from exposure to radiation and radioactive materials. or any area within the site boundary used for residential quarters or for industrial. commercial. institutional or recreational purposes.
l
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.VPAP-2103 POWER -
REVISION 6 PAGE 13 OF 156 4.19 Ventilation Exhaust Treatment System l
A system that redtices gaseous radiciodine or radioactive material in particulate form in f
effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and High f
Efficiency Particulate Air (HEPA) filters to remove iodines and particulates from a gaseous exhaust stream prior to release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup systems l
are not Ventilation Exhaust Treatment System components.
5.0 RESPONSIBILITIES i
5.1 Superintendent Radiological Protection The Superintendent Radiolegical Protection is responsible for:
I 5.1.1 Establishing and maintaining procedures for surveying, sampling, and monitoring radioactive effluents and the environment.
5.1.2 Surveying, sampling, and analyzing plant effluents and environmental monitoring, and documenting these activities.
5.1.3 Analyzing plant effluent trends and recommending actions to correct adverse trends.
i 5.1.4 Preparing Effluent and Environmental Monitoring Program records.
5.2 Superintendent Operations I
The Superintendent Operations is responsible for requesting samples, analyses, and authorization to release effluents.
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POWER REVISION 6 PAGE 14 OF 156 b
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VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 15 OF 156 6.0 INSTRUCTIONS NOTE: Meteorological, liquid, and gaseous pathway analyses are presented in Attachments 28 and 29, Meteorological. Liquid, and Gaseous Pathway Analysis.
f 6.1 Sampling and Monitoring Criteria 6.1.1 Surveys, sampling, and analyses shall use instruments calibrated for the type and range of radiation monitored and the type of disefiarge monitored.
6.1.2 Installed monitoring systems shall be calibrated for the type and range of radiation or parameter monitored.
6.1.3 A sufficient number of survey points shall be used or samples taken to adequately assess the status of the discharge monitored.
6.1.4 Samples shall be representative of the volume and type of discharge monitored.
6.1.5 Surveys, sampling, analyses, and monitoring records shall be accurately and legibly documented, and sufficiently detailed that the meaning and intent of the records are clear.
6.1.6 Surveys, analyses, and monitoring records shall be reviewed for trends, completeness, and accuracy.
6.2 Liquid Radioactive Waste Emuents 6.2.1 Liquid Effluent Concentration Limitations j
- a. Liquid waste concentrations discharged from the Station shall not exceed the following limits:
- 1. For radionuclides (other than dissolved or entrained noble gases), liquid effluent concentrations released to unrestricted areas shall not exceed ten times the effluent concentration values specified in 10 CFR 20, Appendix B, Table 2, Column 2.
- 2. For dissolved or entrained noble gases, concentrations shall not exceed 2E-4 pCi/ml.
- b. If the concentration ofliquid effluent exceeds the limits in 6.2.1.a., promptly reduce concentrations to within limits.
(P
-VIRGINIA.
VPAP-2103 POWER REVISION 6 ~
PAGE 16 OF 156' 6.2.1 Liquid Emuent Concentration Limitations (continued)
- c. Daily concentrations of radioactive materials in liquid waste released to unrestricted areas shall meet the following:
Volume of Waste Discharged + Volume of Dilution Water 3
(3) pCi/ml.
Volume of Waste Discharged x ACW.
1 I
where:
pCi/ml; = the concentration of nuclide i in the liquid effluent discharge ACW;
= ten times the effluent concentration value in unrestricted areas of
. nuclide i, expressed as pCi/ml from 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases, and 2E-4 pCi/ml for
. dissolved or entrained noble gases 6.2.2 Liquid MonitoringInstrumentation
- a. Radioactive Liquid Emuent Monitoring Instrumentation Radioactive liquid effluent monitoring instrumentation channels shown on Attachments 1 and 2, Radioactive Liquid Effluent Monitoring Instrumentation, i
shall be operable with their alarm / trip setpoints set to ensure that 6.2.1.a. limits are not exceeded.
- 1. Alarm / trip setpoints of these channels shall be detennined and adjusted in accordance with 6.2.2.d., Setpoint Calculation.
- 2. If a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint is less conservative than required by 6.2.2.a., perform one of the followmg:
. Promptly suspend release of radioactive liquid effluents monitored by the affected channel Declare the channelinoperable
. Change the setpoint to an acceptable, conservative value
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- VIRGINIA.
- VPAP-2103
')
. POWER :
REVISION 6 PAGE 17 OF 156
- b. Radioactive Liquid Emuent Monitoring Instrumentation Operability Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performing a Channel Check, Source Check, Channel i
Calibration, and Channel Functional Test at the frequencies shown in Attachments l
3 and 4, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.
L
- 1. If the number of operable channels is less than the minimum required by the
~
tables in Attachment 1 or 2, pet!.rm the action shown in those tables.
- 2. Attempt to retum the instruments to operable status within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. Applicable Monitors Liquid effluent monitors for which alarm / trip setpoints shall be determined are:
Release Point Instrument Number t
North Anna Surry Liquid Radwaste Effluent Line 1-LW-RM-111 N/A -
l Service Water System Effluent Line 1-SW-RM-108 1-SW-RM-107 A, l
B,C,D Condenser Circulating Water Line 1-SW-RM-130 1-SW-RM-120 2-SW-RM-230 2-SW-RM-220 Radwaste Facility Effluent Line N/A 1-RRM-RITS-131 l
i l
i h
6 f
I
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 18 OF 156 6.2.2 Liquid Monitoring Instrumentation (continued)
- d. Setpoint Calculation NOTE: This methodology does not preclude use of more conservative setpoints.
- l. Maximum setpoint values shall be calculated by:
CFD S=F (2)
E where:
the serpoint,in Ci/ml, of the radioactivity monitor measuring the S
=
radioactivity concentration in the effluent line prior to dilution C= the effluent concentration limit for the monitor used to implement 10 CFR 20 for the Station,in pCi/ml F = maximum design pathway effluent flow rate E
Fo = dilution water flow rate calculated as:
(Surry) D = F + (200,000 gpm x number of cire, pumps in service)
E (N. Anna) D = Fg + (218,000 gpm x number of cire. pumps in service)
- 2. Each of the condenser circulating water channels (Surry: SW-120, SW-220)
(North Anna: SW-130, SW-230) monitors the effluent (service water, including component cooling service water, circulating water, and liquid radwaste) in the circulating water discharge tunnel beyond the last point of possible radioactive material addition. No dilution is assumed for this pathway. Therefore, Equation (2) becomes:
S=C (3)
The setpoint for Station monitors used to implement 10 CFR 20 for the site becomes the effluent concentration limit.
- 3. In addition, for added conservatism, setpoints shall be calculated for the liquid radwaste effluent line (Nonh Anna: LW-111), the service water system effluent line (Surry: SW-107 A, B, C, and D, Nonh Anna: SW-108), and the Radwaste.
Facility effluent line (Surry: RRM-131).
i
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 19 OF 156 -
h
- 4. For the liquid radwaste effluent line, Equation (2) becomes:
CF K D gw S=
(4)
FE where:
Kw t
The fraction of the effluent concentration limit, used to implement
=
10 CFR 20 for the site, attributable to the liquid radwaste effluent line pathway
- 5. For the service water system effluent line, Equation (2) becomes:
CF K D sw S=
(5)
FE where:
Ksw The fraction of the effluent concentration limit, used to implement
=
10 CFR 20 for the Station, attributable to the service water effluent line pathway
- 6. For the Radwaste Facility effluent line, Equation (2) becomes:
(6)
Fg where:
Kgw The fraction of the effluent concentration limit, used to implement
=
10 CFR 20 attributable to the Radwaste Facility effluent line pathway
- 7. The sum K w + Ksw + Kaw shall not be greater than 1.0.
t
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 20 OF 156 6.2.3 Liquid Effluent Dose Limit
- a. Requirement At least once per 31 days, perform the dose cdiculations in 6.2.3.c. and 6.2.3.d. to ensure the dose or dose commitment to the maximum exposed member of the public from radioactive materials in liquid releases (from each reactor unit) to unrestricted areas is limited to:
- 1. During any calendar quarter:
. Less than or equal to 1.5 mrem to the total body
. Less than or equal to 5 mrem to the critical organ
- 2. During any calendar year:
. Less than or equal to 3 mrem to the total body
. Less than or equal to 10 mrem to the critical organ
- b. Action If the calculated dose from release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that identifies causes for exceeding limits and defines corrective actions taken to reduce releases of radioactive materials in liquid effluents to ensure that subsequent releases will be in compliance with the above limits.
- c. Surry Dow Contribution Calculations NOTE: Thyroid and GI-LLI organ doses must be calculated to determine which is the critical organ for the period being considered.
Dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on the equation:
D = t F M [C;A; (7) i where:
Subscripts i, refers to individual radionuclide
=
l l
l
VIRGINIAi VPAP-2103 '
a POWER -
REVISION 6 PAGE 21 OF 156~-
f D = the cumulative dose commitment to the total body or critical organ'from the e
liquid effluents for the period t, in mrem the period for which C; and F are Averaged for allliquid releases,in hours t
=
M=
the mixing ratio (reciprocal of the dilution factor) at the point of exposure,-
dimensionless,0.2 from Appendix 11 A, Surry UFSAR F=
the near field average dilution factor for C during any liquid effluent ~
i release; the ratio of the average undiluted liquid waste flow duiing release to the average tiow from the site discharge structure to unrestricted areas '
C=
the average concentration of radionuclide, i, in undiluted liquid effluent i
during the period t, from all liquid releases, in pCi/ml A; = the site-related ingestion dose commitment factor to the total body or critical organ of an adult for each identified principal gamma and beta emitter in mrem-ml per hr-pCi. Values for A are given in Attachment 5, Liquid i
. Ingestion Pathway Dose Factors For Surry Power Station.
A; = 1.14 E+05 (21BF; + 5BI;) DF; (8) where:
1.14 E+05 1 E+06 pCi/pCi x 1 E+03 ml/kg/(8760 hr/yr), units conversion
=
factor 21 adult fish consumption, kg/yr, from NUREG-0133
[
=
5 adult invertebrate consumption, kg/yr, from NUREG-0133
=
BI; the bioaccumulation factor for nuclide i, in invertebrates, pCi/kg per
=
pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev. I BF the bioaccumulation factor for nuclide i, in fish, pCi/kg per pCi/1, from
=
i Table A-1 of Regulatory Guide 1.109, Rev.1 DF; = the critical organ dose conversion factor for nuclide i, for adults, in mrem /pCi, from Table E-11 of Regulatory Guide 1.109, f.ev.1 t
E 9
vm
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 22 OF 156 6.2.3 Liquid Effluent Dose Limit (continued)
'd. North Anna Dose Contribution Calculation,s I
NOTE: Attachment 6, North Anna Liquid Ingestion Pathway Dose Factor Calculation provides the derivation for Equation (9).
Dose contribution shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on:
(9)
D = [Q;x B;
{
i Where:
Subscripts = i, refers to individual radionuclide i
D=
the cumulative dose commitment to the total body or critical organ from the liquid effluents for the period t, in mrem Bi= Dose Commitment Factors (mrem /Ci) for adults. Values for Bi are provided in Attachment 7, North Anna Liquid Ingestion Pathway Dose Commitment Factors for Adults Qi = Total released activity for the considered period and the ith nuclide Q = t x C; x Waste Flow (10)-
i Where:
the period for which C; and F are averaged for all liquid releases, in t
=
hours C; = the average concentration of radionuclide, i, in undiluted liquid effluent during the period, t, from any liquid releases, in pCi/ml
- e. Quarterly Composite Analyses For radionuclides not determined in each batch or weekly composite, dose contribution to current monthly or calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on previous mon'thly or quarterly composite analyses. However, for reporting purposes, calculated dose contribution shall be based on the actual composite analyses.
i
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VIRGINIA VPAP-2103
' POWER REVISION 6
'l PAGE 23 OF 156 1
I
{
6.2.4_ Liquid Radwaste Treatment I
- a. Requirement-
- 1. The Liquid Radwaste Treatment System and/or the Suny Radwaste Facility Liquid Waste System shall be used to reduce the radioactive materials in liquid
-l waste prior to discharge when projected dose due to liquid effluent, from each l l
reactor unit, to unrestricted areas would exceed'0.06 mrem to total body or 0.2 mrem to the critical organ in a 31-day period.
l
- 2. Doses due to liquid releases shall be projected at least once per 31 days.'
- b. Action If radioactive liquid waste is discharged without treatment and in excess of the above limits prepare and submit to the NRC, within 30 days,'a special report in
'l accordance with VPAP_-2802, Notifications and Reports, that includes the.
following:
- 1. An explanation of whyliquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-system, and the reason for the I
inoperability.
i
- 2. Actions taken to restore inoperable equipment to operable status.
- 3. Summary description of actions taken to prevent recurrence,
- c. Projected Total Body Dose Calculation l
- 1. Determined 73, the total body dose from liquid effluents in the previous 31-day period, per Equation (7) or Equation (9) (Surry and North Anna, respectively).
- 2. Estimate R, the ratio of the estimated volume ofliquid effluent releases in the '
3 present 31-day period to the volume released in the previous 31-day period.
I
- 3. Estimate F, the ratio of the estimated liquid effluent radioactivity concentration 3
in the present 31-day period to liquid effluent concentration in the previous 31-day period (pCi/ml).
- 4. Determine PDTB, the projected total body dose in a 31-day period.
PDTB = DTB(R3 F)
(11) i r
t 4
b 1
1 3
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 24 OF 156 6.2.4 Liquid Radwaste Treatment (continued)
- d. Projected Critical Organ Dose Calculation,
H'istorical data penaining to the volumes and radioactivity ofliquid effluents released in connection with specific Station functions, s' ch as maintenance or u
refueling outages, shall be used in projections as appropriate.
- 1. Determine D,'the critical organ dose from liquid effluents in the previdus o
31-day period, per Equation (7) or Equation (9) (Surry and North Anna, respectively).
- 2. Estimate R as in 6.2.4.c.2.
3
- 3. Estimate F as in 6.2.4.c.3.
i
- 4. Determine PD, = projected critical organ dose in a 31-day period.
PDO = D @lF)
O 3
6.2.5 Liquid Sampling Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis requirements in Attachments 8 and 9, Radioactive Liquid Waste Sampling and Analysis Program (Surry and North Anna, respectively).
6.3 Gaseous Radicactive Waste Emuents 6.3.1 Gaseous Emuent Dose Rate Limitation
- a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to:
- 1. The dose rate limit for noble gases shall be s 500 mrem / year to the total body and s 3000 mrem / year to the skin.
- 2. The dose rate limit for 1I33,1333. for tritium, and for all radioactive materials in l
particulate form with half-lives greater than 8 days shall be g 1500 mrem / year to the critical organ.
- b. Action
- 1. If dose rates exceed 6.3.1.a. limits, promptly decrease the release rate to within the above limits.
l
~ VIRGINIA VPAP-2103 POWER REVISION 6 -
PAGE 25 OF 156 I
- 2. Dose rates due to noble gases in gaseous effluents shall be determined, continuously, to be within 6.3.1.a. limits.
i
- 3. Dose rates due to 1833, 1133, tritium, and all radionuclides in particulate form l
with half-lives greater than 8 days, in gaseous effluents shall be determined to be within the above limits by obtaining representative samples and performing l
analyses in accordance with the sampling and analysis program specified on Attachments 10 and 11, Radioactive Gaseous Waste Sampling and Analysis Program.
s J
i l
l i
l 1
1 l
I i
1 i
1
VPAP-2103.
POWER REVISION 6 PAGE 26 OF 156 6.3.1 Gaseous Emuent Dose Rate Limitation (continued)
- c. Calculations of Gaseous Emuent Dose Rates
- 1. The dose rate limit for noble gases shall be determined to be within the limit by limiting the release rate to the lesser of:
[K;yyd;yy+K;pyd;py] 5 500 mrem /yr to the total body (13) 3 i
OR i
[l0 yy + 1.1M;yy ) d;yy + 0 ;py + 1.1M py ) dipyl s 3000 mrem /yr to the I
(14) j where:
Subscripts vv, refers to vent releases from the building ventilation vent,
=
including Radwaste Facility Ventilation Vent; pv, refers to the vent releases from the process vent; i, refers to individual radionuclide K yy, K;py The total body dose factor for ventilation vents or process vent
=
release due to gamma emissions for each identified noble gas radionuclide i, in mrem /yr per Curie /sec. Factors are listed in Attachments 12 and 13, Gaseous Effluent Dose Factors (Surry and Nonh Anna,respectively)
The skin dose factor for ventilation vents or process vent Livy,L;py
=
release due to beta emissions for each identified noble gas radionuclide i, in mrem /yr per Curie /sec. Factors are listed in Attachments 12 and 13 1
The air dose factor for ventilation vents or process vent release hijyy, M
=
py due to gamma emissions for each identified noble gas radionuclide, i, in mrad /yr per Curie /sec. Factors are listed in Attachments 12 and 13 The release rate for ventilation vents or process vent of noble d d,
=
gas radionuclide i, in gaseous effluents in Curie /sec (per site)
The unit conversion factor that converts air dose to skin dose, 1.1
=
in mrem / mrad
- VIRGINIA VPAP-2103 POWER -
REVISION 6 z
PAGE 27 OF 156
- 2. The dose rate limit for1333,1133, tritium, and for all radionuclides in particulate l
form with half-lives greater than 8 days, shall be determined to be within the limit by restricting the release rate to:-
((P;yyd;yy+P;pyd;py] s 1500 mrem /yr to the critical organ(15) -
i where:
Piyy, Pipy The critical organ dose factor for ventilation vents or process
=
ventfor1331,I 3
3, H, and all radionuclides in paniculate form ]
i with half-lives greater than 8 days, for the inhalation pathway, in mrem /yr per Curie /sec. Factors are listed in Attachments 12 and 13 The release rate for ventilation vents or process vent of 1I33, d,,d,
=
133, H, and all radionuclides i, in particulate form with half-l 3
1 lives greater than 8 days, in gaseous effluents in Curie /sec (per site)
- 3. All gaseous releases, not through the process vent, are considered ground level l
and shall be included in the determination of d.
6.3.2 Gaseous MonitoringInstrumentation
- a. Requirement l
- 1. The radioactive gaseous effluent monitoring instrumentation channels shown in
, 4 or 15, Radioactive Gaseous Effluent Monitoring Instrumentation, shall be operable with alam1/ trip setpoints set to ensure j
that 6.3.1.a. noble gas limits are not exceeded. Alarm / trip setpoints of these channels shall be determined and adjusted in accordance with 6.3.2.d.
- 2. Each radioactive gaseous effluent monitoring instrumentation channe'l shall be demonstrated operable by Channel Checks, Source Checks, Channel Calibrations, and Channel Functional Tests at the frequencies shown in 6 or 17. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.
i l
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 28 OF 156 6.3.2 Gaseous Monitoring Instrumentation (continued)
- b. Action
- 1. If a radioactive gaseous effluent monitoring instrumentation channel alarm / trip l.
setpoint is less conservative than required by 6.3.2.a.1, promptly:
- Suspend the release of radioactive gaseous effluents monitored by the affected channel and declare the channel inoperable or j
Change the setpoint so it is acceptably conservative
- 2. If th' number of operable channels is less than the minimum required by tables e
in Attachment 14 and 15, take the action shown in those tables.
- 3. Return instruments to operable status within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. Applicable Monitors Radioactive gaseous effluent monitors for which alarm / trip setpoints shall be determined are:
Release Point Instrument Number North Anna Surry Process Vent 1-GW-RM-102 1-GW-RM-102 1-GW-RM-178-1 1-GW-RM-130- 1 Condenser Air Ejector 1-SV-RM-121 1-SV-RM-lll 2-SV-RM-221 2-SV-RM-211 Ventilation Vent A 1-VG-RM-104 N/A 1-VG-RM-179-1 Ventilation Vent B l-VG-RM-ll3 N/A 1-VG RM-180-1 Ventilation Vent No. I N/A 1-VG-RM-104 l
Ventilation Vent No. 2 N/A 1-VG-RM-Il0 1-VG-RM-131-1 Radwaste Facility Vent N/A RRM-101 1
I
1 VIRGINIA VPAP-2103
' POWER REVISION 6 PAGE 29 OF 156 I
- d. Setpoint Calculations
- 1. Setpoint calculations for each monitor listed in 6.3.2.c. shall maintain this I
relationship:
D2D p + D,, + D (16) g c
yy where:
1 t
Step 6.3.1.a. dose limits that implement 10 CFR 20 for the Station, D
=
mrem /yr D
The noble gas site boundary dose rate from process vent gaseous l
=
py effluent releases, mrem /yr The noble gas site boundary dose rate from condenser air ejector
[
De
=
c gaseous effluent releases, mrem /yr i
D The noble gas site boundary dose rate from:
=
yy Surry: Summation of the Ventilation Vents 1,2, and the Radwaste i
Facility vent gaseous effluent releases, mrem /yr -
North Anna: Summation of Ventilation Vent A plus B gaseous l
effluent releases, mrem /yr I
I i
i I
1 I
r
I VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 30 OF 156
.j
- 2. Setpoint values shall be determined by:
R x 2.12'E-03 C
(17)
=
m p
m where:
'Ihe release pathway, process vent (pv), ventilation vent (vv) m
=
condenser air ejector (cae), or Radwaste Facility (rv)
C The effluent concentration limit implementing 6.3.1.a. for the
=
m Station, pCi/ml The release rate limit for pathway m determined from R
=
m l33 methodologyin 6.3.1.c.,using Xe as nuclide to be released, Ci/sec 2.12E-03 CFM per ml/sec
=
F The maximum flow rate for pathway m, CFM
=
m NOTE: According to NUREG-0133, the radioactive effluent radiation monitor alarm / trip setpoints should be based on the radioactive noble gases. It is not practicable to apply instantaneous alarm / trip setpoints to integrating monitors sensitive to radiciodines, radioactive materials in particulate form, and radionuclides other than noble gases.
