ML20092M906
| ML20092M906 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 09/01/1991 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20092M848 | List: |
| References | |
| VPAP-2103, NUDOCS 9202280223 | |
| Download: ML20092M906 (119) | |
Text
11 FORMAT l0N ONLY nU 9
Station Administrative Procedure VIRGINIA POWER
Title:
Offsite Dose Calculation Manual Lead Department: Radiological Protection Procedure Number Revision Number Effective Date V P AP-2103 2
j 09/01/91 Revision Summary:
, dded a tab to Anachment 1, table step 1 (b) on page 43 between "(b)" and "Radwaste."
Revised Attachment 23, item 3 on psge 87 to read " Samples from 3 locations: a) I sample upstream, b) 1 sample downstream, c) Isample from cooling lagoon." Delete " Sample off p
upstream, downstream and cooling lagoon" from the Collection Frequency column.
Revise Attachment 23, on page 96 to change the 1.ocation, Station No., Distance, and Direction
\\
of the surface water and aquatic sediment sample points for the Lake Atma (upstream) sample location to change it to" North Anna River, Rt 669 Bridge (Brook's Bridge)","WhTV", and "12.9." This change is to resolve QA Audit 9103-OBS 08N.
Surry Power Station North Anna PowerStation Approved by:
Approved by:
HW
&lGf*l W0.1
? r.
- t SNSOC Chairman Date SNSOC Chairman Date' Approved 15k:
npproved by:
A ff/Ik/
l
/??
,42 ~
'/ Date
~
$tation Manager Date O
Jeftiojf&lanager Approved by:
/C f
!9/
Vice President-Nuclear Operations
' Date '
9202290223 920221 l
DR ADOCK 0500 0
l "t
VIRGINIA VI'Al'-2103 POWER ltliVISION 2 l'AGli 2 01: 119 TAllt,E Ol' CON I1.NTS Strtion l'are 1.0 l'Ultl'OSE 5
2.0 SCOl'E 5
3.0 1(El EltENCluCOMollTMENT I)OCUMI'NTS 5
4.0 del?iNITIONS 7
5.0 1(ESl'ONSilill,lTIES 10 6.0 INSTitUCTIONS 11 6.1 Sampling and Monitoring Criteria 11 6-6.2 1.lquid Itadioactive Waste Effluents 11 6.2.1 Liquid liffluents Concentration Limitations 1I 6.2.2 Liquid Monitoring Instnunentation 12 6.2.3 Liquid lif0uent Dose Limit 16 6.2.4 1.iquid Radwaste Treatment 19 6.2.5 Liquid Sampling 21 6.3 Gaseous Itadioactive Waste Effluents 21 6.3.1 Gaseous Ef0uent Dose Rate Limitation 21 6.3.2 Gaseous Monitoring Instnunentation 23 6.3.3 Noble Gas lif0uent Air Dose Limit 26 6.3.4 1 131.113. and Radionuclides in Paniculate i orm E10uent Dose 28 k)
Limit
{
6.3.5 Gaseous Radwaste Tieatment 31 6.4 Total Dose 1,imit to l'uhlic From Uranium I?uel C cle Sources 33 3
6.5 Itadiological Environmental Monitoring 34 6.5.1 Monitoring Program 34 6.9.2 Land Use Census 35 6.5.3 Interlaboratory Ccmparison Program 36
/
V:RGINIA VPAP-2103 POWER REVISION 2 PAGE 3 OF 119 TAlli.E OF CONTENTS
{
Section Pap 6.6 Reporting Requirernents 38 6.6.1 Annual Radiological Environinental Operating Report 38 6.6.2 Semiannual Radioactive Effluent Release Report 39 6.6.3 Annual Meteorological Data 40 6.6.4 Changes to the ODCM 40 7.0 RECORDS 42 ATTACllhlENTS I Surry Radioactive I.lquid Effluent Stonitoring Instrumentation 43 2 North Anna Radioactive I.lquid Efnuent Alonitoring 44 Instrumentation 3 Surry Radioactive 1.iquid Efnuent Alonitoring Instrumentation 46 Surteillance Requirements 4 North Anna Radioactive 1.iquid Efnuent Monitoring 47 Instrumentation Surveillance Requirements 5 i.lquid Ingestion Pathwa3 Dose Factors for Surry Station 49 6 North Anna I.lquid Ingestion Pathway Dose Factor Calculatlun 50 7 NAPS I.lquid Ingestion Pathway Dose Commitment Factors for 54 Adults 8 Surry Radioactivo 1.iquid Waste Sampling and Analysis Program 55 9 North Anna Radioactive 1.iquid Waste Sampling and Anal sis 58 3
Program 10 Surry Radioactive Gaseous Waste Sampling and Analysis Program 61 1I North Anna Radioactive Gaseous Waste Sampling and Analysis 65 Program 12 Gaseous Einuent Dose Factors for Surry Power Station 68 13 Gaseous Efnuent Dose Factors for North Anna Power Station 71 14 Surry Radioactive Gaseous Efnuent Monitoring Instrumentation