6.3.3 Noble Gas Effluent Air Dose Limit i
- a. Requirement
- 1. The air dose in unrestricted areas due to noble gases released in gaseous effluents from each unit at or beyond the site boundary shall be limited to:
During any calendar quarter: 55 mrads for gamma radiation and 510 mrads for beta radiation
. During any calendar year: 510 mrads for gamma radiation and 520 mrads for beta radiation
- 2. Cumulative dose contributions for noble gases for the ctuTent calendar quarter and current calendar year shall be determined in accordance with 6.3.3.c. at least once per 31 days.
)
i I
i 1
. VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 31 OF 156
- b. Action If the calculated air dose from radioactive noble gases in gaseous effluents exceeds any of the above limits, prepare and subniit to tne NRC, within 30 days, a special repon in accordance with VPAP-2802, Notifications and Reports, that identifies the causes for exceeding the limits and defimes corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits in 6.3.3.a.
- c. Noble Gas Emuent Air Dose Calculation l
Gaseous releases, not through the process vent, are considered ground level and shtU be included in the determination of Qivv.
The air dose to areas at or beyond the site boundary due to noble gases shall be determined by the following:
For gamma radiation:
= 3.17E-08((M;yyQ;yy + M ;pyQ;py]
l D
8 l
i (18) l
g VIRGINIA -
VPAP-2103 --
POWER
- REVISION 6 PAGE 32 OF f56 For beta radiation:
~
Db = 3.17E-08
[N;,Qiyy + N;pyhipy]
(19)
' 1.-
I Where:
i Subscripts = vv, refers to vent releases from the building ventilation vents, -
including the Radwaste Facility Ventilation Vent and air ejectors pv, refers to the vent releases from the process vent i, refers to individual radionuclide' l
8 the air dose for gamma radiation, in mrad i
D
=
Db
=
the air dose for beta radiation, in mrad.
j M vy, Mipv - = the air dose factors for ventilation vents or process vent release i
dee to gamma emissions for each identified noble gas ra Jionuclide i, in mrad /yr per Curie /sec. Factors are listed in Attachments 12 and 13 the air dose factor for ventilat :..i vents or process vent release l
N vy, Nipv i
i
=
due to beta emissions for ear:h identified noble gas radionuclide i, in mrad /yr p:r Curie /sec. Factors are listed in.
Attachments 12 and 13 Qiyy,Qipy the release for ventilation vcnts or process vent of noble gas
=
radionuclide i, in gaseous effi uents for 31 days, quarter, or year as appropriate in Curies (per site) l l
+~$-
v
=
j,
, i VIRGINIA VPAP-2103
. POWER
. REVISION 6 p
4
~.
PAGE 33 OF 156-2 6.3.4.-I-131,1-133, H-3, and Radionuclides In Particulate Form Emuent Dose Limit l
i
- a. Requirement i
y-
- 1. Methods shall be implemented to ensure that the dose to any organ of a member of the public from 1133, 1133, tritium, and all radionuclides in paniculate form l-e with half-lives greater than 8 days,in gaseous effluents released from the site to unrestricted areas from each reactor unit shall be:
- During any calendar quarter: s 7.5 mrem to the critical organ
]
a During any calendar year: s 15 mrem to the critical organ
-l
- 2. Cumulative dose contributions to a member of the public from 1131, 1133
-l~
l tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to unrestricted areas for the current calendar f
quaner and current calendar year shall be determined at least once per 31 days -
in accordance with 6.3.4.'c. or 6.3.4.d.
I
- b. Action If the calculated dose from the release of 1131, 1133, tritium, and radionuclides in l
particulate form, with half-lives greater than 8 days, in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC within 30 days, a special l
repon in accordance widh VPAP 2802, Notifications and Repons, that centains the:
]
- 1. Causes for exceeding limits.
l
- 2. Corrective actions taken to reduce releases.
'l i
- 3. Proposed corrective actions to be taken to assure that subsequent releases will l
i be in compliance with limits stated in 6.3.4.a.
I f
5
- c. Surry Dose Calculations l
Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of d,,,, Historical data pertaining to the.
volumes and radioactive concentrations of gaseous effluents released in connection '
l to specific Station functions, such as containment purges, shall be used in the l
estimates, as appropriate.
l l
i
-1
VIRGINIA VPAP-2103
' POWER REVISION 6
- i
' PAGE 34 OF 156
]
- 1. The dose to the maximum exposed member of the public, attributable to j
gaseous effluents at and beyond the site boundary that contain 1131,1133, tritium, l'
f and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by:
D, = 3.17E 08
[p djyy + W;pyd;py) + W ;yydgyy + M;pyd;py)]
gyy i
Where:
Subscripts vv, refers to vent releases from the building ventilation vents,
=
including the Radwaste Facility Ventilation Vent and air ejectors; py, refers to the vent releases from the process vent j
the dose to the critical organ of the maximum exposed member Dr
=
of the public in mrem RMivy, RMipv= the cow-milk pathway dose factor for ventilation vents or
~ l
- process vent release due to 1131, gt33, tritium, and from all.
particulate-form radionuclides with half-lives greater than 8 days, in mrem /yr per Curie /sec. Factors are listed in l
- 8, Critical Organ and Inhalation Dose Factors For Surry l
Rijyy,Ri v =
the inhalation pathway dose factor for ventilation vents or ip process vent release due to 1131, 1133, tritium, and from all -
l particulate-form radionuclides with half-lives greater than 8 days, in mrem /yr per Curie /sec. Factors are listed in 8 the release for ventilation vents or process vent of 1131, 1133, l-d d,,,
=
tritium, and from all particulate-form radionuclides with half-lives greater than 8 days in Curies 3.17 E-08 the inverse of the number of seconds in a year
=
4
.,me 7,
3,
--m-
--m.--%--e,-
r y,,,
VIRGINIA -
VPAP-2103 POWER REVISION 6 PAGE 35 OF 156 6.3.4 I-131,I-133, H 3, and Radionuclides In Particulate Form Emuent Dose Limit I
(continued)
- d. North Anna Dose Calculations Gaseous releases, not through the procest, vent, are considered ground level and shall be included in the determination of d, Historical data pertaining to the q
volumes and radioactive concentrations of gaseous effluents released in connection j
to specific Station functions, such as containment purges, shall be used in the l
estimates as apprcpriate.
- 1. The dose to the maximum exposed member of the public, attributable to gaseous effluents at and beyond the site boundary, that contain 1333. 1333, l
. (
tritium, and pa ticulate form radionuclides with half-lives greater than 8 days, shall be determined by:
), = 3.17E-08
[RM;yyd;yy + RM;pyd;py (2a 1
Where:
Subscripts = vv, refers to vent releases from the building ventilation vents; pv, refers to the vent releases from the process vent the dose to the critical organ of the maximum exposed member Dr
=
of the public,in mrem RM vy, RMipv =the cow-milk dose factor for ventilation vents or process vent i
release due to 1133, 1333, tritium, and from all particulate-form l
radionuclides with half-lives greater than 8 days,in mrem /yr per Curie /sec. Factors are listed in Attachment 19 Critical Organ Dose Factors for North Anna the release for ventilation vents or process vent of 1133, 1333, l
6,od,y
=
tritium, and from all particulate-form radionuclides with half-lives greater than 8 days m Curies the inverse of the numbo af seconds in a year 3.17 E-08
=
eVIRGINIA VPAP-2103.
t POWER REVISION 6 i
PAGE 36 OF 156 i
6.3.5 Gaseous Radwaste Treatment l
Historical data pertaining to thE volumes and radioactive concentrations of gaseous j
effluents released in connection with specific Sta' tion functions, ssch as containment i
~
purges, shall be used to calculate projected doses, as appropriate.
- a. Requirement i
- 1.. The Gaseous Radwaste Treatment System and the Ventilation Exhaust-Treatment System shall be used to reduce radioactive material in gaseous waste before its discharge, when projected gaseous effluent air doses due to gaseous
[
effluent releases, from each unit to areas at and beyond the site boundary, would i
exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation, averaged q
over 31 days. (North Anna)
- 2. Appropriate portions of the Gaseous Radwaste Treatment System shall be used to reduce radioactive materials in gaseous waste before its discharge, when the projected gaseous effluent air doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation, averaged over 31 days. (Surry)
- 3. The Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste before its discharge, when the projected doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceed 0.3 mrem to the critical organ, averaged over 31 days.
i
- 4. Doses due to gaseous releases from the site shall be projected at least once l
per 31 days, based on the calculations in 6.3.5.c., and 6.3.5.d.
l
- b. Action if gaseous waste that exceeds the limits in 6.3.5.a. is discharged without treatment, prepare and submit to the NRC within 30 days, a special report in accordance with
]
VPAP-2802, Notifications and Reports, that includes:
1
- 1. An explanation why gaseous radwaste was being discha;3ed without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.
- 2. Actions taken to restore the inoperable equipment to operable status.
- 3. Summary description of actions taken to prevent recurrence.
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- VIRGINIA ~
VPAP-2103
. POWER REVISION 6 L.
PAGE 37 OF 156 I
6.3.5 - Gaseous Radwaste Treatment (continued) -
- c. Projected Gamma Dose l
- 1. Determine D, the 31-day gamma air dose for the previous 31-day period, s
per Equation (18).
.i
- 2. Estimate R, the ratio of the estimated volume of gaseous effluent in the current g
31-day period to the volume released during the previous 31-day period.
l l
- 3. Estimate F, the ratio of the estimated noble gas effluent activity in the current g
31-day period to the noble gas effluent activity during the previous 31-day j
period ( Ci/ml).
- 4. Determine PD, the projected 31-day gamma air dose.
s PD = D (R x F )
(22) l 8
8 8
8
- d. Projected Beta Dose
- 1. Determine Db, the 31-day beta air dose in the previous 31 days, per Equation (19).
- 2. Estimate R and Fg as in 6.3.5.c.2. and 6.3.5.c.3.
g
- 3. Determine PD, the projected 31-day beta air dose.
b PDb. = D @g x F, )
(23) l b
i
- e. Projected Maximum Exposed Member of the Public Dose
- 1. Determine Dmax, the 31-day maximum exposed member of the public dose in the previous 31-day period, per Equation (20) or Equation (21), where Dr =
Dmax.
- 2. Estimate F, the ratio of the estimated activity from II31,1I33, radioactive l
i materials in particulate form with half-lives greater than 8 days, and tritium in the current 31-day period to the activity of 1131, 1133, radioactive materials in
_ l particulate form with half-lives greater than 8 days, and tritium in the previous 31-day period (pCi/ml).
(
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. VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 38 OF 156
- 3. Determine PDmax, the projected 31-day maximum exposed member of the public d'ose.
PD,,x = D,,x(R x F; )
(24) g 6.4 Radioactive Liquid and Gaseous Release Permits RP shall maintain procedures for Liquid and Gaseous Release Permits to e'
- effluent dose limits are not exceeded when making releases.
6.4.1 Liquid Waste Batch Release Permits Operations shall obtain RP authorization before initiating batch releases of radioactive liquids. Examples of batch releases include:
- a. Surry Batch Releases Release of contents from the following tanks / sumps other than transfers to the Surry Radwaste Facility shall have a Liquid Waste Batch Release Permit before the discharge:
- Boron Recovery Test Tank (BRTT)
. Low Level Waste Drain Tank (LLWDT)
High Level Waste Drain Tank (HLWDT)
. Liquid Waste Test Tank (LWTT)
+ Contaminated Drain Tank (CDT)
. Laundry Drain Surge Tank (LDST)
. Turbine Building Sumps when RP determines that source activity requires placing pumps in manual mode
. Condensate Polishing Building Sumps when RP determines the presence of contamination from primary-to-secondary leakage l
i l
g VIRGINIA
. VPAP-2103
- POWER REVISION 6 PAGE 39 OF 156 6.4.1 Liquid Waste Batch Release Permits (continued)
- b. North' Anna Batch Releases NOTE: If the clarifier is in service, releases from tanks processed through the clarifier are considered continuoi s releases.
A Batch Release Permit is required for a release from any tanks / sumps which contain (or potentially contain) radioactive liquid. Tanks / sumps include:
.BRTT
. LLWDT
.HLWDT
. Turbine Building Sumps when secondary coolant activity exceeds 1.0 E-5 pCi/ml
.CDT 4
6.4.2 Continuous Release Permit Operations shall obtain RP authorization before initiating continuous releases of radioactive liquids.
- a. Surry Continuous Releases A Continuous release permit is required at Surry for:
. Steam generator blowdown
. Component Cooling Water (CCW) heat exchanger to service water leakage, if applicable
. Turbine B uilding sumps and/or subsurface drains if source activity concentrations are sufficiently low to allow continuous release
- b. North Anna Continuous Releases A Continuous Release Permit is required at North Anna for:
. Clarifier, unless being bypassed
. Steam generator blowdown when clarifier is bypassed
. Containment mat sumps and service water reservoir when clarifier is bypassed 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit Operations shall obtain RP authorization before initiating WGDT releases.
u j
1 VIRGINIA..
- VPAP-1103 POWER -
REVISION 6 PAGE 40 OF 156 i
6.4.4 Reactor Containment Release Permits Operations sh'all obtain authorization from RP before initiating containment purges or
~
containment hogging. Reactor Containment Release Permits shall be valid from start of purge / hog until:.
y
. Routine termination i
. Terminated for cause by RP l
. Receipt of Radiation Monitoring System (RMS) Containment Gas Monitor high alarm 6.4.5 Miscellaneous Gaseous Release Permit Operations shall obtain RP authorization before initiating releases of noble gases that i
may not be accounted for by routine sampling, or any planned release not being routed
.l through the Process Vent or Ventilation Vents (e.g., steam driven auxiliary feedwater pump testing if pnmary to secondary leakage exists).
B 6.4.6 Radioactive Liquid and Gaseous Release Controls i
- a. Operations shall notify RP of pending releases and request RP to initiate the appropriate release permit. Operations shall provide the necessary information to complete the required release permit.
i
- b. A representative sample shall be obtained of the source to be relered.
- 1. Operations shall provide RP with liquid samples and sample infi 'mation (e.g.,
j time of sample) for samples obtained outside the Primary Sample Room, except '
{
Clarifier Proportional Tank and Clarifier Grab Samples at North Anna.
{
- 2. Chemistry shall provide RP with liquid samples a::d sample information for samples obtained from inside the Primary Sample Room.
- 3. RP shall obtain gaseous samples.
- c. RP shall perform required sample analyses,
- d. RP shall calculate and record the following information on a release permit:
. Maximum authorized release rate l
. Maximum authorized release rate in percentage of limits specified by the ODCM
. Applicable conditions or controls pertaining to the release
..-e
4 VPAP-21031
. VIRGINIA'
. REVISION 6 4
- POWER PAGE 41 OF 156 -
,j
~
6.4.6 ' Radioactive Liquid and Gaseous Release Controls (continued)
- e. RP shall notify the Shift Supervisor if it is determined that a release may not be l
within the effluent dose limits.
- f. Upon receipt of a release permit from RP, Operations shall:
- 1. Verify the correct source is authorized for release.
- 2. Note maximum authorized release rate.
i L
- 3. Note percent of Technical Specification limits the release represents.
- 4. Note and ensure compliance with any indicated controls or conditions applicable to the release.
i
- g. When commencing release, Operations shall provide RP with required information.
.r As appropriate, required information shall include:
- Date and time release was started
. Starting tank / sump level l
. Beginning pressure
~
. Release flow rate "~ '
'. Dilution water flow rate f
I
- h. Upon terminating the release, Operations shall return the permit to RP and provide information necessary for completion of permit. As appropriate, required j
information shallinclude:
. Date and time release was stopped j
. Tank / sump ending level i
. Release flow ratejust prior to termination j
. Ending pressure i
i
. Volume released 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 6.5.1 Requirement l
1 The annual (calendar year) dose or dose commitment to a real individual due to i
releases of radioactivity and radiation from uranium fuel cycle sources shall not i
exceed 25 mrem to the total body or the critical organ (except the thyroid, which shall not exceed 75 mrem).
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VIRGINIA VPAP 2103
". L POWER
' REVISION 6 i
RAGE 42 OF 156 l
t 6.5.2 Action i
- a. If the calculated doses from release of radioactive materials in liquid or gaseous i
effluents exceed twice the limits in 6.2.3.a., 6.'3.3.a., or 6.3.4.a., calculate (including direct radiation contribution from the units and from outside' storage 1
tanks) whether limits in 6.5.1 have been exceeded.
- b. If the limits in 6.5.1 have been exceeded, prepare and submit to the NRC within 30 i
' days, a special report in accordance with VP'AP-2802, Notifications and Reports, i
that defines the corrective action to be taken to reduce subsequent releases and to prevent recurrence, and includes a schedule for achieving conforrnance witn the limits. Special reports, as defined in 10 CFR 20.2203(a)(4), shall include:
- 1. An analysis that estimates the radiation exposure (dose) to a real individual from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes th: releases covered by the report.
- 2. A description of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
r
- 3. If the estimated dose exceeds the limits in 6.5.1, and if the release condition that violates 40 CFR 190 has not already been corrected, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the repost is considered a timely request, and a variance is granted until staff action on the request is complete.
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Or VIRGINIA.
VPAP-2103 POWER _
REVISION 6 i
PAGE 43 OF 156 i
t 6.6 -
Radiological Environmental Monitoring -
6.6.1 Monitoring Program
- a. Requirement i
- 1. The Radiological Environmental Monitoring Program shall be conducted as I
specified in Attachments 20 or 21, Radiological Environmental Monitoring i
Pmgram.
- 2. Samples shall be collected from specific locations specified in Attachment 22 or 23, Environmental Sample Locations. [ Commitment 3.2.2)
J
- 3. Samples shall be analyzed in accordance with:
- Attachment 20 or 21 requirements j
. Detection capabilities required by Attachment 24 or 25, Detection Capabilities for Environmental Sample Analysis
. Guidance of the Radiological Assessment Branch Technical Position on Environmental Monitoring dated November,1979, Revision No.1 l
- b. Action
{
- 1. If the Radiological Environmental Monitoring Program is not being conducted as required in 6.6.1.a., repon the situation in accordance with VPAP-2802,-
Notifications and Repons, by preparing and submitting to the NRC, in the Annual Radiological Environmental Operating Report required by Technical Specification (Surry Technical Specification 6.6.B.2 and North Anna Technical Specification 6.9.1.8), a description of the reasons for not conducting the program as required, and the plan for precluding recurrence.
- 2. If, when averaged over any calendar quarter, radioactivity exceeds the reponing levels of Attachment 26 or 27, Reporting Levels for Radioactivity Concentrations in Environmental Samples, prepare and submit to the NRC within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that:
i
. Identifies the causes for exceeding the limits, and Defines the corrective actions to be taken to reduce radioactive effluents so that the pol:ntial annual dose to a member of the public is less than the
)
calendar year limits of 6.2.3,6.3.3, and 6.3.4
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VIRGINIA VPAP-2103.
POWER REVISION 6 PAGE 44 OF l'56 J
When more than one of the radionuclides listed in Attachment 26 or 27 are detecteil in the sampling medium, the repon shall be submitted if:
)
concentration (1) concentration (2) reporting level (1) + reporting level (2) +.. 21.0 (25) 4
- 3. When radionuclides other than those listed in Attachments 26 and 27 are detected and are the result of plant effluents, the repon shall be submitted if the l
potential annual dose to a member of the public is equal to or greater than the calendar year limits of 6.2.3,6.3.3, and 6.3.4. The repon is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, repon and describe the condition in the Annual Radiological Environmental Operating Repon in accordance with VPAP-2802, Notifications and Repons.
t
- 4. If milk or fresh leafy vegetable samples are unavailable from one or more of the sample locations required by Attachment 20 or 21, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.The specific locations from which samples were unavailable may then be deleted from the monitoring program. Identify the cause of the unavailability of samples and identify the new locations for obtaining replacement samples in the next Annual Radioactive Effluent Release Repon in accordance with VPAP-2802, Notifications and Repons, include in the repon a revised figure and table for the ODCM to reflect the new locations.
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VPAP-2103 VIRGINIA _
's POWER REVISION 6 PAGE 45 OF 156
}-
6.6.2 Land Use Census
- a. Requirement.
A land use census shall be conducted and shallidentify within a distance of 8 km (5 miles) the location in each of the 16 meteorologi, cal sectors of the following:
. Nearest milk animal -
. Nearest residence 2
. Nearest garden greater than 50 m2 (500 ft ) that produces broad leaf vegetation
- 1. The land use census shall be conducted during the growing season, at least once per 12 months, using methods that will provide the best results (e.g., door-to-door survey, aerial survey, local agriculture authorities). Land use census results j
shall be included in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.
- 2. In lieu of the garden census, road leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted ground deposition (D/
I-
- Qs). Specifications for broad leaf vegetation sampling in Attachment 20 or 21 shall be followed, including analysis of control samples.
- b. Action
- 1. If a land use census identifies locations that yield a calculated dose or dose :
commitment greater than the values currently being calculated in 6.3.4.a.2, identify the new locations in the next Annual Radioactive Effluent Release i
Report in accordance with VPAP-2802, Notifications and Reports.
- 2. If a land use census identifies locations that yield a calculated dose or dose commitment (via the same exposure pathway) 20 percent (Surry) or 25 percent (North Anna) greater than at a location from which samples are currently being obtained, add the new locations to the Radiological Environmental Monitoring Program within 30 days. Sampling locations, excluding the control station location, that have the lowest calculated dose or dose cortunitments (via the same exposure pathway) may be deleted from the monitoring program. Identify new locations in the next Annual Radioactive Effluent Release Report and-include in the report revised figures and tables reflecting the new locations in accordance with VPAP-2802, Notifications and Reports. [ Commitment 3.2.4]
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' VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 46 OF 156 6.6.3 Interlaboratory Comparison Program -
)
' a. Requirement Radioactive materials (which contain nuclides produced at the Stations), supplied as part of an Interlaboratory Comparison Program that has been approved by the NRC, shall be analyzed.
- b. Action
- 1. Analyses shall be performed as part of the Environmental Pr'otection Agency's Environmental Radioactivity Laboratory Intercomparison Studies (Cross Check) Program and include:
Program Cross-Check of Milk 1133, Gamma, K, Srs9 and Sr*
131,H (Tritium),Sr89 3
Water Gross Beta, Gamma,1 and Sr* (blind-any combinations of above radionuclides)
. Air Filter
. Gross Beta, Gamma, Sr#
- 2. If analyses are not performed as required by 6.6.3.b., report in the Annual Radiological Environmental Operating Repor t in accordance with VPAP-2802, Notifications and Reports, the corrective actions taken to prevent recurrence.