'4 15 North Anna Radioactive Gaseous Efnuent Monitoring 76 Instrumentation
. _ _. ~. _ _ - _ _ _ _ _...., _ _ _. _, _ -
VIRGINIA VPAP 2103 10WER REVISION 2 PAGE 4 OF 119 l
i
)
f TAlli.E OF CONTENTS SectMn Page ATTACilMENTS (Continued) 16 Surry Radioactive Gaseous Elfluent hionitoring Instrumentation 78 Surveillance Requirements 17 North Anna-Radioactive Gaseous Effluent Monitoring 79 l
Instrumentation Surveillance Requirements 18 Critical' Organ and Inhalation 1)ose Factors for Surry 81 19 Critical Organ 1)ose Factors for North-Anna 83 2
20 Surry Radiological Ensironmental Monitoring Program-84 3
21 North Anna Rs.diological Environmental Monitoring Program 86 j
22 Shrry Environmental Sampling 1.ocations 90 23 North Anna Environmental Sampling 1.ocations 94 j
24 I)etection Capabilities for Surry Station Environmental Sample 98 Analysis
- 25. Detection Capabilities for North Anna Station Environmental 100 l
Sample Analysis 26 Reporting 1.evels for Radioactivity Concentration in 102 i
Environmental Samples at Surry Station 27 Reporting 1.evels for Radioaciliity Concentration in 103 Ensironmental Samples at North Anna Station 28 Surry-Aleleurological,1.lquid and Gaseous Pathway Analysis 104-29. North Anna Meteorologleal, I.lquid and Gaseous Pathway Analysis 112 l
3 r
l.-'
l l
\\
r
-w-Ew,w-- m-=ww e*.
.-e-v
-.. mw
--y + -- e w- - t w r -- e ' r wmew+ we m e ' +
.'..--e,-4
= -,. - -e
- -a 4
+., -.. _ -
..,.,y wy,.
.,,. -... - ~
.w,,,,e,.mr
VIRGINIA VPAP-2103 POWi!R kliVISION 2 PAGli 5 OF 119 1.0 PilHPOSE The Offsite Dose Calculation Manual (ODCN1) establishes the requirements of the Radioactive Ef0uent and Radiological Environmental hionitoring Programs. Methodolqv and parameteis are provided for calculation of offsite doses resulting from radioactive pascous and liquid elfluents, for gaseous and liquid effluent monitming alarnt' trip setpoints, and for conduct of the Environmc,tal Monitoring Program. Requirements are established for the Annual Radiological Environmental Operating Report and the Semi Annual Radioactive Efiluent Release Report required by Station technical specifications. Calculation of of fsite doses due to radioactive liquid and pascous efuwnts are performed to auure that:
+ Concentration of radioactive liquid ef0uents to the unrestricted area will be limited to the
-levels of 10 CFR 20, Appendix 11. Table 11, column 2 for radionuclides other than dissolved or entrained noble gases
- Exposure to the maximum exposed memler of the public m the umestricted area from radioactive liquid efikents will nc.. tesult in doses greater than the liquid dose limits of 10 CFR 50, Appendix 1
- Dose rate at and Ivyond the site loundary from radioactive gaseous ef nuents will be limited to the annual dose rate limits of 10 CFR 20
- Exposure from radioactive gaseous ef 0uents to the masimum exposed member of the public l
in the umestricted area will not result in doses greater than the pascous dose limits of 10 CFR 50, Appendix 1, and
. Exposure to the maximum exposed memtwr of the public will not exceed 40 CFR 190 dose i
i limits 2.0 SCOPE i
This procedure applies to the Radioactive Efnuent and Environmental Monitoring Programs at Surry and North Anna Stations.
3.0 REFERENCES
/ COMMITS 1ENT DOCUMENTS 3.1 References 3.1.1 10 CFR 20, Standards for Protection Against Radiation 3.1.2 10 CFR 50, Domestic 1.icensing of Production and Utilituion Facilities l
3.1.3 40 CFR 190, Environmental Radiation Protectic a Standards for Nuclear Power l
Operations vv-4 y=y.g N y ezz--c %.--.e
+ys wyma.y.M.9g-i g s ya e ppy-c ww
x m m-VIRGINIA V?'V >!
POWiiR ME W% :
o c/Onno 3.1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites 3.1.5 Regulatory Guide 1.21, Nicasuring,livaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive hiaterials in Liquid and Gaseous littluents from Light-Water Cooled Nucicar Power Plants, Rev. I, U.S. NRC, June 1974 3.1.6 Regulatory Guide 1.109, Calculation of Annual Doses to Nian 1: rom Routine Releases of Reactor lif fluents for the Purpose of Evaluating Compliance With 10 Cl R 50, Appendis I, Rev.1 U.S. NRC, Octoter 1977 3.1.7 Regulatory Guide 1.111, hiethods for Estimating Atmosphetic Transport and Disivision of Gaseous Etfluents in Routine Releases from Light-Water Cooled Reactors Rev, I. U.S. NRC, July 1977 3.1.8 Surry and North Anna Technical Specifications (Units 1 and 21 3.1.9 NUREG 0324, XOQDOQ,l'iogram for the hieteorological livaluation of Routiae Elfluent Releases at Nuclear Power Stations, U.S. NRC, September 1977
- 3. i.10 NUREG/CR-1276, Users hianual for the LADTAP 11 Program, U.S. NRC, hiay,19h3 3.1.11 NUREG 0597 User's Guide to GASPAR Code U.S. NRC, June,1980 3.1.12 Radiological Assessm-nt liranch Technical Position on Emironmental N1onitoring, November,1979, Rev. I 3.1.13 NUREG.0133, Preparation of Radiologicallif0uent Technical Specifications for Nuclear Power Stations, October,1978 3.1,14 NURiiG-0543, February 1980, hiethods for Demonstrating 1.WR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 3.1.15 NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressutired Water Reactors, Rev. 3, h1 arch 1982 3.1.16 Environmental hicasurements Laboratory, DOli iI ASL 300 hianual 3.1.17 NRC Generic troer 89-01, Implementation of thogrammatic Controls for Radiological liftluent Technical Specifications (RiiTS) in the Administrative Controls Section of the Technical Specifications and the Relocation of Piocedural Details of RETS to the Of fsite Dose Calculation h1anual or to the Process Control Program 3.1.18 UFS AR (Surry and North Anna) 3.1.19 Nuclear Reactor Environmental Radiation hionitoring Qua'ity Control hianual, IWL-0032-361 3.1.20 VPAP-2802, Notifications and Reports pey, t 3,2 Cominitment Documents 3.2,1 Quality Assurance Audit Report Number C 90 22, Nianagement Safety Review Rev.1 Committee, Observation 03C, January 17,1991 3.2.2 Quality Assurance Audit Report Number 91-03,0bsersation 0hN
VIRGINIA VPAp 2103
. POWi!R RI? VISION 2 PAGli 7 OF 119 i
4.0 DEFINITIONS Rev.1 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 includes the Channel Functional Test. The Channel Calibration can be performed by any series of sequential, overlapping or total channel steps so the entire channel is calibrated.
4.2 Channel Check A qualitative assessment, by observation, of channel behavior during operation. 'lhis assessment includes, where possible, comparison of the channel inditation and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
4.3 Channel Functional Test There are two types of Channel Functional Tests.
4.3.1 Analog Channels injection of a simulated signalinto a channel as close to the sensor as practicable to verify Operability, including alarm and/or trip functions.
4.3.2 Ilhtable Channels injection of a simulated signal into a sensor to verify Operability, including alarm and/or trip functions.
4.4 Duse Equivalent I.131 That concentration of 1 131 (microcurie /grano which alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131,1-132,1 133,1-134 and 1 135, actually present. Thyroid dose conversion factors used for this calculation are listed in 'uble ill of TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites. Tayroid dov-conversion factors from NRC Regulatory Guide 1.109, Revision 1, may be used (Surry).
w
.r
--s
.we---evy,v.
mww-.<re-r-.-
e,
m,,-
--,,5,-.y-....
y 9-vww m-e
,w--,---e,-w.--s*,r rr-v,-s,_,
VI'AP-2103 VlltGINlA Rl! VISION 2 I U W illi PAGli 8 01: 119 4.5 Frequency Notations NOTE: licquencies are allowed a maximum extension of 25 percent.