9
' iVIRGINIA.
VPAP-2103 i
POWER
. REVISION 6 PAGE 47 OF 156 I
t
~ 6.63 Intertaboratory Comparison Program (continued) j
- c. Metho' ology and Results d
- 1. Methodology and results of the cross-check program shall be maintained in the l
contractor-supplied Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual, IWL-0032-361.
j
- 2. Results shall be reported in the Annual Radiological Environmental Monitoring -
l Repon in accordance with VPAP-2802, Notifications and Reports.
6.7 Reporting Requirements 6.7.1 Annual Radiological Environmental Operating Report.
{
Routine Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year.
l A single submittal may be made for the Station. Radiological Environmental.-
Operating Repons shallinclude.
- a. Summaries, interpretations, and analysis of trends of results of' radiological i
environmental surveillan' e activities for the repon period, including:
c
. A comparison (as appropriate) with preoperational studies, operational controls, l
and previous environmental surveillance reports
. An assessment of the observed impacts of the plant operation on the environment
. Results of land use census per 6.6.2
[
- b. Results of analysis of radiological environmental samples and of environmental radiation measurements taken per 6.6.1, Monitoring Program. Results shall be summarized and tabulated in the format of the table in the Radiological Assessment '
l Branch Technical Position on Environmental Monitoring.
i
- 1. If some individual results are not available for inclusion with the repon, the repon shall be submitted, noting and explaining reasons for missing results.
- 2. Missing data shall be submitted in a supplementary repon as soon as possible.
i i
- c. A summary description of the radiological environmental monitoring program..
t
- d. At least two legible maps covering sampling locations,' keyed to a table giving,
distances and directions from the centerline of one reactor. One map shall cover stations near the site boundary; a'second shall include more distant stations.
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' VIRGINIA
'VPAP-2103 POWER REVISION 6
. PAGE 48 OF 156
- e. Results of Station panicipation in the Interlaboratory Comparison Program, per 6.6.3.
- f. Discussion of deviations from the Station's environmental sampling schedule per l 0 or 21.
j
- g. Discussion of analyses in which the lower limit of detection (LLD) required by 4 or'25 was not achievable.
l 6.7.2 Annual Radioactive Emuent Release Report
- a. Requirement Radioactive Effluent Release Reports covering operation of the units during the previous 12 months of operation shall be submitted before May 1 of each year. A l
single submittal may be made for the Station and should combine those sections that are common to both units. Radioactive Effluent Release Repons shall include:
- 1. A summary of quantities of radioactive liquid and gaseous effluents and solid waste releard. Data shall be summarized on a quanerly basis following the format of Regulatory Guide 1.21, Appendix B.
- 2. An assessment of radiation doses to the maximum exposed members of the public due to the radioactive liquid and gaseous effluents released from the Station during the pavious calendar year. This assessment shall be in accordance with 6.7.2.b.
I
- 3. A list and description t f unplanned releases from the site to unrestricted areas, during the reponing period, which meet the following criteria:
Unplanned releases that exceeded the limits in 6.2.1 and 6.3.1 l
. Unplanned releases which require a Deviation Repon and involve the -
discharge of contents of the wrong Waste Gas Decay Tank or the wrong liquid l
radwaste release tank
. Unplanned releases from large leaks due to unexpected valve or pipe failures
(
that result in s quantity of release such that a 10 CFR 50.72, immediate '
Notification Requirements for Operating Nuclear Power Reactors or 10 CFR 50.73, Licensee Event Repon System, repon is required
+
+ Unplanned releases as determined by Radiation Protection Supervision, which may or may not require a Deviation Repon
- ~. - - _
w VIRGINIA.
VPAP-2103 POWER -
REVISION 6 PAGE 49 OF 156 6.7.2 Annual Radioactive Emuent Release Report (continued)
- 4. Ma'jor changes to radioactive liquid, gaseous, and solid waste treatment systems '
i during the reporting period.
' 5. Changes to VPAP-2103, Offsite Dose Calculation Manual (see 6.7.4).
o
- 6. A listing of new locations for dose calculations or environmental monitoring l
identified by the land use census (see 6.6.2).
- b. Dose Assessment
- 1. Radiation dose to individuals due to radioactive liquid and gaseous effluents from the Station during the previous calendar year shall either be calculated in 1
accordance with this procedure or in accordance with Regulatory Guide 1.109.
Population doses 'shall not be included in dose assessments.
- 2. The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station shall be incorporated with the dose.
+
assessment performed above. If the dose to the maximum exposed member of the public exceeds twice the limits of 6.2.3.a.1,6.2.3.a.2,6.3.3.a.1, or 6.3.4.a.1, the dose assessment shall include the contribution from direct radiation.
NOTE: NUREG-0543 states:"There is reasonable assurance that sites with up to four operating reactors that have releases within Appendix 1 design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard,40 CFR Part 190."
i
- 3. Meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used to determine
[
gaseous pathway doses.
6.7.3 Annual Meteorological Data
- a. Meteorological data collected during the previous year shall be in the form ofjoint frequency distributions of wind speed, wind direction, r :1 atmospheric stability.
- b. Meteorological data shall be retained in a file on site and shall be made available to l
NRC upon request.
6 D
'. VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 50 OF 156 6.7.4 Changes to the ODCM I
Changes to the ODCM shall be:
- a. _ Reviewed and approved by SNSOC and the Station Manager before implementation.
- b. Documented. Records of reviews shall be retained as Station records.
Documentation shallinclude:
- l. - Sufficient information to suppon changes, together with appropriate analyses or
. evaluationsjustifying changes.
- 2. A determination that a change will not adversely impact the accuracy or
' reliability of effluent doses or setpoint calculations, and will maintain the level of radioactive effluent control required by:
10 CFR 20 Subpan D 40 CFR 190 10 CFR 50.36a 10 CFR 50, Appendix 1
- c. Submitted to NRC in the form of a complete, legible copy of the entire ODCM as a pan of, or concurrent with the Annual Radioactive Effluent Release Repon for the period of the repon in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
l
- d. Submitted to the Management Safety Review Committee (MSRC) Coordinator.
[ Commitment 3.2.1]
- e. Submitted to NRC in accordance with VPAP-2802, Notifications and Repons.
VIRGINIA VPAP-2103 POWER-
. ' REVISION 6 q
PAGE 51 OF 156 -
l l
2 7.0 -
RECORDS r
7.1 The following individual and packaged documents and copies of any related correspondence i
completed as a result of the performance or implemen'tation of this procedure are records. They shall be submitted to Records Management in accordance with VPAP-1701 Records Management. Prior to transmittal to Records Management, the sender shall assure that:
. &ch record is packaged when applicable,
. QA program requirements have been fulfilled for' Quality Assurance records,
. Each record is legible, completely filled out, and adequately identifiable to the item or activity involved,
. Each record is stamped, initialed, signed, or otherwise authenticated an'd dated, as required by this procedure.
71.1 Individual Records
. None j
7.1.2 Record Packages I
. Records of changes to the ODCM in accordance with 6.7.4
. Records of meteorological data in accordance with 6.7.3 l
. Records of sampling and analyses f
. Records of radioactive materials and other effluents released to the environment
. Records of preventive maintenance, surveillances, and calibrations i
7.2 The following documents completed as a result of the implementation of this procedure are not records and are not required to be transmitted to Records Management.
None i
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? VIRGINIA VPAP-2103.
POWER REVISION 6 i
PAGE 53 OF 156 f
' A'ITACHMENT I
' (Page 1 of 1) l 1
Surry Radioactive Liquid Emuent Monitoring Instrumentation
)
Instrument Minimum -
Action i
Operable Channels
- i. GROSS RADIOACTIVITY MONTIORS PROVIDING ALARM
[
' AND AUTOMATIC"IERMINATION OF RELEASE (a) Radwaste Facility Liquid Emuent Line I
~
RM-RRM 131
}
}
2.
GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC
'IERMINATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1-SW.RM-120 2
2 Unit 2: 2 SW-RM-220 (b) Component Cooling Service Water Emuent Line l-SW-RM-107A-4 2
1-SW RM-107B i
f 1-SW RM 107C 1 SW RM-107D 3.
FLOW RATE MEASUREMENT DEVICES Radwaste Facility Liquid Effluent Line Instrument Loop RLW-153 1
3
- ACTION 1:
If the number of operable channels is less than required, effluent releases shall be suspended.
ACTION 2:
If the number of operable channels is less than required, effluent releases via.this -
pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal g'amma emitters, as defined in Attachment 8 Surry _
Radioactive Liquid Waste Sampling and Analysis Program.
ACTION 3:
If the number of operable channels is less than required, effluent releases via this pathway shall be suspended.
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VIRGINIA VPAP-2103 i
POWER REVISION 6 PAGE 54 OF 156 i
Intentionally Blank i
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VIRGINIA VPAP-2103 POWER -
REVISION 6 PAGE 55 OF 156 ATTACHMENT 2 (Page 1 of 2)
North Anna Radioactive Liquid Emuent Monitoring Instrumentation Minimum Instrument Operable Action Channels 1.
Liquid Radwaste Emuent (a) 1 RM-LW 111, Liquid Radwaste Effluent Monitor 1
1 (b) 1-LW-FT-104. Liquid Radwaste Emuent Total Flow Measuring 1
2 Device (c) 1 LW SOV-121, Clarifier Emuent Line Continuous Composite
}
}
Sampler and Sampler Flow Monitor (d) 1-LW-TK 20. Liquid Waste Emuent Sample Vessel 1
1 (e) 1 LW-1130 Liquid Waste Emuent Pmportional Sample Valve 1
1 (f) 1-RM-SW-108, Service Water Emuent Monitor 1
1 (g) 1 RM-SW-130, Unit 1 Circulating Water System Emuent Line
}
'4 Monitor (h) 2-RM-SW-230, Unit 2 Circulating Water System'Emuent Line 3
4 Monitor 2.
Tank Level Indicating Devices (Note 1)
(a) RefuelingWaterStorageTanks Unit I l-QS-LT-100A 1
3 1-QS-LT-100B l-QS LT 100C 1-QS-LT 100D Unit 2 2-QS-LT-200A 1
3 2-OS-LT-200B 2-QS-LT-200C 2-QS LT-200D (b) Casing Cooling Storage Tanks Unit 1 I-RS-LT-103A 1
3 1-RS-LT-103B Unit 2 2 RS-LT-203A 1
3 2-RS-LT-203B (c) PG Water Storage Tanks (Note 2) 1 BR LT-116A (1-PG-TK 1A) 1
,3 1 BR-LT-il6B (1-PG-TK-1B) 1 3
(d) Boron Recovery Test Tanks (Note 2) 1-BR-LT-112A (1-BR-TK-2A) 1 3
1-BR-LT-112B (1-BR TK-2B) 1 3
l VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 56 OF 156 NITACHMENT 2 l
(Page 2 of 2)
North Anna Radioactive Liquid Emuent Monitoring Instrumentation ACTION 1:
If the number of operable channels is less than required, effiuent releases via this pathway may continue if, at least once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta and gamma) at an LLD of at least 1x10-7 pCi/g or an isotopic radioactivity at an LLD of at least 5x10-7 pCi/g.
ACTION 2:
If the number of operable channels is less than required, effluent releases via this pathway may continue if the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Design capacity performance curves generated in situ may be used to estimate flow.
ACTION 3:
If the number of operable channels is less than required, liquid additions to this tank may continue if the tank liquid level is estimated during allliquid additions to the tank.
ACTION 4:
If the number of operable channels is less than required, make repairs as soon as possible. Grab samples cannot be obtained via this pathway.
NOTE 1: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents, and do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.
NOTE 2: This is a shared system between Unit 1 and Unit 2.
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A'ITACHMENT 3 i
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Surry Radioactive Liquid Emuent Monitoring Instrumentation Surveillance Requirements l
Channel Description Channel Source Channel Channel Check Check Calibration Functional Test -
1.
GROSS RADIOACTIVITY MONITORS
. PROVIDING ALARM AND AUTOMATIC
'IERMINATION OF RELEASE (a) Radwaste Facility Liquid Efnuent Line RM-RRM 131 D
P R'
Q 2.
GROSS BETA OR GAMMA RADIOACTIV-ITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AIJTOMATIC TERMI.
NA* DON OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1 SW-RM-120 D
M R
Q Unit 2: 2-SW RM-220 (b) Component Cooling Service Water Efflu.
-j ent Line l-SW-RM-107A D
M R
Q 1-SW.RM-107B l SW-RM-107C 1-SW-RM-107D 3.
FLOW RATE MEASUREhENT DEVICES Radwaste Facility Liquid Effluent Line Instrument Loop RLW-153 DR N/A R
N/A l
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i ATTACHMENT 4 (Page 1 of 2) 1 North Anna Radioactive Liquid Emuent Monitoring Instrumentation Surveillance Requirements Channel Description Channel Source Channel Channel Check Check Calibration Functional Test 1.
Liquid Radwaste Emuent (a) 1 RM-LW.lll,LiquidRadwasteEffluent D
D R
Q (NOTE l)
Monitor (b) 1-LW FT 104, Liquid Radwaste Effluent D (NOTE 3)
N/A R
Q TotalFlow Measuring Device (c) 1 LW-SOV-121, Clarifier Effluent Line N/A N/A R
N/A Continuous Composite Sampler and Sampler Flow Monitor (d) 1-LW-TK 20, Liquid Waste Effluent D(NOTE 9)
N/A N/A N/A Sample Vessel (e) 1-LW-ll30, Liquid Waste Effluent D(NOTE 9)
N/A N/A N/A Proportional Sample Valve (f) 1 RM-SW-108, Service Water System D
M R
Q (NOTE 2)
Effluent Monitor (g) 1 RM-SW-130, Unit I Circulating Water D
M R
Q (NOTE 2)
System Effluent Line Monitor (h) 2 RM-SW-230. Unit 2 Circulating Water D
M R
Q (NOTE 2) j System Effluent Line Monitor 2.
Tank Level Indicating Device 4
(NOTE 6)
[
(a) Refueling Water Stomge Tanks Unit I l-QS-LT 100A D (NOTE 4)
N/A R
Q (NOTE 7) i 1-QS LT-100B l-QS-LT 100C l-QS-LT 100D 1
Unit 2 2-QS LT-200A D (NOTE 4)
N/A R
Q (NOTE 7) 2-QS-LT-200B 2-QS-LT-200C 2-QS-LT-200D (b) Casing Cooling Storage Tanks i
Unit I l RS-LT-103A D (NOTE 4) t./A R
Q(NOTE 7) i 1 RS-LT 103B Unit 2 2 RS-LT 203A D (NOTE 4)
N/A R
Q(NOTE 7) 2-RS-LT 203B (c) PG Water Storage Tanks (NOTE 5) 1 BR-LT 116A (1-PG TK 1A)
D (NOTE 4)
N/A R
Q(NOTE 8) 1-BR.LT ll6B (1 PG-TK 1B)
D (NOTE 4)
N/A R
Q (NOTE 8) '
(d) Boron Recovery Test Tanks (NOTE 5) 1-BR-LT il2A (1 BR-TK-2A)
D (NOTE 4)
N/A R
Q (NOTE 8) 1-BR-LT-112B (1-BR TK-2B)
D (NOTE 4)
N/A R
Q(NOTE 8)
f VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 60 OF 156 ATTACHMENT 4 (Page 2 of 2)
North Anna Radioactive Liquid Emuent Monitoring Ihstrumentation Surveillance Requirements NOTE 1: The Channel Functional Test shall demonstrate:
- a. Automatic isolation of this pathway and Control Room alarm annunciation occurif the instrument indicates measured levels above alarm / trip setpoint.
i
- b. Alarm annunciation occurs if the instrument controls are not set in " operate" mode.
NOTE 2: The Channel Functional Test shall demonstrate that Control Room alarm iuu:unciation occur if any of the following conditions exists:
a.
Instrument indicates measured levels above the alarm / trip setpoint.
- b. Instrument controls not set in " operate" mode.
NOTE 3: Channel Check shall consist of verifying indication of flow during periods of release.
Channel Check shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
NOTE 4: During liquid additions to the tank, verify indication oflevel change.
NOTE 5: This is a shared system between Unit I and Unit 2.
NOTE 6: Tanks included in this requirement are those outdoor tanks that are not' surrounded by liners, dikes, or walls capable of holding the tank contents and do not have overflows and sunounding area drains connected to the liquid radwaste treatment system.
NOTE 7: The Channel Functional Test shall demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur if instrument indicates' measured levels outside the i
alarm / trip setpoint. Demonstration of automatic isolation may consist of verifying the appropriate signal is generated. Valves need not be operated for this test.
NOTE 8: The Channel Functional Test shall demonstrate that Control Room alarm annunciation l
occurs if the instrument indicates measured levels are outside alarm setpoint.
NOTE 9: Channel Check shall consist of verifying that proportional flow exceeds 0.5 mis / gallon.
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VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 61 OF 156 ATTACHMENT 5 (Page1of1)
Liquid Ingestion Pathway Dose Factors for Surry Station Units I and 2 Total Body Ai Thyroid Ai Gl.LLI Radionuclide mrem /hr mrem /hr mrem /hr uCi/mi pCi/mi nCi/mi H-3 2.82E-01 2.82E-01 2.82E 01 Na-24 4.57E-01 4.57E-01 4.57E-01 Cr-51 5.58E+00 3.34E-01 1.40E+03 2.16E+04 Mn-54 1.35E+03 2.03EKM Fe-55 8.23E+03 6.32E+05 Fe-59 7.27E+04 1.22EdM Co-58 1.35E+03 3.25E+(M Co-60 3.82E+03 3.23E+05 Zn-65 2.32E+05 1.23E+02 Rb-86 2.91E+02 8.00E+02
~
Sr-89 1.43E+02 3.55E+03 Sr-90 3.01E+04 4.89EMM Y-91 2.37E+00 1.62EM M Zr-95 3.46E+00 Zr-9'l 8.13E-02 5.51E4M 1.51E+06 Nt> 95 1.34EK)2 2.%E+02 Mo-99 2.43E+0!
4 Ru-103 4.60E4)1 1.25E+04 1.03E+05 Ru-106 2.01E+02 5.97E+05 Ag-110m 8.60E+02 Sb-124 1.09E+02 6.70E-01 7.84 E+03 Sb 125 4.20E+01 1.79E-01 1.94E+03 Te-125m 2.91E+01 6.52E+01 8.66E+02 Te 127m 6.68E+4? s 1.40E+02 1.84E+03 Te-129m 1.47E+02 3.20EM)2 4.69E+03 Te-13Im 5.71E+01 1.08E+02 6.80E+03 Te-132 1.24E+02 1.46E+02 6.24E+03 l131 1.79E+02 1.02E+05 8.23E+01 1 132 9.%E+00 9.%E+02 5.35E+00 1133 3.95E+01 1.90Ed4 1.16E+02 1 134 5.40E+00 2.62E+02 1.32E-02 l135 2.24E+01 4.01E+03 6.87E+01 2.85E4)2 Cs-134 1.33E+04 3.21E+02 Cs-136 2.04E+03 2.32E+02 Cs 137 7.85E+03 5.12E-05 Cs-138 5.94E+00 3.38E403 Ba-140 1.08E+02 5.83E+04 1 a-140 2.10E-01 U 2 +03 Cc-141 2.63E-01 1.67E+04 Cc 143 4.94E-02 6.04E+(M 1
Cc 144 9.59E+00 7.1 IE+0' Np-239 1.91E-03 i
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ATTACHMENT 6 (Page 1 of 5)
North Anna Liquid Ingestion Pathway Dose Factor Calculation Units I and 2 1.0 Equation (6)
D = t F[f;C;A; (6-1) i-where:
D = cumulative dose commitment to the total body or critical organ, from the liquid effluents f
for the period t,in mrem
= period for which C; and F are averaged for all liquid releases, in hours t
= the near field avcage dilution factor for C during any liquid effluent release. Defined as F
i the ratio of the average undiluted liquid waste flow during' release to the average flow from the Station discharge structure to unrestricted areas fi = the individual dilution multiplication factor to account for increases in concentration cf long-lived nuclides due to recirculation, listed on page 5 of this attachment. "fi"is the l
ratio of the total dilution flow over the effective dilution flow C; = average concentration of radionuclide i, in undiluted liquid effluent during the period t, from any liquid releases,in pCi/ml A = the site-related ingestion dose commitment factor to the total body or critical organ of an i
adult for each identified principal gamma and beta emitter listed on page 5 of this l
attachment,in mrem /hr per pCi/mi A; = 1.14 E+05 (730/Dw+ 21 BF;/D,) DF; (6-2) where:
1.14 E405 = (1 E46 pCi/ Ci x 1 E+03 ml/kg)/8760 hr/yr, units conversion factor adult water consumption, kg/yr, from NUREG-0133 730
=
I f
' VPAP-2103 POWER REVISION 6 PAGE 64 OF 156
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A'ITACHMENT 6 l
(Page 2 of 5)
-i North Anna Liquid Ingestion Pathway Dose Factor Calculation I
Units 1 and 2 l
.Dw dilution' factor from the near field area within one-quaner mile of the f
=
release point to the potable water intake for the adult water consumption.
~
D, includes the dilution contributions from the Lake Anna Dam to Doswell(0.73),theWHTF(C JC ),and1.ake Anna (C /C ).Thepotable
{
t C R L water mixing ratio is calculated as:
1/(C /C )(C /C ) x 0.73 =' C /(C x 0.73 )
t C
R g
C R
(6-3) where C, C and C are the respective concentrations for the considered C L R
nuclide in the discharge channel, WHTF (Lagoon) and the Lake.