NOTATION IRI.UUENCY 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 SA Semi annually At least once per 184 days R - Refueling At least once per 18 months S/U Startup Prior to each reactor stanup P Prior to release Comtileted piior to each release N.A. - Not applicable Not applicabie 4.6
(;aseous 1(adwaste Treatment S3 stem A system that reduces radioactise gaseous ef 0uents by collecting primary coolant system offpases froin the primary system and provida delay or holdup to reduce total radioactivity prior to release to the environment. The system comprises the waste pas decay tanks, tegenerative heat exchanger, w aste pas charcoal filters, process vent blowers, waste gas surge tanks, and waste pas diaphragm compressor (North Anna).
4,7 (ieneral Nomenclatuce x = Chi: concentration at a point at a given instant (cuties per cubic meter)
D=
Deposition: quantity of deposited radioactive material per unit area (curies per squate meter)
Q = Source strength (instantaneous; grams, curies) limission rate (continuous; grams per sceond, euries per secondf
=
limission rate (continuous line source; grams per second per meter) e 4.8 1.uwer 1.imit of Detection (1.1.0)
The smallest concentration of radioactive material in a sample that will yield a net count (above Rev.I system background) that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
VlltOINIA VI'AP 21(13 l'O W illt Iti!YlSION 2 PAGli 9 01; 119 4.9 Members of the l'uhlic Individuals who, by sittue of their occupational status, have no f ormal asweiation with the Station. This catepoiy includes non-employees of Viipinia Power w ho are permitted to use portions of the site for recreational, occupational, or other purposes not awociated with Station f unctioll% This category does not include non employees stich as vt iding machine servicemen or postmen who, as p ut of their fonnal job function, occasionally enter an area that is controlled by Virginia Power for putposes of protection of individuals f rom esposuie to ladiation and radioactive materials.
4.10 Operable Operability A system, subsystem, train, component or des ice is opeiable or has operability w hen it is capable of perfonning its specified iunctions and all necessary, attendant insuumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are requited for the system, subsystem, train, component, of device to perform its functions are also capable of performing their related suppott functions.
4.1 I l' urge - Purging Controlled disthange of ali or pas from a confinement to inaintain temperatuie, pressuie, humidity, concentration or other operating condition, so that replacement air or pas is required to purify the confinement.
4.12 Rated Thermal Power Total reactor core heat 'ransf er rate to reactor coolant.
. Surry:
2441 Megawatt Thermal (MWI)
. North Anna:
2893 M Wt 4.13 Site lloundar,)
The line beyond w hich Virginia Power does not ou n sease, o stherw ise control the land.
4.14 Source Check A qualitatise assessment of channel response v hen the thannel senwr is esposed to radiation.
This applies to installed radiation monitoring systems.
- 4. I 5 Special 1(eport A report to the NRC to comply with Subsection (i,2,6.3, or h4 of this procedute.
Rev.1 i
~ _..
...~-.-a-VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 10 OF 119 4.16 Thermni Power Total reactor core heat transfer rate to the reactor coolant.
4.17 Unrestricted Area Any area at or beyond the site boundary where access is not 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.
4.1 M Ventilation Exhnust Treatment System A system th, t ieduces pascous radioindine or radioactive material in paiticulate form in effluents by }.assing ventilation or vent exhaust gases through charcoal adsorbers and liigh Ef0ciency Particulate Adsorber (llEPA) filters to remove lodines and particulates fiom a gaseous exhaust stream prior to release to the environment (such a system is not considered to have any effect on noble pas ef0uents). Engineered Safety Feature (ESP) atmospheric cleanup systems are not Ventilation Exhaust Treatment System components.
5.0 RESPONSillli,lTIES 5.1 Radiological Protection
. Rev.1 Radiological Protection is tesponsible for:
5.1.1 Establishing and maintaining pacedures for surveying, sampling, and monitoring radioactive ef0uents and the environment 5.1.2 Surveying, sampling, and analyzing plant efnuents and environmental monitoring, and documenting these activities.
5.1.3 Analyzing plant effluent trends and recommending actions to coneet adverse trends.
5.1.4 Preparing Ef0uent and Environmental Monitoring Program records.
5.2 Operations Department The Operationa Department is responsible for requesting samples, analysis, and authorization to release effluents.
VIRGINIA VPAP-2103 POWi!R RiiVISION 2 PAGli 11 OF 1 a 6.0 INSTI(UCTIONS NOTI:: Metectological, liquid and gaseous pathway analyses are presented in Attaciunents 28 and 29, Meteorological,l.iquid and Gaseous Pathway Analysis.
6.1 Sampling and Monitoring Criteria 6.1.1 Surveys, sampling, and analyses shall use instruments calibrated for the type and tange of radiation monkored and the type of discharge 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 awess the status of the discharge monitored.
6,1.4 Samples shall tv representative of the volume and type of discharge monitored.