Calculation is per expressions 11.2-5,11.2-6, and 11.2-8 of the North Anna UFSAR
/
21 adult fish consumption rate, kg/yr, from NUREG 0133 l
{
=
BFi the bioaccumulation factor for nuclide i, in fish, pCi/kg per pCi/1. from l
=
Table A-1 of Regulatory Guide 1.109, Rev.1
[
Da dilution factor for the fish pathway, calculated as 1/(CL /Cc) where CL f
=
and Cc are the concentrations for the considered nuclide in the discharge channel and the WHTF (Lagoon). Calculation is per Expressions 11.2-5, j
and 11.2-6 of North Anna's UFSAR l
DFi
=
the critical organ dose conversion factor for nuclide i, for adults, in mrem /
l pCi, from Table E-11 of Regulatory Guide 1.109, Rev.1 1
2 i
l i
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VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 65 OF 156 ATTACHMENT 6 (Page 3 of 5)
North Anna Liquid Ingestion Pathway Dose Factor Calculation l
Units 1 and 2 i
2.0 Equation (9)
Equation (6) is simplified for actual dose calculations by introducing:
WASTE FLOW.
WASTE FLOW (6-4)
~
F = CIRC. (WATER) FLOW + WASTE FLOW -CIRC. FLOW l
and i
CIRC. FLOW (6-5) i
- f.. =
EFFECTIVE DIL. FLOW.
1 1
Effective dilution flow rates for individual nuclides "i" are listed on Attachment 7. Nort Liquid Pathway Dose Commitment Factors for Adults. Then the total released activity (Qi) the considered period and the ith nuclide is written as:
Q; = t x C; x WASTE FLOW (6-6) and Equation (6) reduces to:
3 A'.
D=[Q (6-7) iEFF. DIL. FLOW.
3 1
For the long lived, dose controlling nuclides, the effective dilution flow is essentially the over (dam) flow rate out of the Lake Anna system (i.e., the liquid pathway dose is practically independent from the circulating water flow rate. However, to accurately assess long range average effects of reduced circulating water flow rates during outages or periods of low lake water temperatures, calculations are based on an average of 7 out of 8 circulating water pumps running at 218,000 gpm = 485.6 cft/sec per pump.
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VIRGINIA POWER VPAP-2103 REVISION 6 PAGE 66 OF 156 ATTACHMENT 6 -
(Page 4 of 5) i North Anna Liquid Ingestion Pathway Dose Factor Calculation Units 1 and 2 i
NOTE: De 218,000 gpm flow rate per Circulating Waterpump is based on Reference 3.1.21.
De choice of seven Circulating Water pumps is considered realistic. Compared to.
this, the NAPS UFSAR, Chapter 11.2 (Referenc,e 3.1.18), contains an extremely conservative consideration based on the minimum flow in accordance with Reference 3.1.21 with only two Circulating Water pumps operating. Even at such a l
low flow rate, which cannot be sustained during power generation, liquid pathway effluent dose factors increase only slightly for the dose controlling nuclides (i.e., Cs
- 19 percent, Csl37 15 percent).
By defining Bj = A / EFF. DIL. FLOW, the dose calculation is reduced to a two factor l
i formula:
D = {Q; x B; (6-8) r i
Values for B (mrem /Ci) and EFF. DIL. FLOW are listed in Attachment 7.
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VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 67 OF 156 ATTACIIMENT 6 (Page 5 of 5)
North Anna Liquid Ingestion Pathway Dose Factor Calculation Units I and 2 Liver Bi Individual Dilution Total Body Bi Radionuclide Multiplication Factor mrem /hr mrem /hr (f) pCi/mi pCi/ml i
H-3 14.9 6.18E+00 6.18E+00 t
Na.24 1.0 3.71E+01 3.71E41 Cr-51 1.7 1.10E+00 Mn54 7.0 8.62E+02 4.52E+03 Fe-55 113 130E+02 5.56E+02 Fe-59 2.2 9.47E+02 2.47E+03 Co-58 2.8 2.49E+02 1.llE+02 Co-60 13 3 8.27E+02 3.75E+02 Zn-65 6.1 3.28E+04 7.25E+04 Kb.86 1.5 3.53E+04 7.59E+04 Sr-89 2.3 8.70E+02 Sr90 15.8 239E+05 Y-91 2.5 3.42E-01 Zr-95 2.7 2.98E-01 4.41E-01 Zr-97 1.0 1.50E-04 3.27E-04 N b.95 1.9 1.13E+02 2.10E+02 Mo.99 1.0 7.48E+00 3.93E+01 Ru-103 2.0 4.10E+00 Ru-106 7.6 2.65E+01 Ag llom 6.2 4.94E+00 8.32E+00 Sb-124 2.6 4.37E+01 2.08E+00 Sb 125 11.4 2.46E+01 1.16E+00 Te 125m 2.5 3.23E+02 8.73E+02 Te.127m 3.7 7.82E+02 2.29E+03 Te-129m 1.9 1.52E+03 3.58E+03 Te.131m 1.0 1.12E+02 1.35E+02 Te-132 1.0 5.04E+02 5.37E+02 1 131 1.2 9.66E+01 1.69E+02 1-132 1.0 1.03E-01 2.95E-01 1-133 1.0 3.47E+00 1.14E+01 1-134 1.0 2.15E-02 6.00E-02 1135 1.0 6.5SE-01 1.78E+00 Cs 134 103 5.80E+05 7.09E+05 Cs 136 13 6.01E+04 835E+04 Cs 137 15.8 3.45E+05 5.26E+05 Cs-138 1.0 9.18E-01 1.85E40 Ba.140 13 2.65E+01 5.08E-01 La-140 1.0 4.47E-03 1.69E-02 Cc-141 1.8 2.14E-02 1.89E-01 Cc-143 1.0 135E-04 1.22E+00 Ce.144 6.6 1.41E+00 1.10E+01 Np.239 1.0 5.13E-04 931E-04
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VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 69 OF 156 ATTACIIMENT 7 (Page1of1)
North Anna Liquid Pathway Dose Commitment Factors for. Adults B = A F / CIRC FLOW = (A / Effective Dilution Flowi) X 9.81E-3 hr ft3 pCi / sec ml Ci i
i i
Liver Bi Effective Dilution Flow Total Body Bi Radionuclide (cft/sec)
(mrem /Ci)
(mrem /Ci)
H-3 2.28E+02 2.66E-04 2.66E-04 Na-24 339E+03 1.07E-04 1.07E44 Cr 51 1.99E+03 5.44E-06 N/A Mn-54 4.88E402 1.73E-02 9.065-02 Fe 55 3.01E+02 4.23E-03 1.81E-02 Fe-59 l57E+03 5.93E-03 1.55E-02 Co-58 1.20E+03 2.04E-03 9.10E-04 Co-60 2.55E+02 3.18E-02 1.44E-02 Z n-65 5.60E+02 5.745-01 1.27E+00 Rb-86 234E+03 1.485-01 3.18E-01 Sr-89 1.46E+03 5A4E-03 N/A Sr-90 2.16E+02 1.09E+01 N/A Y-91 134E+03 2.50E-06 N/A b-95 1.27E+03 230E-06 3.40E-06 b.97 339E+03 4.33E-10 9.46E-10 Nb-95 1.78E+03 6.24E44 1.16E-03 Mo-99 330E+03 2.22E-05 1.17E-04 Ru-103 1.68E+03 2.40E-05 N/A Ru-106 4.48E+02 5.80E-04 N/A Ag 110m 5.52E+02 8.78E-05 1.48E-04 Sb.124 132E+03 3.2SE-04 1.55E-05 Sb.125 2.98E+02 8.10E-04 3 AGE-05 Te-125m 1.35E+03 235E-03 635E-03 Te-127m 9.16E+02 837E-03 2.46E-02 Te-129m 1.82E+03 8.19E-03 1.93E-02 Te-131m 338E+03 3.27E-04 3.92E-04 Te-132 3.27E+03 1.51E-03 1.61E-03 1 131 2.94E+03 3.22E-04 5.62E-04 1132 3.40E+03 2.98E-07 8.51E-07 l-133 339E+03 1.00E-05 3.29E-05 1 134 3.40E+03 6.19E-08 1.73E-07 1135 3.40E+03 1.90E-06 5.15E-06 Cs-134 3.29E+02 1.73E+01 2.11E+01 Cs-136 2.62E+03 2.25E-01 3.12E-01 Cs 137 2.15E+02 1.57E+01 2.40E+01 Cs-138 3.40E+03 2.65E-06 534E-06 fia-140 2.65E+03 9.83E-05 1.88E-06 La 140 336E+03 131E-08 4.94E-08 Ce-141 1.85E+03 1.14E-07 1.00E-06 Ce 143 337E+03 3.93E-10 3.55E-06 Ce-144 5.14E+02 2.70E-05 2.10E-04 Np-239 3.32E+03 1.51E-09 2.75E-09
VIRGINIA OMR VPAP-2103 REVISION 6 PAGE 70 OF 156
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VPAP-2103 -
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_P/> GE 71 OF 156 REVISION 6 -
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- ATTACHMENT 8
-(Page 1 of 3)
Surry Radioactive Liquid Waste Sampling and Analysis Program
(
}
Liquid Release Sampling Minimum Analy-Typeof Activity n
LD)
Type Frequency _
sis Frequency Analysis
( Ci/ml). (Note 1)
Principle Gamma 5 x 10'7 p
p Emitters (Note 3)
(Each Batch)
(Each Batch) 1131 1 x 10-6 Dissolved and 1 x 10-5 M
Entrained Gases Batch Releases e BaM)
(Gamma Enu,tters)
(Note 2)
P M Composite H3 1 x 10-5 l
1 x 10'7 (Each Batch)
(Note 4)
Gross Alpha 89 and Sr#
5 x 10-8 l
P Q Composite Sr 55 1 x 10-6 (Each Batch)
(Note 4)
Fe caG 5 x 10'7 Continuous W Composite
,N 131 1 x 10-6 j
(Note 6)
(Note 6) 1 Dissolved and 1 x 10-5,
Continuous M
M Entrained Gases Releases Grab Sample (Gamma Emitters) 3 1 x 10-5 l
(Note 5)
Continuous M Composite H
1 x 10 7 (Note 6)
(Note 6)
Gross Alpha 89 and Sr#
5 x 10-8 Continuous Q Composi-Sr 55 1 x 10 6 (Note 6)
(Note 6)
Fe I
m
.,y
+
M
VIRGINIA -
POWER VPAP-2103 REVISION 6 PAGE 72 OF 156
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ATTACHMENT 8 i
(Page 2 of 3)
Surry Radioactive Liquid Waste Sampling and Analysis Program f
NOTE 1: For a particular measurement system (which may include radiochemical separation) 4.66 s LLD =
b (g,3)
E V e 2.22E+06 Y
- e-(Aat)
Where:
LLD the "a priori" (before the fact) Lower Limit of Detection (as microcuries
=
per unit mass or volume)(see 4.8) the standard deviation of the background counting rate or of the counting sb
=
rate of a blank sample as appropriate (as counts per minute, cpm)
E the counting efficiency (as counts per disintegration)
=
V the sample size (in units of mass or volurne)
=
2.22E+06 =
the number of disintegrations per minute (dpm) per microcurie Y
the fractional radiochemical yield (when applicable)
=
A the radioactive decay constant for the particular radionuclide
=
At the elapsed time between the midpoint of sample collection and time of
=
counting Typical values of E, V, Y and At should be used in the calculation.
The LLD is an "a priori"(before the fact) limit representing the capability of a measurement system and not a "posteriori"(after the fact) limit for a particular measurement.
NOTE 2: A batch release is the discharge ofliquid wastes of a discrete volume. Before samp analyses, each batch shall be isolated, and appropriate methods will be used to obtain a representative sample for analysis.
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 73 OF 156 ATTACHMENT 8 (Page 3 of 3)
Surry Radioactive Liquid Waste Sampling and Analysis Program NOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are the 65, Mo, Cs ?d,Csl37. Celd', and 99 l
54 59 60 following radionuclides: Mn, Fe, Coss, Co, Zn
. This list does not mean that only these nuclides are to be detected and reported.
ld4 Ce Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.
NOTE 4: A composite sample is one in which the quantity of liquid sampled is proportional to the quantity ofliquid waste discharged and for which the method of sampling employed re in a specimen that is representative of the liquids released.
A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from NOTE 5:
a volume of a system that has an input flow durinh -.e continuous release.
NOTE 6: To be representative of the quantities and concentrations of radioactive materials in liquid effluents, composite sampling shall employ appropriate methods which will result in a specimen representative of the effluent release.
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VPAP 2103
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North Anna Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sampling Minimum Analy-Type of Activity Lower Limit of Type Frequency sis Frequency -
Analysis Detection (LLD)
(pCi/ml),(Note 1)
P P
Principle Gamma 5 x 10-7 Emitters (Note 3) 131 1 x 10-6 (Each Batch)
(Each Batch) 3 Batch Releases P
M Dissolved and 1 x 10 5 Entrained Gases (One Batch /M)
(Gamma Emitters)
(Notes 2 and 7)
P M Composite H3 1 x 10 (Each Batch)
(Note 4)
Gross Alpha 1 x 10-7 89 and Sr*
5 x 10-8 P
Q Composite Sr (Each Batch)
(Note 4) p,55 1 x 10-6 Pnncipal Gamma 5 x 10-7 Emitters (Note 6) 131 1 x 10-6 Continuous W Composite 3
Dissolved and Continuous (Note 6)
(Note 6) 1 x 10-5 Entrained Gases Releases (Gamma Emitters) 3 1 x 10-5 (Note 5)
Continuous M Composite H
(Note 6)
(Note 6)
Gross Alpha 1 x 10-7 89 and Sr*
5 x 10-8 Continuous Q Composite Sr 55 1 x 10-6 (Note 6)
(Note 6) pe
p VIRGINIA POWER VPAP-2103 REVISION 6 PAGE 76 0F 156 ATTACHMENT 9 (Page 2 of 3)
North Anna Radioactive Liquid Waste Sampling'and Analysis Program NOTE 1: For a particular neasurement system (which may melude radiochemical separa 4.66 s LLD =
b E
- V = 2.22E+06
- Y
- e-(AAt)
Where:
LLD the "a priori" (before the fact) Lower Limit of Detection as defined above
=
(as microcuries per unit mass or volume) (see 4.8) the standard deviation of the background counting rate or of the co sb
=
rate of a blank sample as appropriate (as counts per minute, cpm)
E the counting efficiency (as. counts per disintegration)
=
V the sample size (in units of mass or volume)
=
2.22E+06 =
the number of disintegrations per minute (dpm) per microcurie Y
the fractional radiochemical yield (when applicable)
=
A the radioactive decay constant for the particular radionuclide
=
At the elapsed time between the midpoint of sample collection and time of
=
counting Typical values of E, V, Y and At should be used in the calculation.
The LLD is an "a priori"(before the fact) limit representing the capability of a measurement system and not a "posteriori"(after the fact) limit for a particular measurement.
NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Befor analyses, each batch shall be isolated, and then thoroughly mixed as the situ to assure representative sampling.
4
VPAP-2103 VIRGINIA PIVISION 6 POWER PAGE 77 OF 156 ATTACHMENT 9 (Page 3 of 3)
North Anna Radioactive Liquid Waste Sampling and Analysis Program t
The principal gamma emitters for which the LLD specification applies exclusively are th NOTE 3:
, CoS8, Co, Zn65, Mo, Cs
, Cs137 CeI4I 60 99 l34
,and following radionuclides: Mn54 pe59 l44. This list does not mean that only these nuclides are to be detected and reponed.
Ce Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.
A composite sample is one in which the quantity of liquid sanipled is proportional to the NOTE 4:
quantity ofliquid waste discharged and for which the method of sampling employed re in a specimen that is representative of the liquids released.
A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from NOTE 5:
a volume of a system that has an input flow during the continuous release.
To be representative of the quantities and concentrations of radioactive materials in NOTE 6:
effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent releases.
Whenever the secondary coolant activity exceeds 10-5 Ci/ml, the turbine building sump NOTE 7:
pumps shall be placed in manual operation and samples shall be taken and analy to release. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- VIRGINIA POWER VPAP-2103 REVISION 6 PAGE 78 OF 156 c
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ATTACHMENT 10 (Page 1 of 5)
Surry Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sampling Minimum Type of Activity Lower Limit of Type Frequency Analysis Analysis Detection (LLD)
(pCi/ml). (Note 1)
Frequency l
'I
- I***
Prior to Release PrincipalGamma 4
1 x 10 A. Waste Gas
)
(Each Tank)
Emitters (Note 2)
Storage Tank 3
,)
Principle Gamma 1 x 10d Prior to Release Prior to Release Emitters (Note 2) l B. Containment
(
h RGE)
(Each PURGE)
H 1 x 10-6 3
Purge Ga
)
Principle Gamma 4
l
)
C. Ventilation Weekly W*ektY Emitters (Note 2) 1 x 10 (1) Process Vent (Grab Sample)
(2) Vent Vent #1 3
1 x 10-6 (3) Vent Vent #2 (Note 3)
(Note 3)
H (4)SRF Vent 333 1 x 10-12 1
1 Continuous Weekly (Note 5)
(Note 4)
(Charcoal Sample) g133 1 x 10-10 g
Continuous Weekly (Note 5)
Principal Gamma 1 x 10'in All Release (Note 4)
Particulate Sample Emitter (Note 2)
Weekly Types as listed Composite Gross Alpha 1 x 10'33 Co nuous Paruculate Sample in A, B, and C Quarterly Composite Sr" and Sr*
1 x 10 33 Continuous te 4)
Particulate Continuous Noble Gas NobleGasesGross 1 x 10~6 (Note 4)
Monitor Beta and Gamma Principle Gamma j
Weekly Weekly Emitters (Note 2)
Condenser Air Grab Sample (Note 3)
H 1 x 10-6 3
Ejector (Note 3)
VIRGINIA VPAP-2103 POWER' REVISION 6 PAGE 80 OF 156 ATTACHMENT 10 (Page 2 of 5)
Surry Radioactive Gaseous Waste Sampling an'd Analysis Program Gaseous Release
' Sampling Minimum Type of Activity Lower Limit of Type Frequency Analysis Analysis Detection (LLD)
Frequency -
( Ci/ml),(Note 1)
Prior to Release Prior to Release nc P anna 3 x ;ga (Grab Sample)
(Each Release)
H 1 x 10-6 3
Continuous Charcoal Sample (Note 4)
(Note 6) 1133 1 x 10-30 l
Continuous Particulate Principal Gamma Hog Depres-10 (Note 4)
Sample (Note 6)
Emitter (Note 2) surization Continuous Composite Paniculate Gross Alpha 1 x 10-to (Note 4)
Sample (Note 6) '
Contmuous Composite 89 and Sr*
1 x 10~30 Particulate Sr I
- 4)
Sample (Note 6) m-
0 VIRGINIA POWER VPAP-2103 REVISION 6 PAGE 81 OF 156 ATTACHMENT 10 (Page 3 of 5)
Surry Radioactive Gaseous Waste Sampling and Analysis Program NOTE 1:
For a particular measurement system (which may include radiochemical separation):
4.66 s LLD =
b (10-1)
E
- V e 2.22E+06
- Y = e-(Aot)
Where:
LLD the "a priori"(before the fact) Lower Limit of Detection as defined above
=
(as microcuries per unit mass or volume) (see 4.8).
the standard deviation of the background counting rate or of the counting sb
=
rate of a blank sample as appropriate (as counts per minute, cpm).
E the counting efficiency (as counts per disintegration).
=
V the sample size (in units of mass or volume).
=
2.22E+06 =
the number of disintegrations per minute (dpm) per microcurie.
Y the fractional radiochemical yield (when applicable).
=
A
= the radioactive decay constant for the particular radionuclide.
At the elapsed time between the midpoint of sample collection and time of
=
counting.
Typical values of E V, Y and At should be used in the calculation.
The l'LD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.
I 4
I
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 82 OF 156 1
ATTACHMENT 10 (Page 4 of 5)
Surry Radioactive Gaseous Waste Sampling arid Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the 88 138 following radionuclides: K/7, Kr, Xel33, Xel33" Xe135, x,135m, and Xefor gaseous 59 S8 60 65 l44 54, Fe, Co, Co, Zn, Mo", Csl34, Csl37, Cel41 and Ce for.
emissions and Mn particulate emissions.This list does not mean that only these nuclides are to be detected and reported. Other nuclides with half lives greater than 8 days, that are measurable and identifiable. at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.
NOTE 3: Sampling and analysis shall also be performed following shutdown, start-up, and whenever a thermal power change exceeding 15 percent of the rated thermal power occurs within any one-hour period, when:
- a. Analysis shows that the dose equivalent 1 concentration in the primary ' oolant has 131 c
increased more than a factor of 3; and
- b. The noble gas activity monitor shows that effluent activity has increased by more than a factor of 3.
NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the period covered by each dose or dose rate calculation made in accordance with 6.3.1, 6.3.3, and 6.3.4.
Samples shall be changed at least once per seven days and analyses shall be completed NOTE 5:
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least seven days following each shutdown, start.
up, or snermal power change exceeding 15 percent of rated thermal power in one hour, and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if Analysis shows that the dose equivalent 1 concentration in the primary coolant has 131 a.
increased by a factor of 3; and
- b. Noble gas monitor shows that effluent activity has increased more than a factor of 3.
P VIRGN POWER VPAP-2103 i
REVISION 6 PAGE 83 OF 156 ATTACHMENT 10 (Page 5 of 5)
Surry Radioactive Gaseous Waste Sampling and Analysis Program NOTE 6: To be representative of the quantities and concentrations ofradioactive materials in i efauents, composite sampling shall employ appropriate methods that will result in a specimen representative of the efauent release.
J e
P b
f 1
2 s
4 A
l l
1
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 84 OF 156 '
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VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 85 OF 156 ATTACHMENT 11 (Page 1 of 4)
North Anna Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sampling Minimum Type of Activity Lower Limit of Type Frequency Analysis Analysis Detection (LLD)
Frequency (4Ci/ml). (Note 1)
A. Waste Gas Prior to Release Principal Gamma Each 'I'a 1 x 104 Storage Tank (Each Ta@
Entten @om 2)
. Grab Sample)
Prior to Release Prior to Release Principle Gamma 4
i x i0 B. Containment Emitters (Note 2) l (Each PURGE Purge (Each PURGE)
H3 Grab Sample) 1 x 10-6 C. Ventilation Monthly 1
peg l K l0^
g (1) Process Vent (Grab Sample)
Monthly
, No 2)
(2) Vent Vent A (Notes 3,4, and (Note 3)
H3 1 x 10-6 i
(3) Vent Vent B 5)
Continuous Weekly I
1 x 10-12 (Note 4)
(Charcoal Sample) g133 1 x 10-'U l
{
Continuous Weekly Principal Gamma 1 x 10-11 All Release (Note 4)
Particulate Sample Emitter (Note 2)
Monthly Co uous Types as listed Composite Gross Alpha 1 x 1011 Particulate Sample in 'A, B, and C Continuous Quarterly Composite Sr" and Sr90 1 x 10-31
")
Particulate Continuous Noble Gas NobleGasesGross 1 x 10-6 (Note 4)
Monitor Beta or Gamma Condenser Air Principle Gamma Ejector / Steam Weekly Weekly I x 104 Emitters (Note 7)
Generator Grab Sample H3 1 x 10-6 Blowdown Vent (Note 6)
Containment.
Principle Gamma Prior to Release Prior to each 1 x 104 Vacuum Steam Emitters (Note 2)
Ejector (Hogger)
(Grab Sample) 3 1 x 10-6 l
Release H
(Note 8)
VPAP-2103.
VIRGINIA REVISION 6 POWER PAGE 86 OF 156 ATTACHMENT 11 (Page 2 of 4)
North Anna Radioactive Gaseous Waste Sampling and Analysis Nrogram I
NOTE 1: For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD =
(33,3)
E = V e 2.22E+06
- Y = e-(AAt)
Where:
the "a priori" (before the fact) Lower Limit of Detection as defined above LLD
=
(as microcuries per unit mass or volume) (see Subsection 4.9) the standard deviation of the background counting rate or of the counting
=
sb rate of a blank sample as appropriate (as counts per minute, cpm) the counting efficiency (as counts per disintegration)
E
=
the sample size (in units of mass or volume)
V
=
2.22E+06 = the number of disintegrations per minute (dpm) per microcurie the fractional radiochemical yield (when applicable)
Y
=
the radioactive decay constant for the pa:ticular radionuclide A
=
the elapsed time between the midpoint of sample collection and time of At
=
counting Typical values of E, V, Y and At should be used in the calculation.
The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not as "posteriori" (after the fact) limit for a particular measurement.
I
VIRGINIA VPAP-2103 POWER REVISION 6 -
. PAGE 87 OF 156 -
ATTACHMENT 11 (Page 3 of 4)
North Anna Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the 87 88 followingradionuclides:Kr,Kr,Xel33, Xel33" Xe135, ge135m,and Xe138 for gaseous emissions and Mn54 p,59,Co,Co ss 60, Zn, yo, Csl34 65 w
. Csl37, Celdl ld4 and Ce for particulate emissions. This list does not mean th5t only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identified and leported.
NOTE 3: Sampling and analysis shall also be performed following shutdown, start-up, and whenever a thermal power change exceeding 15 percent of the rated thermal power occurs within any one-hour period,if:
- a. Analysis shows that the dose equivalent 1331 concentration in the primary coolant is
- greater than 1.0 Ci/gm; and
- b. The noble gas activity monitor shows that effluent activity has increased by more than a factor of 3.
NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the -
period covered by each dose or dose rate calculation made in accordance with 6.3.1,6.3.3, and 6.3.4.
NOTE 5: Samples shall be changed at least once per seven days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least seven days following each shutdown, start-up or thermal power change exceeding 15 percent of rated thermal power in one hour and analyses shall be ;ompleted within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if:
333 Analysis shows that the dose equivalent 1 concentration in the primary coolant is a.
greater than 1.0 pCi/gm and;
- b. Noble gas monitor shows the.t effluent activity has increased more than a factor of 3.
f
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 88 OF 156 ATTACHMENT 11 (Page 4 of 4)
North Anna Radioactive Gaseous Waste Sampling and Analysis Program NOTE 6: Whenever the secondarp coolant activity exceeds 10-5 Ci/ml, samples shall be obtained and analyzed weeldy. Secondary coolant activity samples shall be collected and analyzed on a weekly basis.These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
NOTE 7: The principal gamma emitters for which the LLD speci6 cation applies exclusively are the 138 followingradionuclides:Kr,Kr,Xel33, Xel335, Xe135, Xe135m, and Xefor gaseous 87 88 emissions. This list does not mean that only these nuclides are to be detected and reported.
Other peaks that are measurable and identifiable, at levels exceeding the LLD together with the above nuclides, shall also be identified and reponed.
NOTE 8: If the secondary coolant activity levelin any Steam Generator supplying steam to the Hogger exceeds 1.0E-5 Ci/ml, Steam Generator samples shall be obtained and analyzed prior to release.
6 4
4 9
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 89 OF 156 ATTACHMENT 12 (Page 1 of 3)
Gaseous Emuent Dose Factors for Surry (Gamma and Beta Dose Factors) 3 x/Q = 6.0E-05 sec/m at 499 meters N Direction Dose Factors for Ventilation Vent Noble Gas K
Lw Min N
iw i
iw Radionuclide Total Body Skin Gamma Air Beta Air mrem /vr mremlyr mrad /yr Stad/vr Curie /sec Curie /sec Curie /sec Curie /sec -
Kr-83m 4.54E+00 1.16E+03 1.73E+04 Kr-85m 7.02E+04 8.76E+04 7.38E+04 1.18E+05 Kr-85 9.66E+02 8.04E+04 1.03E+03 1.17E+05 Kr-87 3.55E+05 5.84E+05 3.70E+05 6.18E+05 Kr-88 8.82E+05 1.42E+05 9.12E+05 1.76E+05 Kr 89 9.96E+05 6.06E+05 1.04E+06 6.36E+05 Kr-90 9.36E+05 4.37E+05 9.78E+05 4.70E+05 Xe-131m 5.49E+03 2.86E+04 9.36E+03 6.66E+04 Xe-133m 1.51E+04 5.96E+04 1.96E+04 8.88E+04 Xe-133 1.76E+04 1.84E+04 2.12E+04 6.30E+04 Xe-135m 1.87E+05 4.27E+04 2.02E+05 4.43E+04 Xe-135 1.09E+05 1.12E+05 1.15E+05 1.48E+05 Xe-137 8.52E+04 7.32E+05 9.06E+04 7.62E+05 Xe-138 5.30E+05 2.48E+05 5.53E+05 2.85E+05 Ar-41 5.30E+05 1.61E+05 5.58E+05 1.97E+05
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 90 OF 156 ATTACHMENT 12 (Page 2 of 3)
Gaseous Effluent Dose Factors fot Surry (Gamma and Beta Dose Factors) 3 X/Q = 1.0E-06 sec/m at 644 meters N Direction Dose Factors for Process Vent My Njpy K,
bpy ip Noble Gas ip Radionuclide Total Body Skin Gamma Air Beta Air mrem /vr mrem /vr mrad /vr mrad /vr l
l Curie /sec Curie /sec Curie /sec Curie /sec Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr 85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E403 1.72E+01 -
1.95E+03 i
Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr 90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.llE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
I i
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 91 OF 156
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- ATTACHMENT 12 f
(Page 3 of 3)
Gaseous Emuent Dose Factors for Surry
-(Inhalation Pathway Dose Factors) 3 Ventilation Vent X/Q = 6.0E-05 sec/m at 499 meters N Direction i
i 3
Process Vent x/Q = 1.0E-06 sec/m at 644 meters S Direction.
t l
Radionuclide P
P,.
l iyy ip mrem /vr mrem /vr '
j Curie /sec Curie /sec.
H-3 6.75E+04 1.12E+03 '
i Cr-51 5.13E+03
. 8.55E+01 -
l Mn-54 ND ND Fe 59 ND ND
.j Co-58 ND ND N
. Co ND ND j
Zn-65 -.
ND ND Rb-86 ND ND.
I Sr-90 ND ND Y-91 ND ND l
Zr-95 ND
-ND Nb-95 ND ND Ru-103 -
ND ND Ru-l%
ND ND Ag-110m ND ND i
Te-127m 3.64E+05 6.07E+03 i
Te-129m 3.80E+05 6.33E+03
[
Cs-134 ND ND I
Cs-136 ND ND Cs-137 ND ND Ba 140 ND ND Ce-141 ND ND j
Cc-144 ND ND i
i 1-131 9.75E+08 1.62E+0.7 I-133 2.31E+08 3.85E+06 l
ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1 i
I
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 92 OF 156 i
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e VIRGINIA POWER VPAP-2103 REVISION 6 PAGE 93 OF 156 ATTACHMENT 13 (Page 1 of 3)
Gaseous Emuent Dose Factors for North Anna (Gamma and Beta Dose Factors) 3
%/Q = 9.3E-06 sec/m e.t 1416 meters SE Direction Dose Factors for Ventilation Vent Noble Gas Kiw Lin Miw Njw Radionuclide Total Body Skin Gamma Air Beta Air mrem /yr mrem /yr mrad /vr mrad /yr Curie /sec Curie /sec Curie /sec Curie /sec Kr-83m 7.03E-01 1.79E+02 2.68E+03 Kr-85m 1.09E+04 1.36E+04 1.14E+04 1.83E+04 Kr-85 1.50E+02 1.25E+04 1.60E+02 1.81E+04 Kr-87 5.51E+04 9.05E+04 5.74E+04 9.58E+04 Kr-88 1.37E+05 2.20E+04 1.41E+05 2.72E+04 Kr-89 1.54E+05 9.39E+04 1.61E+05 9.86E+04 Kr-90 1.45E+05 6.78E+04 1.52E+05 7.28E+04 Xe-131m 8.51E+02 4.43E+03 1.45E+03 1.03E+04 Xe-133m 2.33E+03 9.24E+03 3.04E+03 1.38E+04 Xe-133 2.73E+03 2.85E+03 3.28E+03 9.77E+03 Xe-135m 2.90E+04 6.61E+03 3.12E+04 6.87E+03 Xe-135 1.68E+04 1.73E+04 1.79E+04 2.29E+04 Xe-137 1.32E+04 1.13E+05 1.40E+04 1.18E+05 Xe-138 8.21E+04 3.84E+04 8.57E+04 4.42E+04 j
Ar-41 8.22E+04 2.50E+04 8.65E+04 3.05E+04 I
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 94 OF 156 ATTACHMENT 13 (Page 2 of 3)
Gaseous Emuent Dose Factors for Nbrth Anna (Gamma and Beta Dose Factors) 3 y/Q = 1.2E-06 sec/m at 1513 meters S Direction Dose Factors for Process Vent M,
N ip ipv Kv 1.ip, Noble Gas ip Radionuclide Total Body Skin Gamma Air Beta Air mrem /vr mrem /vr mrad /vr mrad /vr Curie /sec Curie /sec Curie /sec Curie /sec 2.32E+01 3.46E+02 Kr-83m 9.07E-02 Kr-85m 1.40E+03 1.75E+03 1.48E+03 2.36E+03 Kr-85 1.93E+01 1.61E+03 2.06E+01 2.34E+03 Kr-87 7.10E+03 1.17E+04 7.40E+03 1.24E+04 Kr-88 1.76E+04 2.84E+03 1.82E+04 3.52E+03 Kr-89 1.99E+04 1.21E+04 2.08E+04 1.27E+04 Kr-90 1.87E+04 8.75E+03 1.96E+04 9.40E+03 Xe 131m 1.10E+02 5.71E+02 1.87E+02 1.33E+03 Xe-133m 3.01E+02 1.19E+03 3.92E+02 1.78E+03 Xe-133 3.53E+02 3.67E+02 4.24E+02 1.26E+03 Xe-135m 3.74E+03 8.53E+02 4.03E+03 8.87E+02 Xe 135 2.17E+03 2.23E+03 2.30E+03 2.95E+03 Xe-137 1.70E+03 1.46E+04 1.81E+03 1.52E+04 Xe-138 1.06E+04 4.96E+03 1.11E404 5.70E+03 Ar-41 1.06E+04 3.23E+03 1.12E+04 3.94E+03
I l
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 95 OF 156 ATTACHMENT 13 (Page 3 of 3)
Gaseous Emuent Dose Factors for North Anna (Inhalation Pathway Dose Factors) 3 Ventilation Vent x/Q = 9.3E-06 sec/m at 1416 meters SE Direction 3
Process Vent x/Q = 1.2E-06 sec/m at 1513 meters S Direction Radionuclide Piyy Pipy mrem /vr mrem /vr Curie /sec Curie /sec H-3 1.05E+04 1.35E+03 Cr-51 7.95E+02 1.02E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND i
Co-60 ND ND Zn-65 ND ND
)
Rb-86 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-110m ND ND Te-127m 5.64E+04 7.28E+03 Te-129m 5.88E+04 7.59E+03 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND I
Cc-141 ND ND Ce-144 ND ND l-131 1.51E+08 1.95E+07 l-133 3.59E+07 4.62E+06 l
ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 96 OF 156
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Surry Radioactive Gaseous Emuent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS
- 1. PROCESS VENT SYSTEM ta) Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 1-GW-RM-102 1
1 1-GW-RM-130-1 (b) lodine Sampler Process Vent Continuous HP Sampler, or l
l-GW-RM-130-1 1
2 l
(c)
Particulate Sampler Process Vent Continuous HP Sampler, or 1
2 l
l-GW-RM-130-1 (d) Process Vent Flow Rate Monitor 1-GW-FT-100 1
3 (e) Sampler Flow Rate Measuring Device KAMAN Flow Rate Measuring Device 1
3 (Parameter #19), or HP Sampler Rotometer
- 2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor 1-SV-RM-111 2 (one per unit) 1
. 2-SV-RM-211 (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP-FI-1 A 1-VP-F1-1B 2 (one per unit) 3 Unit 2: 2-VP-F1-1 A 2-VP-F1-1 B i
- 3. VENTILATION VENT SYSTEM (a)
Noble Gas Activity Monitor SRF:
RRM-101 1
1 l
SPS: Vent #1 1-VG-RM-104 1
1 Vent #2,1-VG-RM -110, or 1
1 1-VG-RM-131-1 e
VPAP-2103
- VIRGINIA REVISION 6 POWER PAGE 98 OF 156 ATTACHMENT 14
}
(Page 2 of 3)
Surry Radioactive Gaseous Emuent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS (b) lodine Sampler SRF: RRM-101 1
2 SPS: Vent #1,1-VG-RM-104 1
2 Vent #2, Continuous HP Sampler, or 1
2 1-VG-RM-131-1 (c) Particulate Sampler SRF: RRM-101 1
2 SPS: Vent #1, VG-RM-104 1
2 Vent #2, HP Continuous Sampler, or 1
2 1-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor 1
3 SRF: 01-RHV-FT-156 1
3 SPS: Vent #1,1-VS-FT-119 1
3 Vent #2,1-VS-FT-il6 (e) Sampler Flow Rate Measuring Device i
SRF: RRM-101 1
3 SPS: Vent #1,1-VG-RM-104 1
3 Vent #2, KAMAN Flow Rate Measuring Device 1
3 (Parameter #19), or HP Sampler Rotometer I
i l
l
~_
1 VPAP 2103 VIRGINIA REVISION 6 POWER PAGE 99 OF 156 t
ATTACHMENT 14
(' age 3 of 3) i Surry Radioactive Gaseous Emuent Monitoring Instrumentation If the number of operable channels is less than required, effluent releases via this path ACTION 1:
may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the number of operable channels is less than required, effluent releases via the ACTION 2:
effected path may continue provided samples are continuously collected within one hour with auxiliary sampling equipment as required in Attachment 10.
l If the number of operable channels is less than required, effluent releases via this ACTION 3:
pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, i
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VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 101 OF 156 ATTACHMENT 15 (Page 1 of 3)
North Anna Radioactive Gaseous Emuent Monitoring Instrumentation INSTRUMENT MINIMUM ACTION OPERABLE CHANNELS
- 1. PROCESS VENT SYSTEM (a)
Noble Gas Activity Monitor l-RM-GW-102 1
2,4 1-RM-GW-178-1 (b) lodine Sampler 1-RM-GW-178-1 1
2, 5 Process Vent Continuous HP Sampler (c)
Particulate Sampler 1-RM-GW-178 1 1
2, 5 Process Vent Continuous HP Sampler (d) Total Flow Monitor 1-GW-FT-108 1
1 (e)
Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19)
I I
HP Sampler Rotameter
- 2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor UnitI l-SV-RM-121 1
3 Unit 2 2-SV-RM-221 (b) Flow Rate Measuring Device UnitI l-SV-FI 100A l SV-FI-101 A 1 (NOTE 1)
I 1-SV-FI-100B l-SV-FI-101B Unit 2 2 SV-FI-200A 2 SV FI-201A 1 (NOTE 2) 1 2-SV-FI-200B 2 SV FI 201B s
l VIRGINIA -
VPAP-2103 POWER REVISION 6 PAGE 102 OF 156 ATTACHMENT 15 (Page 2 of 3)
North Anna Radioactive Gaseous Emuent Monitbring Instrumentation i
MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS
- 3. VENTILATION VENT A (a) Noble Gas Activity Monitor 1-RM VG-104 I
1-RM-VG-179-1 (b) lodine Sampler 1 RM-VG-179-1 1
2 Vent Vent A Continuous HP Sampler (c)
Particulate Sampler 1-RM-VG-179-1 1
2 Vent Vent A Continuous HP Sampler (d) Total Flow Monitor l-HV FT 1212A 1
1 (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19)
HP Sampler Rotameter
- 4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-RM-VG-'l l 3 1
2 1-RM VG-180-1 (b) lodine Sampler 1 RM-VG-180-1 1
2 Vent Vent B Continuous HP Sampler (c) Particulate Sampler 1-RM-VG-180-1 1
2 Vent Vent B Continuous HP Sampler (d) Total Flow Monitor 1-HV FT-1212B 1
1 (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19)
HP Sampler Rotameter 9
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VPAP-2103
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REVISION 6 PAGE 103 OF 156 ATTACHMENT 15 (Page 3 of 3)
North Anna Radioactive Gaseous Emuent Monitoring Instrumentation l
- ACTION 1:
If the number of operable channels is less than required, effluent releases, via this path, may continue if the flow rate is estimated at least once per four hours.
ACTION 2:
If the number of operable channels is less than required, effluent releases, via this path,-
may continue if grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are l
analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACrlON 3:
If the number of operable channels is less than required, effluent releases, via this path, l
may continue if the frequency of the grab samples provided by Technical Specification requirement 4.4.6.3.b is increased to at least once per four hours and these samples are analyzed for gross activity or gamma isotopic activity within eight hours.
ACTION 4:
If the number of operable channels is less than required, the contents of the Waste Gas i
Decay Tanks may be released to the environment provided that prior to initiation of the f
release:
q At least two independent samples of the tank's contents are analyzed, and; j
a.
- b. Atleast two technically qualified members of the Station staffindependently verify the release rate calculations and discharge valve lineup.
ACTION 5:
If the number of operable channels is less than required, effluent releases from the Waste Gas Decay Tank may continue provided samples are continuously _ collected with auxiliary sampling equipment as required in Attachment i1.
NOTE 1: A channel shall consist of:
- a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (1-SV-FI-100A,101 A), or Train B (1-SV-FI-100B,101B) or both,
- b. Flow instruments 101 A and 101B provide low range measurement. Flow instruments 100A and 100B provide high range measurement.
NOTE 2: A channel shall consist of:
- a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (2-SV-FI-200A,201 A), or Train B (2-S -F1-200B,201B) or both, f
- b. Flow instruments 201 A and 201B provide low range measurement. FI'ow instruments l
200A and 200B provide high range measurement.
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Surry Radioactive Gaseous Effluent Monitoring Instramentation Surveillance Requirements CHANNEL CHANNEL CHANNEL SOURCE CHANNEL FUN NAL DESCRIPTION CHECK CHECK CALIBRATION 1.
PROCESS VENT SYb i EM (a) Noble Gas Activity Monitor-Pmviding Alarm and Automatic Termination of Release l-GW-RM-102 D
M**
R O
l-GW-RM-130-1 (b) lodine Sampler Process Vent Continuous HP Sampler, or 1-GW-RM-1301 W
N/A N/A N/A (c) Particulate Sampler Pmcess Vent Continuous HP Sampler, or 1-GW RM-130-1 W
N/A N/A N/A (d) Pmcess Vent Flow Rate Monitor 1-GW-FT-100 D
N/A R
N/A (e) Sampler Flow Rate Measuring j
Device HP Sampler Rotometer, or D
N/A SA N/A KAMAN Flow Rate Measuring D
N/A R
N/A Device (Parameter #19) 2.
CONDENSER AIR EJECTOR SYSTEM (a) Gmss Activity Monitor Unit 1: 1-SV-RM-l i t D
M R
Q Unit 2: 2-SV-RM 211 (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP F1 1 A 1-VP-F1 1B D
N/A R
N/A Unit 2: 2-VP-F1-l A 2-VP-FI-1B 3.
VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF:
RRM 101 SPS:
1-VG-RM -I l0 D
M R
Q i
1-VG-RM -131-1 9
VIRGINIA VPAP-2103 POWER' REVISION 6 PAGE 106 OF 156 ATTACHMENT 16 (Page 2 of 2)
Surry Radioactive Gaseous Emuent Monitoring Instrumentation Surveillance Requirements phNC
"^
CHANNEL CHANNEL SOURCE CHANNEL O
DESCRIPTION CHECK CHECK CALIBRATION TEST (b) lodine Sampler SRF:
RRM-101 SPS:
Vent #1,1-VG-RM-104 Vent #2, Continuous HP W
N/A N/A N/A Sampler, or 1-VG-RM 131-1 (c) Particulate Sampler SRF:
RRM-101 SPS:
Vent #1,1-VG-RM-104 Vent #2, Continuous HP W
N/A N/A N/A Sampler, or 1-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor SRF: Ol-RHV-FI'-156 SPS:
Vent #1,1-VS-FT-119 D
N/A R
N/A Vent #2,1-VS-FT-116 (e) Sampler Flow Rate Measuring Device SRF: RRM-101 D
N/A R
N/A SPS:
Vent #1,1-VG-RM-104 D
N/A R
N/A Vent #2,KAMAN FlowRate D
N/A R
N/A Measuring Device (Parameter #19), or HP D
N/A N/A Sampler Rotometer S/A i
- Prior to each Waste Oas Decay lank release e
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 107 OF 156 ATTACHMENT 17 (Page 1 of 3)
North Anna Radioactive Gaseous Emuent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL SOURCE CHANNEL CHANNEL DESCRIPTION CHECK CHECK CALIBRATION FUNCTIONAL TEST 1.
PROCESS VENT SYSTEM (a)
Noble Gas Activity Monitor 1-RM-GW-102 D
M (NOTE 5)
R Q (NOTE 1) 1 RM-GW-1781 D
M (NOTE 5)
R Q (NOTE 1)
(b) lodine Sampler l-RM-GW-178-1 W
N/A N/A N/A Process Vent Continuous HP Sampler D (NOTE 3)
N/A N/A N/A (c)
Paniculate Sampler l-RM-GW-178-1 W
N/A N/A N/A Process Vent Continuous HP Sampler D (NOTE 3)
N/A N/A-N/A (d) Total Flow Monitor j
1-GW-FT-108 D
N/A R
Q (e)
Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D (NOTE 3)
N/A R
N/A Device (Parameter 19)
HP Sampler Rotameter D (NOTE 3)
N/A SA N/A 2.
CONDENSER AIR EJECTOR SYSTEM j
(a)
Noble Gas Activity Monitor i
Unit I l-SV RM-121 D
M R
Q (NOTE 1)
Unit 2 2-SV RM-221 (b)
Flow Rate Measuring Device UnitI l SV F1-100A 1 SV-FI-101 A D
N/A R
N/A 1-SV-FI 100B l-SV-FI-101B
^
Unit 2 2-SV F1-200A 2-SV-F1201 A D
N/A R
N/A 2-SV-F1200B 2 SV F1-201B
VIRGINIA VPAP-2103 POWER REVISION 6
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North Anna Radioactive Gaseous Emuent Monitoring Instrumentation Surveillance Requirements C
CHANNEL CHANNEL SOURCE CHANNEL FUN O
DESCRIPHON CHECK CHECK CALIBRATION TEST
- 3. VENTILATION VENT A (a)
Noble Gas Activity Monitor 1-RM-VG-104 D
M R
Q (NOTE 2) 1 RM-VG-179-1 D
M (NOTE S)
R Q (NOTE 2).
(b) lodine Sampler 1-RM-VG-179-1 W-N/A N/A N/A Vent Vent A Continuous HP Sampler D(NOTE 3)
N/A N/A N/A s
(c)
Paniculate Sampler 1 RM-VG-179-1 W
N/A N/A N/A Vent Vent A Continuous HP Sampler D (NOTE 3)
N/A N/A N/A (d) Total Flow Monitor 1 HV-FT-1212A D
N/A R
Q (e)
Sampler Flow Rate Measuring Device t
KAMANS Row Rate Measuring D(NOTE 3)
N/A R
N/A Device (Parameter 19)
HP Sampler Rotameter D (NOTE 3)
N/A SA N/A 4 VENTILATION VENT B (a)
Noble Gas Activity Monitor 1 RM-VG-ll3 D
M R
Q (NOTE 4) 1 RM-VG-180-1 D
M (NOTE 5)
R Q (NOTE 2)
(b) lodine Sampler 1-RM VG-180-1 W
N/A N/A N/A Vent Vent B Continuous HP Sampler D (NOTE 3)
N/A N/A N/A (c)
Particulate Sampler 1-RM-VG 180-1 W
N/A N/A N/A Vent Vent B Continuous HP Sampler D (NOTE 3)
N/A N/A N/A (d) Total Row Monitor 1 HV-FT-1212B D
N/A R
Q (e)
Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D (NOTE 3)
N/A R
N/A Device (Parameter 19)
HP Sampler Rotameter D (NOTE 3)
N/A SA N/A
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ATTACHMENT 17 (Page 3 of 3)
North Anna Radioactive Gaseous Emuent Monitoring InstrumentationSurveillance Requirements NOTE 1: The Channel Functional Test shall demonstrate:
a.
Automatic actuation of the valves in this pathway and Control Room alarm l
annunciation occur if the instrument indicates measured levels above the alarm / trip setpoint.
- b. Alarm annunciation occurs if the instrument controls not set in " operate" mode.
NOTE 2: The Channel Functional Test shall demonstrate:
a.
Control Room alarm annunciation occurs if the instrument indicates measured levels are above the alarm / trip setpoint.
- b. Alarm annunciation occurs if the instrument controls not set in " operate" mode.
NOTE 3: Channel Checks shall consist of verifying indication of flow during periods of release.
Channel Checks shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
The Channel Funct onal Test shall demonstrate that:
i NOTE 4:
a.
Control Room alarm annunciation occurs if the instrument indicates measured levels are above alarm / trip setpoint.
- b. The Instrument mode selection control automatically resets to " operate" mode when released.
NOTE 5: Monitors 1-RM-GW-178-1,1-RM-VG-179-1, and 1-RM-VG-180-1 are electronically source checked using an LED.
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ATTACHMENT 18
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Critical Organ and Inhalation Dose. Factors for Surry (Critical Pathway Dose Factors)
Ventilation Vent D/Q = 9.0E-10 m-2 at 5150 meters S Direction Process Vent D/Q = 4.3E-10 m-2 at 5150 meters S Direction RM Radionuclide RMjyy mred; vr mrem /vr Curie /sec Curie /sec H-3 7.20E+02 3.12E+02 Mn-54 ND ND Fe-59 ND ND Cr-51 6.45E+01 3.08E+01 l
Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-110m ND ND Te-127m 8.06E+04 3.85E+04
~~
Te-129m 1.25E+05 5.98E+04 1-131 6.21E+08 2.97E+08 1-133 5.79E+06 2.77E+06 l
Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-14i ND ND Ce-144 ND ND ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 112 OF 156 ATTACHMENT 18 (Page 2 of 2)
Critical Organ and Inhalation Dose Factors for Surry (Inhalation Pathway Dose Factors) 3 Ventilation Vent yjQ = 3.0E-07 sec/m at 5150 meters S Direction 3
Process Vent y/Q = 1.3E-07 sec/m at 5150 meters S Direction Radionuclide RM;yy RM;py mrem /vr mrem /vr Curie /sec Curie /sec H3 1.94E+02 8.41E+01 Cr-51 1.73E+01 7.48E+00 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru 103 ND ND Ru-106 ND ND Ag-110m ND ND Te-127m 1.46E+03 6.33E+02 Te-129m 1.64E+03 7.12E+02 1-131 4.45E+06 1.93E+06 1-133 1.07E+06 4.63E+05 Cs-134 ND ND l
Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Cc-141 ND ND Ce-144 ND ND i
ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1 l
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VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 113 OF 156 ATTACHMENT 19 (Page 1 of 1)
Critical Organ Dose Factors for North Anna (Critical Pathway Dose Factors)
Ventilation Vent D/Q = 2.4E-09 m-2 at 3250 meters N Direction Process Vent D/Q = 1.lE-09 m-2 at 3250 meters N Direction RM Radionuclide RMiyy ipy mrem /vr mrem /vr Curie /sec Curie /sec H-3 1.73E+03 9.36E+02 Mn-54 ND ND Fe-59 ND ND Cr-51 1.50E+02 6.89E+01 l
Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND Y ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-110m ND ND Te-127m 1.97E+05 9.04E+04 Te-129m 2.95E+05 1.35E+05 1-131 1.45E+09 6.72E+08 1-133 1.33E+07 6.12E+06 l
Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Cc-141 ND ND Ce-144 ND ND ND - No data for dose factor accordmg to Regulatory Guide 1.109, Revision I i
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Surry Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Lention Frequency Analysis
- 1. DIRECT RADIATION About 40 Routine Monitoring Stations to be placed as follows:
- 1) Inner Ringin general area of site boundary GAMMA DOSE with station in each sector
- 2) Outer Ring 6 to 8 km from the site with a Quarterly Quanerly station in each sector
- 3) The balance of the 8 dosimeters should be placedin specialinterest areas such as population centers, nearby residents, schools, and in 2or 3 areasto serve as controls
- 2. AIRBORNE Samples from 7 locations:
a) I sample from close to the site boundary-location of the highest Radioiodine Canister 131 calculated annual 1
Analysis Weekly average ground level Continuous Radioiodines and D/Q Sampler Particulates b) 5 sample locations 6-8 operation with Particulate Sampler km distancelocated in a samplecollection Gross beta radioactivity concentric ring around weekly analysis following filter the Station change; c) I sample from a control Gamma. isotopic analysis location 15-30 km f composite (by distant, providing valid 1 cation) quarterly background data
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 116 OF 156 ATTACHMENT 20 (Page 2 of 3)
Surry Radiological Environmental Monitbring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location Frequency Analysis
- 3. WATERBORNE a) I sample upstream Gamma isotopic analysis a) Surface Monthly Sample monthi :-
Y b) I sample downstream Composite for trinum analysis quarterly Ganmiaisotopic and tritium b) Ground Sample from 1 or 2 sources Quarterly analysis quarterly c) Sediment I sample from downstream Gamma isotopic analysis from area with existing or Semi-Annually shoreline potential recreational value semi-annually 5 samples from vicinity of Gamma isotopic analysis d) Silt the Station Semi-Annually 3
,g
- 4. INGESTION a) Milk a) 3 samples from, milking (NOTE 1) ammalsin the vicimty of the Station 131 Gamma isotopic and 1 b) I s, ample from milking Monthly ammals at a control analysis monthly location (15-30 km distant) a) 2 samples of oysters in the vicinity of the Semi-Annually Gamma isotopic on edibles l
Station b) 4 samples of clams in l
the vicinity of the Semi-Annually Gamma isotopic on edibles l
b) Fish and Station invertebrates c) I sampling of crabs from the vicinity of the Annually Gamma isotopic on edibles Station d) 2 samples of fish from the vicinity of the Station (catfish, white Semi-Annually Gamma isotopic on edibles perch, cel)
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 117 OF 156 ATTACHMENT 20 (Page 3 of 3)
Surry Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location Frequency Analysis
- 4. INGESTION (Continued)
Ga isotopic on edible b) amp e oybeans Annually c) I sample peanuts d) I sample of a broadleaf vegetation of two different available offth locations with higi:c% annual average c) Food ground levelD/Q,if one Products or more milk samples Monthly,if 331 Gamma isotopic and 1 are unavailable available, or at anal sis Y
e) I sample of a broadleaf harvest vegetation grown 15-30 kmin the available,least prevalent wind direction,if one or more milk samples are unavailable NOTE 1: If milk sampling cannot be performed, use item 4.c (d).
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North Anna Radiological Environmental Monitoring Program i
Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location (NOTE 2)
. Frequency Analysis
- 1. DIRECT RADIATION (NOTE 3) 36 routine monitoring stations, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, to be placed as follows:
- 1) An inner ring of stations, one in each emergency GAMMA DOSE l
meteorological sector within the site boundary
- 2) An outer ring of stations, one in each l
i emergency 0"*"*IIY 0"*"*IIY meteorological sector within 8 km range from the site
- 3) The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations
VIRGlNIA VPAP-2103 POWER REVISION 6 PAGE 120 OF 156 ATTACHMENT 21 (Page 2 of 5)
North Anna Radiological Environmental Monitoring Program I
Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location (NOTE 2)
Frequency Analysis
- 2. AIRBORNE Samples from 5 locations:
a) 3 samples from close to i
the 3 site boundary locations (in different sectors) of the highest Radiojodine Canister 1
I Analysis, weekly calculated historical annual average ground Continuous Radioiodines and level D/Q
- samplet, Particulates b) I sample from the operation with vicinity of a community sample Particulate Sampler l
having the highest collection Gross beta radioactivity calculated annual weekly analysis following filter average ground level change;(NOTE 4)
D/Q l
c) I sample from a control Gamma isotopic analysis location 15-40 km of composite (by l
distant and in the least location) quanerly prevalent wind direction (NOTE 5)
- 3. WATERBORNE Samples from 3 locations:
Gamma isotopic analysis a) I sample upstream monthly; (NOTE 5) a) Surface b) 1 sample downstream Grab Monthly Composite for tritium c) I sample from cooling analysis quarterly lagoon Sample from 1 or 2 sources Gammaisotopic and tritium b) Ground only iflikely to be affected Grab Quarterly analysis qtiarterly (NOTE 5)
I sample from downstream Gamma isotopic analysis c) Sediment area with existing or Semi-Annually potential recreational value semi-annually (NOTE 5)
VPAP-2103 VIRGINIA REVISION 6 c
POWER PAGE 121 OF 156 ATTACHMENT 21 (Page 3 of 5)
North Anna Radiological Environmental Monitoring Program Exposure Pathway Numberof Sample and Samp%
Collection Type and Frequency of l
and/or Sample Location (NOTE 2)
Frequency Analysis
- 4. INGESTION a) Samples from milking animals in 3 locations within 5 km that have the highest potential. If there are none, then I sample from milking animals in each of 3 areas a) Milk between 5 to 8 km where Monthly atall Gammaisotopic(NOTE 5) 133 (NOTE 7) doses are calculated to be times and 1 analysis monthly greater than 1 mrem per yr (NOTE 6) b) I sample from milking animals at a controllocation (15-30 km in the least prevalent wind direction) a) I sample ofcommercially and recreationally important species (bass, sunfish, catfish) b) Fish and in vicinity of plant discharge Gamma isotopic on edible Semiannually Invertebrates area portions b) I sample of same species in areas not influenced by plant discharge a) Samples of an edible broad leaf vegetation grown nearest each of two different offsite locations of highest predicted historical annual average Monthly if Gamma isotopic (NOTE S) c) Food ground level D/Q if milk
""" '" '*' I
!31 and!
analysis Products sampling is not performed at harvest b) I sample of broad leaf vegetation grown 15-30 kmin the least prevalent wind direction if milk sampling is not performed i
t i
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ATTACHMENT 21 (Page 4 of 5) i North Anna Radiological Environmental Mdnitoring Progr'am NOTE 1: The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable.
Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and be included in the sampling program.
NOTE 2: For each and every sample location in Attachment 21, specific parameters of distance and direction sector from the centerline of the reactor, and additional description where pertinent, shall be provided in Attachment 23. Refer to Radiological Assessment Branch Technical Positions and to NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plant. Deviations are permitted from the required sampling schedule if specimens are unattainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unattainable due to sampling equipment malfunction, every effort shall be made to complete corrective action before the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to 6.7.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable attemative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to 6.7.2, identify the cause of the unavailability of samples for that pathway and identify the new locations for obtaining replacement samples in the next Annual Radioactive Effluent Release Report, and include revised figures and tables from the ODCM reflecting the new locations in the report.
o
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 123 OF 156 ATTACHMENT 21 (Page 5 of 5)
North Anna Radiological Environmental Monitoring Program NOTE 3: One or more instruments, such as a pressurized ion chamber, for measuring and recording dosr eate continuously may be used in place of, or in addition to, integrating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be
~
one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct radiation. The 36 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal t
fading.
NOTE 4: Airbome particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples,
~
gamma isotopic analysis shall be performed on the individual samples.
NOTE 5: Gamma isotopic analysis is the identification and quantification of gamma-emitting radionuclides that may be attributable to effluents from the facility.
NOTE 6: The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
NOTE 7: If milk sampling cannot be performed, use item 4.c (Page 3 of 5, Attachment 21)
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Surry Environmental Sampling Locations SAMPLE LOCATION DISTANCE DIRECTION REMARKS MEDIA (MILES)
Site Boundary Air Charcoal
'.37 NNE Location at Sector 0
and Paniculate Surry Station (SS) with Highest D/Q Hog Island Reserve (HIR) 2.0 NNE Bacons Castle (BC) 4.5 SSW Alliance (ALL) 5.1 WSW Colonial Parkway (CP) 3.7 NNW Dow Chemical (DOW) 5.1 ENE Fon Eustis (FE) 4.8 ESE Newpon News (NN) 16.5 ESE Control Location Environmental Control (00)
Onsite **
TLDs West Nonh West (02) 0.17 WNW Site Boundary Surry Station Discharg 0.6 NW Site Boundary (03)
North Nonh West (04) 0.4 NNW Site Boundary North (05) 0.29 N
Site Boundary l
North North East (06) 0.28 NNE Site Boundary Nonh East (07) 0.31 NE Site Boundary East Nonh East (08) 0.43 ENE Site Boundary East (Exclusion)
(09) 0.31 E
Onsite West (10) 0.40 W
Site Boundary West South West (11) 0.45 WSW Site Boundary South West (12) 0.30 SW Site Boundary South South West (13) 0.43 SSW Site Boundary South (14) 0.48 S
Site Boundary South South East (15) 0.74 SSE Site Boundary South East (16) 1.00 SE Site Boundary East (17) 0.57 E
Site Boundary Station Intake (18) 1.23 ESE Site Boundary Hog Island Reserve (19) 1.94 NNE Near Resident
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 126 OF 156 ATTACHMENT 22 1
(Page 2 of 4)
. Surry Environmental Sampling L6 cations SAMPLE LOCATION DISTANCE DIRECTION REMARKS MEDIA (MILES)
Environmental Bacons Castle (20) 4.45 SSW Approx. 5 miles TLDs Route 633 (21) 3.5 SW Approx. 5 miles Alliance (22) 5.1 WSW Approx. 5 miles Surry (23) 8.0 WSW Population Center Route 636 and 637 (24) 4.0 W
Approx. 5 miles Scotland Wharf (25) 5.0 WNW Approx. 5 miles Jamestown (26) 6.3 NW Approx. 5 miles Colonial Parkway (27) 3.7 NNW Approx. 5 miles Route 617 and 618 (28) 5.2 NNW Approx. 5 miles Kingsmill (29) 4.8 N
Approx. 5 miles Williamsburg (30) 7.8 N
Population Center Kingsmill North (31) 5.6 NNE Approx. 5 miles Budweiser (32) 5.7 NNE Population Center Water Plant (33) 4.8 NE Approx. 5 miles Dow (34) 5.1 ENE Approx. 5 miles Lee Hall (35) 7.1 ENE Population Center Goose Island (36) 5.0 E
Approx. 5 miles Fort Eustis (37) 4.8 ESE Approx. 5 miles Newport News (38) 16.5 ESE Population Center James River Bridge (39) 14.8 SSE Control Benn's Church (40) 14.5 S
Control Smithfield (41) 11.5 S
Control Rushmere (42) 5.2 SSE Approx. 5 miles Route 628 (43) 5.0 S
Approx. 5 miles Milk Epp's 4.8 SSW Colonial Parkway 3.7 NNW Judkin's 6.2 SSW William's 22.5 S
Control Location l
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 127 OF 156 ATTACHMENT 22 (Page 3 of 4) l Surry Environmental Sampling Locations SAMPLE LOCATION DISTANCE DIRECTION REMARKS MEDIA (MILES)
Onsite* *
- Well Water Surry Station Hog Island Reserve 2.0 NNE f
Crops (Corn, Slade's Fann 2.4 S
- Peanuts, Soybeans)
Brock's Farm 3.8 S
Crops Spratley's Garden 3.2 S
(Cabbage, Kale)
Carter's Grove Garden 4.8 NE
'*N "
g,,,s Garden (Chester, Va.)
River Water Surry Discharge 0.17 NW (Monthly)
Scotland Wharf 5.0 WNW Control Location Sediment Chickahominy River 11.2 WNW Control Location (Silt)
Surry Station Intake 1.9 ESE Suny Station Discharge 1.0 NNW Hog Island Point 2.4 NE I
Point of Shoals 6.4 SSE l
m
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 128 OF 156 ATTACHMENT 22 (Page 4 of 4)
Surry Environmental Sampling Locations SAMPLE
' LOCATION DISTANCE DIRECTION REMARKS MEDIA (MILES)
Clams Chickahominy River 11.2 WNW Control Location Surry Station Discharge 1.3 NNW Hog Island Point 2.4 NE Lawne's Creek 2.4 SE Oysters Walnut Point 2.0 EENE l
Mulberry Point 4.9 EESE l
Crabs Surry Station Discharge 0.6 NW Fish Surry Station Discharge 0.6 NW Shoreline Hog Island Reserve 0.8 N
Sediment Onsite Location -in Lead Shield Onsite sample of Well Water-taken from tap-water at Surry Environmental Building
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 129 OF 156 ATTACHMENT 23 (Page 1 of 4)
North Anna Environmental Sampling Locations Distance and Direction From Unit No.1 Sample.
Location Station Distance Direction Collection REMARKS Media No.
(Miles)
Frequency 01 0.20 NE Quanerly & On-Site Environment NAPS SewageTreatment al Plant Annually R Ds Frederick's Hall 02 5.30 SSW Quanerly &
Annually
%A Mineral.VA 03 7.10 WSW 9
%E Warcs Crossroads 04 5.10 WSW 9
9 E
Route 752 05 4.20 NNE Sturgeon's Creek Marina OSA 3.20 N
9 dY A y
Levy, VA 06 4.70 ESE 9
A Qdane Bumpass. VA 07 7.30 SSE Qdam Site Boundary End of Route 685 21 1.00 WNW Route 700 22 1.00 WSW 9
dY A Site Boundary y
Od**dY # Site Boundary
" Aspen Hills" 23 0.93 SSE y
Orange, VA 24 22.00 NW Quamrly & Control g
y Beanng Cooling Tower N-1/33 0.06 N
Quarterly On-Site Sturgeon's Creek Marina N-2/34 3.20 N
Quanerly Parking Lot "C" NNE-3/35 0.25 NNE Quanerly On-Site Good Hope Church NNE-4/36 4.96 NNE Quanerly Parking Lot "B" NE 5/37 0.20 NE Quarterly On-Site Lake Anna Manna NE-6/38 1.49 NE Quanerly Weather Tower Fence ENE-7/39 0.36 ENE Quarterly On-Site Route 689 ENE-8/40 2.43 ENE Quanerly Near Trairung Facility E-9/41 0.30 E
Quanerly On-Site "Moming Glory Hill" E-10/42 2.85 E
Quanerly Island Dike ESE-II/43 0.12 ESE Quanerly On-Site Route 622 ESE-12/44 4.70 ESE-Quanerly l
(
nVIRGINIA VPAP-2103 POWER REVISION 6
'PAGE 130 OF 156 I
ATTACHMENT 23 (Page 2 of 4)'
North Anna Environmental Sampling Locations Distance and Direction From Unit No.1 i
i Sample Location Station Distance Direction Collection REMARKS Meaia No.
(Miles)
Frequency
{
Envimnment Biology Lab SE-13/45 0.75 SE Quanerly.
On-Site al TLDs Route 701 (Dam Entrance)
SE-14/46 5.88 SE Quanerty
" Aspen Hills" SSE-15/47 0.93 SSE Quanerly Site Boundary Elk Creek SSE-16/48 2.33 SSE Quanerly l
Canpoumi S-17/49 0.22 S
Quanerly On-Site' Gm Elk Creek Oiurch S-18/50 1.55 S
Quanerly l
NAPS Access Road SSW-19/51 0.36 SSW Quanerly On-Site Route 618 SSW-20/52 5.30 SSW Quaneriy
~
NAPS Access Road SW-21/53 0.30 SW Quanerly on-Site Route 700 SW-22/54 4.36 SW Quanerly
[
500 KV Tower WSW-23/55 0.40 WSW Quanerly On-Site l
Route 700 WSW-24/56 1.00 WSW Quanerly Site Boundary NAPS RadioTower W-25/57 0.31 W
Quanerly On-Site Route 685 W-26/58 1.55 W
Quanerly End of Route 685 WNW-27/59 1.00 WNW Quanerly Site Boundary H. Purcell's Private Road WNW-28/60 1.52 WNW Quanerly End of #1M2 Intake NW-29/61 0.15 NW Quanerly On-Site Lake Anna Campground NW-30/62 2.54 NW Quanerly
- 1M21ntake NNW-31/63 0.07 NNW Quanerly On-Site l
Route 208 NNW-32/64 3.43 NNW Quanerly -
i Bumpass Post Office C-1/2 7.30 SSE Quanerly -
Control Orange, VA C-3/4 22.00 NW Quanerly Control r
Mineral. VA -
C-5/6 7.10 WSW Quarterly Control
^
Louisa. VA C-7/8 11.54 WSW Quanerly Control 2
h h
l
)
w a
T i
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 131 OF 156 ATTACHMENT 23 (Page 3 of 4)
North Anna Environmental Sampling Locations Distance and Direction From Unit No.1 Sample Location Station Distance Direction Collection REMARKS Media No.
(Miles)
Frequency Airbome NAPS SewageTreatment 01 0.20 NE Weekly On-Site Plant Paniculate Frederick's Hall 02 5.30 SSW Weekly and Mineral. VA 03 7.10 WSW Weekly Radioiodine Wares Crossmads 04 5.10 WNW Weekly Route 752 05 4.20 NNE Weekly Sturgeon's Creek Marina 05A 3.20 N
Weekly Levy.VA 06 4.70 ESE Weekly Bumpass. VA 07 7.30 SSE Weekly.
End of Route 685 21 1.00 WNW Weekly Site Boundary Route 700 22 1.00 WSW Weekly Site Boundary
" Aspen Hills" 23 0.93 SSE Weekly Site Boundary Orange. VA 24 22.00 NW Weekly Control Surface Water Waste HeatTreatment (Commitment Facility (Second Cooling 08 1.10 SSE Monthly 3.2.2]
Lagoon)
North Anna River (upstream)Rt 669 Bridge 09A 12.9 WNW Monthly Control (Brook's Bridge)
North Anna River 11 5.80 SE Monthly (downstream) d ar Biology Lab OIA 0.75 SE Quartedy Aquatic Waste Heat Treatment Sediment Facility (Second Cooling 08 1.10 SSE Semi-Annually Lagoon)
Nonh Anna River (upstream)Rt 669 Bddge 09A 12.9 WNW Semi-Annually Control (Brook's Bridge)
North Anna River 11 5.80 SE Semi-Annually (downstream)
Shoreline Soil Lake Anna (upstream) 09 2.20 NW Semi-Annually Soil NAPS SewageTreatment 01 0.20 NE Once per 3 yrs On-Site Plant 1
J
b VIRGINIA VPAP-2103 POWER REVISION 6.
PAGE 132 OF 156 ATTACHMENT 23 (Page 4 of 4)
North Anna Environmental Sampling Locations Distance and Direction From Unit No.1 Sample Location Station Distance Direction Collection REMARKS Media No.
(Miles)
Frequency Soil Fredericks Hall 02 5.30 SSW Once per 3 yrs (continued)
Mineral. VA 03 7.10 WSW Once per 3 yrs Wares Crossroads 04 5.10 WNW Once per 3 yrs Route 752 05 4.20 NNE Once per 3 yrs Sturgeon's Creek Marina 05A 3.20 N
Once per 3 yrs Levy. VA 06 4.70 ESE Once per 3 yrs Bumpass. VA 07 7.30 SSE Once per 3 yrs End of Route 685 21 1.00 WNW Once per 3 yrs Site Boundary Route 700 22 1.00 WSW Once per 3 yrs Site Boundary
" Aspen Hills" 23 0.93 SSE Once per 3 yrs Site Boundary Orange. VA 24 22.00 NW Once per 3 yrs Control Milk Holladay Dairy 12 8.30 NW Monthly (R.C. Goodwin)
" I (Frede c '
all)
Fish Waste Heat Treatment Semi-Facility (Second Cooling 08 1.10 SSE Annually Lagoon)
Lake Orange 25 16.50 NW
}y Control Food Products Route 713 14 vanes NE (Broad Leaf Route 614 15 varies SE Monthly vegetation)
Route 629/522 16 varies NW if available, or Control Route 685 21 varies WNW at harvest
" Aspen Hills" Area 23 varies SSE
VPAP-2103 VIRGINIA REVISION 6 POWER PAGE 133 OF 156 ATTACHMENT 24 (Page 1 of 2)
Detection Capabilities for Surry Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD)
Food Airborne Sed.iment Analysis Water Particulate Milk Products II
(
g)
(NOTE 2)
(pCill) or Gases (pCi/l)
(pCi/kg)
)
(wet) 3 (pCi/m )
Gross beta 4
0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 (NOTE 3) 1 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 60 Ba-140 60 15 La-140 15 Required detection capabilities for thermoluminescent dosimeters used for environment NOTE 1:
measurements are given in Regulatory Guide 4.13.
This list does not mean that only these nuclides are to be detected and reported. Other peaks NOTE 2:
that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
LLD for the Ground (drinking) Water Samples. The LLD for the surface (non-drinking)
NOTE 3:
water samples is 10 pCi/1.
s a
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 134 OF 156 ATTACHMENT 24 (Page 2 of 2)
Detection Capabilities for Surry Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD)
NOTE 1: For a particular measurement system (which may include radiochemical separation):
4.66 sD LLD =
(24-1)
E
- V e 2.22E+06
- Y = e-(AAt)
Where:
LLD the "a priori" (before the fact) Lower Limit of Detection as defined above
=
(as microcuries per unit mass or volume) (see 4.8) the standard deviation of the background counting rate or of the counting sb
=
rate of a blank sample as appropriate (as counts per minute, cpm)
E the counting efficiency (as counts per disintegration)
=
V the sample size (in units of mass or volume)
=
2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y
the fractional radiochemical yield (when applicable)
=
A the radioactive decay constant for the particular radionuclide
=
At the elapsed time between sample collection (or end of the sample
=
collection period) and time of counting (for environmental samples, not plant effluent samples) l Typical values of E, V, Y and At should be used in the calculation.
The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.
c VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 135 OF 156 ATTACHMENT 25 (Page 1 of 2)
Detection Capabilities for North Anna Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD)
^I' Fish Sediment Analysis Water Particulate Milk Products
(
II (PCi/kg)
(NOTE 2)
(pCi/l) or Gases (pCi/l)
(pCi/kg) 3
(**I)
(**I)
(pCi/m )
(weg)
Gross beta 4
0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260-Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 (NOTE 3) 1 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs 137 18 0.06 150 18 80 180 Bt-140 60 60 La-140 15 15 NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
NOTE 3: LLD for the ground (drinking) water samples. The LLD for the surface (non-drinking) water samples is 10 pCi/1.
O
I VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 136 OF 156 ATTACHMENT 25 (Page 2 of 2)
Detection Capabilities for North Anna Environniental Sample Analysis LOWER LIMIT OF DETECTION (LLD) (NOTE 3)
NOTE 3: For a particular measurement system (which may include radiochemical separation):
l 4.66 s i
D LLD =
(25-1)
E V
- 2.22E+06
- Y = e-(Aat)
Where:
LLD the "a priori"(before the fact) Lower Limit of Detection as defm~ ed above
=
(as microcuries per unit mass or volume) (see 4.9) the standard deviation of the background counting rate or of the counting sb
=
rate of a blank sample as appropriate (as counts per minute, cpm)
E the counting efficiency (as counts per disintegration)
=
V the sample size (in units of mass or volume)
=
2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y
the fractional radiochemical yield (when applicable)
=
1 the radioactive decay constant for the particular radionuclide
=
the elapsed time between sample collection (or end of the sample At
=
collection period) and time of counting (for environmental samples, not plant effluent samples)
Typical values of E, V, Y and At should be used in the calculation.
The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.
- VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 137 OF 156 ATTACHMENT 26 (Page 1 of 1)
Reporting Levels for Radioactivity Concentrations in Environmental Samples at Surry Airbrne
' Water Fish Milk Food Products (PCill)
{p ;j[)
(pCi/kg, wet)
(pCi/l)
(pCi/kg, wet) r g
H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 (NOTE 1) 2 0.9 3
100 Cs-134 30 10 1,000 60 1,000' Cs-137 50 20 2,000 70 2.000 Ba-La-140 200 300 NOTE 1: Reponing icvel for the ground (drinking) water samples required by Attachment 20. The reponing level for the surface (non-drinking) water samples required by Attachment 20 is 20 pCi/1.
VIRGINIA VPAP-2103
' POWER.
REVISION 6 PAGE 138 OF 156 l
l l
l Intentionally Blank "P
r
VIRGINIA VPAP-2103 -
POWER REVISION 6 PAGE 139 OF 156 ATTACHMENT 27 (Page 1 of 1)
Reporting Levels for Radioactivity Concentrations in Environmental Samples at North Anna
^ '"'
Water Fish Milk Food Products (PCi/l)
(pCi/kg, wet)
(pCi/l)
(pCi/kg, wet) g y
OE 1)
H-3 20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 NOTE 1: For drinking w/Jer samples
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 140 OF 156 I
s I
i l
Intentionally Blank i
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 141 OF 156 ATTACHMENT 28 (Page 1 of 8)
Surry Meteorological, Liquid, and Gaseous Pathway Analysis 1.0 METEORLOGICAL ANALYSIS 1.1 Purpose The purpose of the meteorological analysis was to determine the annual average X/Q and D/Q values at critical locations around the Station for ventilation vent (ground level) and process vent (mixed mode) releases. The annual average X/Q and D/Q values were used in a dose pathway analysis to determine both the maximum exposed individual at site boundary and -
member of the public. The X/Q and D/Q values resulting in the maximum exposures were incorporated into the dose factors in Attachments 12 and 18.
1.2 Meteorological Data, Parameters, and Methodology Onsite meteorological data for the period January 1,1979, through December 31,1981, were used in calculations. These data included wind speed, wind direction.
,d iiGerential temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (i.e., ventilation vent), and those characterized as mixed mode (i.e., process vent). The portions of release characterized as ground level were based on AT sg,9fi.28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were i
based on AT158.9ft-28.2ft and 158.9 ft wind data.
X/Qs and D/Qs were calculated using the NRC computer code "XOQDOQ - Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations",
September,1977. The code is based upon a straight line airflow model implementing the assumptions outlined in Section C (excluding Cla and Clb) of Regulatory Guide 1.111,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."
The open terrain adjustment factors were applied to the X/Q values as recommended in Regulatory Guide 1.111. The site region is characterized flat terrain such that open terrain correction factors are considered appropriate. The ground level ventilation vent release calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area. The effective release height used in mixed mode release calculations was based on a process vent release height of 131 ft, and plume rise due to momentum for a vent diameter of 3 in, with plume exit velocity of 100 ft/sec.
-.- ---.a
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 142 OF 156 ATTACHMENT 28 (Page 2 of 8)
Surry Meteorological, Liquid, and Gaseous Pathway Analysis Ventilation vent, and vent releases other than from the process vent, are considered ground level as specified in Regulatory Guide 1.111 for release points less than the height of adjacent solid structures. Terrain elevations were obtained from Surry Power Station Units 1 and 2 Virginia Electric and Power Company Updated Final Safety Analysis Repon Table 11 A-8.
X/Q and D/Q values were calculated for the nearest site boundary, resident, milk cow, and vegetable garden by sector for process vent and ventilation vent releases. %/Q values were also calculated for the nearest discharge canal bank for process and ventilation vent releases.
According to the defm* ition for short term in NUREG-0133," Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations," October,1978, some gaseous releases may fit this category, primarily waste gas decay tank releases and containment purges.
However, these releases are considered long term for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past release reports.
Therefore, the use of annual avc we concentrations is appropriate according to NUREG-0133.
1.3 Results The X/Q value that resulted in the maximum total body, skin, and inhalation exposure for ventilation vent releases was 6.0E-05 sec/m3 at a site boundary location 499 meters N s= tor.
For process vent releases, the site boundary X/Q value was 1.0E-06 sec/m3 at a location 644 meters S sector. The discharge canal bank X/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 7.8E-05 sec/m3 at a location 290 meters NW sector.
The discharge canal bank X/Q value for process vent was 1.6E-06 sec/m3 at a location 290 meters NW sector.
Pathway analysis indicated that the maximum exposure from 1131, 1133, and from all l
radionuclides in particulate form with half-lives greater than 8 days, was through the grass-cow-milk pathway. The D/Q value from ventilation vent releases resulting in the maximum 2
exposure was 9.0E-10 per m at a location 5150 meters S sector. For process vent releases, the 2
D/Q value was 4.3E-10 per m at a location 5150 meters S sector. For tritium, the X/Q value from ventilation vent releases resulting in the maximum exposure for the milk pathway was 3.0E-07 sec/m, and 1.3E-07 sec/m3 for process vent releases at a location 5150 meters S 3
sector. The inhalation pathway is the only other pathway existing at this location.Th'erefore, the %/Q values given for tritium also apply for the inhalation pathway.
VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 143 OF 156 ATTACHMENT 28 (Page 3 of 8)
Surry Meteorological, Liquid, and Gaseous Pathway Analysis 2.0 LIQUID PATHWAY ANALYSIS 2.1 Purpose The purpose of the liquid pathway analysis was to determine the maximum exposed member of the public in unrestricted areas as a result of radioactive liquid effluent releases. The analysis included a determination of most restrictive liquid pathway, most restrictive age group, and critical organ. This analysis is required for Subsection 6.2, Liquid Radioactive Waste Effluents.
2.2 Data, Parameters, and Methodology Radioactive liquid ef0uent release data for the years 1976,1977,1978,1979,1980, ahd 1981 were compiled from the Surry Power Station effluent release reports. The data for each year, along with appropriate site specific parameters and default selected parameters, were entered into the NRC computer code LADTAP as described in NUREG-0133.
Liquid radioactive effluents from both units are released to the. Tames River via the discharge canal. Possible pathways of exposure for release from the Station include ingestion of fish and invertebrates and shoreline activities. The irrigated food pathway and potable water pathway
~
do not exist at this location. Access to the discharge canal by the general public is gained two ways: bank fishing, controlled by the Station and limited to Virginia Power employees or guests of employees, and by boat as far upstream as the inshore end of the discharge canal groin. It has been estimated that boat sport fishing would be performed a maximum of 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per year, and that bank fishing would be performed a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year.
For an individual fishing in the discharge canal, no river dilution was assumed for the fish pathway. For an individual located beyond the discharge canal groins, a river dilution factor of 5 was assumed as appropriate according to Regulatory Guide 1.109, Rev.1, and the fish, I
invertebrate, and shoreline pathways were considered to exist. Dose factors, bioaccumulation factors, and shore width factors given in Regulatory Guide 1.109, Rev.1, and in LADTAP were used, as were usage terms for shoreline activities and ingestion of fish and invenebrates. Dose to an individual fishing on the discharge bank was determined by multiplying the annual dose l
calculated with LADTAP by the fractional year the individual spent fishing in the canal.
7 3
I VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 144 OF 156 i
ATTACHMENT 28 j
(Page 4 of 8)
Surry Meteorological, Liquid, and Gaseous Pathway Analysis 2.3 Results For the years 1976,1977,1979,1980, and 1981, the invertebrate pathway resulted in the largest dose. In 1978 the fish pathway'resulted in the largest dose. He maximum exposed member of the public was determined to utilize the James River. he critical age group was the adult and the critical organ was either the thyroid or GI-LLI. The ingestion dose factor, A, in 6.2.3 i
i includes the fish and invertebrate pathways. Ai dose factors were calculated for the total body, thyroid, and GI-LLI organs.
3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose A gaseous effluent pathway analysis was performed to detemiine the location that would result in the maximum doses due to noble gases, for use in demonstrating compliance with 6.3.1.a.
i and 6.3.3.a. The analysis also included a determination of the location, pathway, and critical organ, of the maximum exposed member of the public, as a result of the release of II31,1133, l
tritium, and for all radionuclides in particulate form with half-lives greater than eight days for use in demonstrating compliance with 6.3.4.a. In addition, the analysis included a determination of the critical organ, maximum age group, and sector location of an exposed individual through the inhalation pathway from 1133, 1133, tritium, and particulates to l
demonstrate compliance with 6.3.1.a..
3.2 Data, Parameters, and Methodology Annual average %/Q values were calculated, as described in Section 1 of this attachment, for the nearest site boundary in each directional sector and at other critical locations accessible to the public inside site boundary. The largest X/Q value was determined to be 6.0E-05 sec/m3 at site boundary for ventilation vent releases at a location 499 meters N direction, and 1.0E-06 sec/m3 at site boundary for process vent releases at a location 644 meters S direction. The maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble gases would be at these site boundary locations. The doses from both release points are summed in calculations to calculate total maximum dose.
' VIRGINIA,
VPAP-2103 POWER REVISION 6 PAGE 145 OF 156 ATTACHMENT 28 (Page 5 of 8)
Surry MeWI; Liquid, and Gaseous Pathway Analysis.
l Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations h'
and X/Q values determined for maximum noble gas doses can be used to determine the maximum dose from 1133. 1133, tritium,'and for all radionuclides in particulate form with half-l h
lives greater than 8 days for the inhalation pathway.
The NRC computer code GASPAR," Evaluation of Atmospheric Releases," Revised S/19/77, was run using 1976,1977,1978,1979,1980, and 1981 Surry Power Station gaseous effluent release report data. Doses from 1131. 1133, tritium, and particulates for the inhalation pathway l
were calculated using the 6.0E-05 sec/m3 site boundary %/Q. Except for the source term data and the X/Q value, computer code default parameters were used. Results for each year indicated that the critical age group was the child and the criscal organ was the thyroid for the inhaladon pathway. In 1979, the teen was the critical age group. However, the dose calculated for the teen was only slightly greater than for the child and the doses could be considered equivalent.
The gamma and beta dose factors K vv, L vy, Mivy, and Nivv in Attachment 12 were obtained i
i by performing a units conversion of the appropriate dose factors from Table B-1, Regulatory Guide 1.109, Rev.1, to mrem /yr per Ci/m3 or mrad /yr per Ci/m3, and multiplying by the ventilation vent site boundary %/Q value of 6.0E-05 sec/m3. The same approach was used to calculate the gamma and beta dose factors Kipv, Lipv, Mipy, and Nip, in Attachment 12, using the process vent site boundary X/Q value of 1.0E-06 sec/m3 Inhalation pathway dose factors P vy and Pipv in Attachment 12 were calculated using the i
, equation:
)
P; = K'(BR) DFA;(xiQ)(mrem /yr per Curie /sec)
(28-1) where:
K'
= a constan.t of unit conversion,1E+12 pCi/Ci 3
BR
= the breathing rate of the child age group,3700 m /yr, from Table E-5, Regulatory Guide 1.109, Rev.1 DFAi = the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in ~ mrem /pCi, from Table E-9, Regulatory Guide 1.109, Rev.1 X/Q
= the ventilation vent site boundary X/Q,6 W,-5 sec/m3, or the process vent site boundary X/Q,1.0E-06 se.c/m3, as approy.iate S
VIRGINIA -
VPAP-2103 POWER REVISION 6 PAGE 146 OF 156 ATTACHMENT 28
. (Page 6 of 8)-
Surry Meteorological, Liquid, and Gaseous Pathway Analysis Step 6.3.4.a., requires that the dose to the maximum exposed member of the public from 1131,
_l 1133, tritium, and from all radionuclides in particulate fonn with half-lives greater than 8 days be less than or equal to the specified limits. Dose calculations were perfonned for an exposed i
member of the public within site boundary unrestricted areas, discharge canal bank, and to an exposed member of the public beyond site boundary at real residences with the largest X/Q.
values using the NRC computer code GASPAR. Doses to members of the public were also calculated for the vegetable garden, meat animal, and mill-cow pathways with the largest D/Q-values using the NRC computer code GASPAR.
It was determined that the member of the public within site boundary would be using the
- discharge canal bank for fishing a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year. The maximum annual l
X/O at this location was determined to be 7.8E-05 sec/m3 at 290 meters NW direction. After l
applying a correction for the fractional part of year an individual would be fishing at this location, the dose was calculated to be less than an kiividual would receive at site boundary.
The member of the public receiving the largest / 2i fond site boundary.was determined to be located 5150 meters S sector. The critical pathay was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid. For each year 1976,1977,1978, i
1979,1980 and 1981 the dose to the infant from the grass-cow-milk pathway was greater than
[
the dose to the member of the public within site boundary, nearest residence, vegetable or meat
{
pathways. Therefore, the maximum exposed member of the public was determined to be the l
infant, exposed through the grass-cow milk pathway, critical organ thyroid, at a location 5150 meters S sector. The only other pathway existing at this location for the infant is inhalation.
i l
5 6
i
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VIRGINIA VPAP-2103 POWER REVISION 6 PAGE 147 OF 156 l
ATTACHMENT 28 (Page 7 of 8)
Surry Meteorological, Liquid, and Gaseous Pathway Analysis The RMivy and RMipv dose factors, except for tritium,in Attachment 18 were calculated by multiplying the appropriate D/Q value with the following equation:
MN ff ib RM; =. K aP) F,(6 m ;)
p s + (1 -f f ) e F
-At ps e
ii (28-2)
{
P s
3 where:
a constant of unit conversion,1E+12 pCi/Ci K'
=
cow's consumption rate,50, in Kg/ day (wet weight)
Qp
=
infant milk consumption rate, 330, liters /yr Uap
=
p agricultural productivity by unit area of pasture feed grass,0.7 Kg/m2 Y
=
agricultural productivity by unit area of stored feed,2.0, in Kg/m2 Ys
=
stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109,
[
Fm
=
Rev.I fraction of deposited activity retained on cow's feed grass,1.0 for radiciodine, and l
r
=
0.2 for particulates thyroid ingestion dose factor for the ith radionuclide for the infant, in mrem /pCi, DFLi
=
. from Table E-14. Regulatory Guide 1.109. Rev.1 i
i decay constant for the ith radionuclide, in sec 1, from Table of Isotopes, Lederer, li
=
Hollander, and Perlman, sixth Edition.
Aw decay constant for removal of activity ofleaf and plant surfaces by weathering,
=
5.73E-07 sec-1 (corresponding to a 14 day half-life) j transport time from pasture to cow, to milk, to receptor,1.73+05, in seconds tr
=
transport time from pasture, to harvest, to cow, to milk, to receptor,7.78E406, in l
th
=
seconds fraction of year that cow is on pasture,0.67 (dimensionless),7.78E+06 in seconds f
=
r p
fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensionless fs
=
Parameters used above were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev.l.
l
i VIRGINIA VPAP-2!03 POWER REVISION 6 PAGE 148 OF 156 ATTACHMENT 28 (Page 8 of 8)
Surry Meteorological, Liquid, and Gaseous Pathway Analysis t
Since the concentration of tritium in milk is based on the airborne concentration rather than the l
deposition, the following equation is used
- i RH3 = K'K'"F,QpU,p( Eg3 ) _0.75(0.5/H) X/Q (28-3) where:
l K'" = a constant of unit conversion IE+03 gm/kg absolute humidity of the atmosphere,8.0, gm/m3 H
=
0.75 = the fraction of total feed that is water the ratio of the specific activity of the feed grass to the atmospheric water j
0.5
=
X/Q = the annual average concentration at a location 5150 meters S sector,3.0E-07 sec/m3 for ventilation vent releases, and 1.3E-07 sec/m3 for the process vent releases Other parameters have been previously defined.
The inhalation pathway dose factors RI vv and RIipv in Attachment 18 were calculated using i
the following equation:
RI; = K'(BR)DFA;(x/Q)(mrem /yrperCurie/sec) g where:
K' a constant of unit conversion, IE+12 pCi/Ci
=
breathing rate of the infant age group,1400 m3/yr, from Table E-5, Regulatory BR
=
Guide 1.109, Rev.1 DFAi = thyroid organ inhalation dose factor for infant age group for the ith radionuclide, in mrem /pCi, from Table E-10, Regulatory Guide 1.109, Rev.1 ventilation vent X/Q,3.0E-07 sec/m3, or the process vent site boundary X/Q, X/Q
=
1.3E-07 sec/m3, at a location 5150 meters S sector.
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VIRGINIA VPAP-2103 POWER REVISION 6 -
PAGE 149 OF 156 j
ATTACHMENT 29
/
1 (Page 1 of 8)
North Anna Meteorological, Liquid, and Gaseous Pathway Analysis f
1.0 METEOROLOGICAL ANALYSIS i
1.1 Purpose j
The purpose of the meteorological analysis was to determine the annual average X/Q and D/Q values at critical locations around the Station'for ventilation vent (ground level) and process f
vent (mixed mode) releases. The annual average X/Q and D/Q values were used to perform a j
dose pathway analysis to determine both the maximum exposed individual at site boundary and j
member of the public. The %/Q and D/Q values resulting in the maximum exposures were incorporated into the dose factors in Attachments 13 and 19.
}
1.2 Meteorological Data, Parameters, and Methodology Onsite meteorological data for the period January 1,1981, through December 31,1981, were l
used in calculations. These data included wind speed, wind direction, and differential temperature for the purpose of determining joint frequency distributions fo'r those releases I
characterized as ground level (e.g., ventilation vent), and those characterized as mixed mode i
(i.e., process vent). The portions of release characterized as ground level were based on l
AT 8.9ft-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were f
15 I
based on AT158.9ft-28.2ft and 158.9 ft wind data.
l X/Q's and D/Q's were calculated using the NRC computer code "XOQDOQ - Program for the l
Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,"
September,1977. ne code is based upon a straight line airflow model implementing the assumptions outlined in Section C (excluding Cla and Clb) of Regulatory Guide 1.111, j
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."
f The open terrain adjustment factors were applied to the X/Q values as recommended m -
l Regulatory Guide 1.111. He site region is characterized by gently rolling terrain so open j
terrain correction factors were considered appropriate. The ground level ventilation vent j
release calculations included a building wake correction based on a 1516 m2 containment -
l minimum cross-sectional area.
l l
r
=- -
- ~. _ - -.
e
- n J VIRGINIA VPAP-2103 i
POWER REVISION 6 PAGE 150 OF 156 t
ATTACHMENT 29-(Page 2 of 8)
North Anna Meteorological, Liquid,and Gaseous Pathway Analysis 1
The effective release height used in mixed mode release calculations was based on a process vent release height of 157.5 ft, and plume rise due to momentum for a vent diameter of 3 in.
i with plume exit velocity of 100 ft/sec. Ventilation vent, and vent releases other than from the process vent, are considered ground level as specified in Regulatory Guide 1.111 for release points less than the height of adjacent solid structures. Terrain elevations were obtained from North Anna Power Station Units 1 and 2, Virginia Electric and Power Company Final Safety -
l Analysis Report Table llc.2-8.
X/Q and D/Q values were calculated for the nearest site boundary, resident, milk cow, and
- vegetable garden by sector for process vent and ventilation vent releases at distances specified from North Anna Power Station Annual Environmental Survey Data,for 1981. X/Q values were also calculated for the nearest lake shoreline by sector for the process vent and ventilation vent releases.
l A: cording to the definition for short term in NUREG-0133," Preparation of Radiological i
Effluent Technical Specifications for Nuclear Power Stations," October,1978, some gaseous
[
releases may fit this category, primarily waste gas decay tank releases and containment ptn ges.
However, these releases are considered long term for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past release repons.
Therefore, the use of annual average concentrations is appropriate according to NUREG-0133.
l The X/Q and D/Q values calculated from 1981 meteorological data are comparable to the -
values presented in the North Anna Power Station UFSAR.
1.3 Results E
The X/Q value that resulted in the maximum total body, skin and inhalation exposure for j
ventilation vent releases was 9.3E-06 sec/m3 at a site boundary location 1416 meters SE sector.
For process vent releases, the site boundary X/Q value was 1.2E-06 sec/m at a location 1513 3
meters S sector. The shoreline X/Q value that resulted in the maximum inhalation exposure for I
ventilation vent releases was 1.0E-04 sec/m at a location 274 meters NNE sector. The 3
shoreline X/Q value for process vent was 2.7E-06 sec/m3 at a location 274 meters NNE sector.
n
1 VIRGINIA '.
VPAP-2103 f
POWER '
REVISION 6 PAGE 151 OF 156 i
ATTACHMENT 29'
-(Page 3 of 8) r North Anna Meteorological, Liquid, and Gaseous Pathway Analysis l
Pathway analysis indicated that the maximum exposure from I-131,1133, and from all l
radionuclides in particulate form with half-lives greater than 8 days was through the grass-cow-milk pathway. De D/Q value from ventilation vent releases resulting in the maximum exposure was 2.4E-09 per m2 at a location 3250 meters N sector. For process vent releases, the -
2 D/Q value was 1.lE-09 per m at a location 3250 meters N sector. For tritium, the X/Q value from ventilation vent releases resulting in the maximum exposure for the' milk pathway was
.i 7.2E-07 sec/m3, and 3.9E-07 sec/m3 for process vent releases at a location 3250 meters N sector.
y i
2.0 LIQUID PATHWAY ANALYSIS f
2.1 Purpose l
I The purpose of the liquid pathway analysis was to determine the maximum exposed member of the public in unrestricted areas as a result of radioactive, liquid effluent releases. He analysis includes a determination of most restrictive liquid pathway, most restrictive age group, and I
critical organ. This analysis is required for Sukection 6.2.
i 2.2 Data, Parameters, and Methodology j
Radioactive liquid effluent release data for the years 1979,1980, and 1981 were compiled from the North Anna Power Station semi-annual effluent release reports. The data for each year, along with appropriate si'e specific parameters and default selected parameters, were entered into the NRC computer code LADTAP as described in NUREG-0133.
Re-concentration of effluents using the small lake connected to larger water body model was selected with the appropriate parameters determined from Table 3.5.3.5, Design Data for I
Reservoir and Waste Heat Treatment Facility from Virginia Electric and Power Company, Applicant's Environmental Report Supplement, North Anna Power Station, Units 1 and 2 March 15,1972. Dilution factors for aquatic foods, shoreline, and drinking water were set to one. Transit time calculations were based on average flow rates. 'All other parameters were defaults selected by the LADTAP computer code.
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VIRGINIA VPAP-2103 POWER
. REVISION 6-PAGE 152 OF 156
?
ATTACHMENT 29 (Page 4 of 8) l t
North Anna Meteorological, Liquid, and Gasedus Pathway Analysis 2.3 Results I
For each year, the fish pathway resulted in the largest dose. The critical organ each year was the liver, and the adult and teenage age' groups received the same organ dose. However, since -
f the adult total body dose was greater than the teeri total body dose for each year, the adult was i
. selected as the most restrictive age group. Dose factors in Attachment 7 are for the maximum exposed member of the public, an adult, with the critical organ being the liver.
o 3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose r
A gaseous effluent pathway analysis was performed to determine the location that would result in the maximum doses due to noble gases for use in demonstrating compliance with 6.3.1.a.'
I and 6.3.3.a. The analysis also included a determination of the critical pathway, location of maximum exposed member of the public, and the critical organ for the maximum dose'due to j
1131, 1133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for use in demonstrating compliance with requirements in 6.3.4.a.1. In addition, the analysis included a determination of the critical pathway, maximum age group, and sector
[
location of an exposed individual through the inhalation pathway from 1131, 1133, tritium, and
[
particulates with half-lives greater than 8 days to demonstrate compliance with 6.3.1.a..
l 3.2 Data, Parameters, and Methodology Annual average X/Q values were calculated, as described in Section 1 of this attachment, for the nearest site boundary in each directional sector and at other critical locations beyond the l
site boundary. The largest X/Q value was determined to be 9.3E-06 sec/m3 at site boundary for ventilation vent releases at a location 1416 meters SE direction, and 1.2E-06 sec/m at site 3
boundary for process vent releases at a location 1513 meters S direction. The maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble gases, would be at these site boundary locations. The doses from both release points are summed in calculations to calculate total maximum dose.
I i
r b
\\'-
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n VIRGINIA VPAP-2103 '
POWER REVISION 6 PAGE 153 OF 156 I
ATTACHMENT 29 (Page 5 of 8)
North Anna Meteorological, Liquid, and Gaseous Pathway. Analysis J
Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and X/Q values determined for maximum rioble gas doses can be used to determine th'e maximum dose from 1831, 1833, tritium, and for all radionuclides in particulate form with half-l lives greater than 8 days for the inhalation pathway.
The NRC computer code GASPAR," Evaluation of Atmospheric Releases," Revised 8/19/77, was run using 1979,1980 and 1981 North Anna Power Station Gaseous Effluent Release j
Report data. Doses from 1131, 1133, tritium, and particulates for the inhalation pathway were l
calculated using the 9.3E-06 sec/m3 site boundary %/Q. Except for the source term data and the X/Q value, computer code default parameters were used. Results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway.
f The gamma and beta dose factors K vy, L vy, Mivy,'and N vv in Attachment 13 were obtained i
i i
by performing a units conversion of ute appropriate dose factors from Table B-1, Regulatory Guide 1.109, Rev.1, to mrerrpyi per Ci/m3 or mrad /yr per Ci/m3, and multiplying by the ventilation vent site boundary X/Q value of 9.3E-06 sec/m3. The same approach was used m calculating the gamma and beta dose factors Kipy, L v, Mipy, and Nipv in Attachment 13 using l
ip
.the process vent site boundary X/Q value of 1.2E-06 sec/m3 The inhalation pathway dose factors Pivv and Pipv in Attachment 13 were calculated using the following equation:
l P; = K'(BR) DFA;(x/Q) (mrem /yr per Curie /sec)
(29-1) where:
K' a constant of unit conversion, IE+12 pCi/Ci
]
=
the breathing rate of the child age group,3700 m3/yr, from Table E-5, Regulatory BR
=
Guide 1.109, Rev.1 DFAi = the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in mrem /pCi, from Table E-9, Regulatory Guide 1.109. Rev.1 the ventilation vent site boundary X/Q,9.3E-06 sec/m3, or the process vent site
%/Q
=
boundary X/Q,1.2E-06 sec/m3, as appropriate.
a
t VIRGINIA.
VPAP-2103 POWER -
REVISION 6
. PAGE 154 OF 156 :
r ATTACHMENT 29' (Page 6 of 8)
North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Step 6.3.4.a., requires that the dose to the maximum exposed member of the public from 1333, 1333, tritium, and from all radionuclides in particulate form with half-lives greater than 8 days l
be less than or equal to the specified limits. Dose calculations were performed for an exposed member of the public within site boundary unrestricted areas, and to an exposed member of the public beyond site boundary at locations identified in the North Anna Power Station Annual Environmental Survey Data for 1981.
It was determined that the member of the public within site boundary would be using Lake Anna for recreational purposes a maximum of 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> per year. It is assumed that this member of the public would be located the entire 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> at the lake shoreline with the largest annual %/Q of 1.0E-04 at a location 274 meters NNE sector. De NRC computer code l
G ASPAR was run to calculate the inhalation dose to this individual. The GASPAR results were -
corrected for the fractional year the member of the public would be using the lake.
Using the NRC computer code GASPAR and annual average %/Q and D/Q values obtained as described in Section 1 of this attachment, the member of the public receiving the largest dose beyond site boundary was determined to be located 3250 meters N sector. The critical pathway was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid. For each year 1979,1980, and 1981 the dose to the infant from the grass-cow-milk pathway was greater than the dose to the member of the public within site boundary. Therefore, the maximum exposed member of the public was determined to be the infant, exposed through the grass-cow-milk pathway, critical organ thyroid, at a location 3250 meters N sector.
Pathway analysis results indicate that existing pathways, including ground and inhalation, within five miles of North Anna Power Station, yield R; dose factors less than those determined for the cow milk pathway. Although the cow-milk pathway does not exist within five miles of the Station, NUREG-0133 requires the use of cow-milk R dose factors since these values result i
in the most limiting doses. There is no requirement to include the other pathways.
[ Commitment 3.2.3]
)
i
VIRGINIA VPAP-2103
- POWER REVISION 6 PAGE 155 OF 156 ATTACHMENT 29 (Page 7 of 8)
Noeth Anna Meteorological, Liquid, and Gaseous Pathway Analysis The RM yy and RM;py dose factors, except for tritium,in Attachment 19 were calculated by i
multiplying the appropriate D/Q value with the following equation:
RM. = K Q (URP )
A; + A, Fm (r)(DFL; ) P s + (i _ f f ) e-1A F
ff d t' ps e
i (29-2) i y
y
. P s
where:
K' a constant of unit conversion, IE+12 pCi/Ci
=
QF cow's consumption rate,50, in Kg/ day (wet weight)-
t
=
Uap = infant milk consumption rate,330 liters /yr Yp agricultural productivity by unit area of pasture feed grass,0.7 Kg/m2
=
Ys agricultural productivity by unit area of stored feed,2.0, in Kg/m2
=
Fm stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev. I
=
fraction of deposited activity retained on cow's feed grass,1.0 for radiciodine, and r
=
0.2 for particulates D' L = thyroid ingestion dose factor for the ith radionuclide for the infant, in mrem /pCi, from F i Table E-14, Regulatory Guide 1.109, Rev.1 Ai decay constant for the ith radionuclide, in sec 1, from Table of Isotopes, Lederer,
=
Hollander, and Perlman, sixth Edition.
Aw decay constant for removal of activity ofleaf and plant surfaces by weathering,
=
5.73E-07 sec-1 (corresponding to a 14 day half-life) transport time from pasture to cow, to milk, to receptor,1.73E+05, in seconds tr
=
transport time from pasture, to harvest, to cow, to milk, to receptor,7.78EM6, in th
=
seconds fp fraction of year that cow is on pasture,0.58 (dimensionless),7 months per year from
=
NUREG-0597 fs fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensionless
=
Parameters used in the above equation were obtairied from NUREG-0133 and Regulatory Guide 1.109, Rev.l.
^, _,.
VIRGINIA VPAP-21b3
. POWER REVISION 6 PAGE 156 OF 156 ATTACHMENT 29 (Page 8 of 8)
North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used:
O U (DFLg3 ) }0.75(0.5/H) %/Q '
(29-3)
EH8
- m F ap where:
~
I K"' = a constant of unit conversion IE+03 grAg absolute humidity of the atmosphere,8.0, gm/m3 H
=
l-0.75 = the fraction of total feed that is water the ratio of the specific activity of the feed grass to the atmospheric water 0.5
=
X/Q = the annual average concentration at a location 3250 meters N sector,.7.2E-07 sec/m3 for ventilation vent releases, and 3.9E-07 sec/m3 for the process vent releases Other parameters have been previously defined.
9 4
e
ATTACHMENT 4
MAJOR CHANGES -TO RADIOACTIVE LIOUID.
- GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS 12/94)
(01/94 As required by'the ODCM, Section 6.7.2.a.4, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment.
Supporting information as to the reason (s) for the change (s) and a summary of the 10 CFR 50.59 cvaluation are included, as applicable.
i No major changes to the radioactive gaseous and solid waste treatment systems were made for the time period covered by this report.
10 1
l
ATTACHMENT 5
IMOPERABILITY OF RADIOACTIVE LIOUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION
\\
12/94)
I (01/94 As required by the.ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous offluent monitoring instrumentation is provided in tPis attachment.
No extended periods of inoperability occurred with any of-the Liquid or Gaseous Effluent Monitoring Instrumentation specified in the
- ODCM, I
Attachments 2 and 15, for the time period covered by this report.
l 1
11
ATTACHMENT 6
UNPLANNED RELEASES 12/94)
(01/94 As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.
No unplanned releases, as defined by the criteria presented in the ODCM, Section 6.7.2.a.3, occurred during the time period covered by this report.
12
ATTACHMENT 7
LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/94 12/94)
Gaggggs Effluents:
Required L.L.D.
Typical L.L.D.
Hadloisotone (uCi/ml)
(uCi/ml)
Krypton - 87 1.00E-4 4.43E-8 4.34E-7 KryDton - 88 1.00E-4 7.09E-8 6.28E-7 3.89E-7 Xenon - 133 1.00E-4 4.48E-8 1.51E-6 Xenon - 133m 1.00E-4 1.51E-7 Xenon - 135 1.00E-4 1.79E-8 1.78E-7 Xenon - 135m 1.00E-4 6.84E-8 7.54E-7 1.96E-6 Xenon - 138 1.00E-4 1.64E-7 Iodine - 131 1.00E-12 5.34E 7.59E-14 Manaanese - 54 1.00E-11 3.64E 5.32E-14 Cobalt - 58 1.00E-11 4.05E 5.21E-14 Iron - 59 1.00E-11 7.70E 1.01E-13 Cobalt - 60 1.00E-11 4.93E 1.52E-13 Zinc - 65 1.00E-11 1.01E 1.19E-13 Strontium - 89 1.00E-11 4.00E 5.00E-15 Strontium - 90 1.00E-11 7.00E 1.00E-15 Molybdenum - 99 1.00E-11 2.72E 3.47E-13 Cesium - 134 1.00E-11 5.61E 1.61E-13 Cesium - 137 1.00E-11 4.70E 5.77E-14 Cerium - 141 1.00E-11 4.54E 6.79E-14 Cerium - 144 1.00E-11 2.04E 3.22E-13 Gross Aloha 1.00E-11 6.90E 1.20E-14 1.37E-7 Tritium 1.00E-6 1.12E-7 13 l
f ATTACHMENT 7
LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS 12/94)
(01/94 Liauld Effluents:
Required L.L.D.
Typical L.L.D.
Radioisotope fuC1/nl) fuci/ml) 7.29E-8 Krvoton - 87 1.00E-5 5.93E-8 Krvoton - 88 1.00E-5 8.85E-8 1.16E-7 l
8.83E-8 l
Xenon - 133 1.00E-5 6.08E-8 i
Xenon - 133m 1.00E-5 2_^4E-7 2.69E-7
]
1 Xenon - 135 1.00E-5 2.50E-8 3.14E-8 l
Xenon - 135m 1.00E-5 8.92E-8 1.19E-7 I
Xenon - 138 1.00E-5 2.17E-7 3.41E-7 l
Iodine - 131 1.00E-6 2.63E-8 3.43E-8 3.93E-8 Manaanese - 54 5.00E-7 2.45E-8 8.00E-7 l
Iron - 55 1.00E-6 4.00E-7 l
Cobalt - 58 5.00E-7 2.61E-8 3.25E-8 Iron - 59 5.00E-7 4.85E-8 5.86E-8 Cobalt - 60 5.00E-7 2.86E-8 8.43E-8 Zinc - 65 5.00E-7 5.81E-8 6.83E-8 Strontium - 89 5.00E-8 3.00E-8 5.00E-8 Strontium - 90 5.00E-8 5.00E-9 1.00E-8 2.31E-7 Molybdenum - 99 5.00E-7 1.82E-7 Cesium - 134 5.00E-7 3.59E-8 1.00E-7 Cesium - 137 5.00E-7 3.32E-8 3.79E-8 Cerium - 141 5.00E-7 4.07E-8 5.47E-8 Cerium - 144 5.00E-7 1.81E-7 2.63E-7 Gross Aloha 1.00E-7 2.15E-8 3.72E-8 Tritium 1.00E-5 2.78E-6 3.32E-6 14
____ _