6.1.5 Sun eys, sampling, analyses, and monitoring records shall be accurately and icpibly documented, and sulticiently detailed so that the meaning and intera of the records are clear.
6.1.6 Surveys, analyses, and monitoring records shall be reviewed for trends, completeness, and accuracy.
6.2 1.lquid 1(adioactise Waste Effluents 6.2.1 1.iquid Elfluent Conuntration 1. imitations
- a. Liquid waste concentrations discharged from the Station shall not exceed the following limits:
- 1. For radionuclides (other than dissolved or entrained noble pases), liquid
^
elfluent concentrations teleased to unrestricted areas shall not escred those specified in 10 CFR 20, Appendix 11, Table 11, Column 2.
- 2. For dissolved or entrained noble pases, concentrations shall not exceed 2E-4 pCi/ml.
- b. If the concentration of liquid einucats exceed above limits in 6.2.1.a promptly reduce concentrations to within lim >;
VIRGINIA VPAl' 2103 IOWiiR RiiVISION 2 PAGli 12 OF 119
- c. Daily concentrations of radioactive materials in liquid waste scleased to untestricted areas shall meet the following:
Volume of Waste Discharced + Volume of Dilution Water 3
g)
Volume of Waste Discharged x Nb,'h Miti a
u here:
pCi/ml, = the concentration of nuclide iin the liquid tinuent disharge:
M PC, the maximum permissible concenuation in unrestricted areas of
=
nuclide, i, expressed as pCi/mi from 10 CFR 20, Appendix II, Table
- 11. for radionuclides other than noble pases, and 21?-4 pCi/mi for dissolved or entrained noble pases 6.2.2 1.iquid Stonitoring Instrumentation
- a. Radioactive 1.lquid l'inuent Stonitoring Instrutnentation Radioactive liquid effluent monitoring instrumentatio i channels shown on Attachments 1 and 2, Radioactive Liquid lif0uent Monitoring Instrumentation, shall be operable with their alami/ trip setpoints set to ensure that limits of 6.2.1.a 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 following:
- Promptly suspend release of radioactise liquid ef0uents monitored by the affected channel
. Dechtte the channel inoperable a Change the setpoint to an acceptable, conservative value i
l l
l
l VIRGINIA VFAl'.2103 POWER RiiVISION 2 PAGli 13 OF l19
- b. Rndioactise 1.lquid Effluent Stonitoring instrumentation Operability
!!ach radioactive liquid effluent monitoring instiumentation channel shall le demonsuated operable by [vrfonning a Channel Check, Source Check, Channel Calibration and Channel Functional Test at the ficquencies shown in Attachments 3 and.1, Radioactive 1.iquid liffluent Monitoring Imtrumentation Surveillance Requirements.
- 1. If the numter of operable channels is less than the minimum required by the tables in Attachment I or 2, perform the action shown in these tables.
- 2. Attempt to retum the instruments to operable status within 30 days. If unsuccessful, explain in the next Semiannual Radioactive fitfluent Release Report w hy the inoperability w as not corrected in a timely manner,
- c. Applicable Monitors Liquid effluent monitors for which alann/ rip setpoints shall be detennined are:
Rev.1 t
instruinent Number Release Point North Annn Surry Liquid Radwaste Elfluent Line I.W.111 LW 108 Service Water System liffluent I ine SW-108 SW.107 A.II,C,D Rey,1 Condenser Circulating Water Line SW-130, SW.230. SW-120, SW 220 Radwaste Facility liffluent Line -
N/A RRM 131 Rev.1
- ~.
VIRGINIA VPAP-2103 POWER Hl! VISION 2 PAGE 14 OF 119
- d. Selpoint Calculatlun NOTE: This methodology does not preclude use of more conservative setpoints.
- 1. hiaximtun setpoint values shall be calculated by:
c=
[
(2) where:
c = the setpoint,in HCihul, of the radioactivity monitor measuring the 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 pCihnt; f = the flow setpoint as measured at the radiation monitor location.GPM:
F = dilution water flow calculated as:
(Surry) F = f + (200,0(4) GPM x Number of Cire. Pumps in Service)
(N. Anna) F = f + (218,00() 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) tecomes:
c=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 (Surry: 1,W 108, North Anna: LW-111), the service water system effluent line (Surry: SW-107 A, H C, and D, North Anna:
Rev.1 SW-108), and the Radwaste Facility efiluent line (Surry: RRM 131).
L
' VIRGINIA Yl'AF-2103 IOWi!R RliVISION 2 r
l'AGli 15 0F 119 i
- 4. For the liquid radwaste efuuent line, Ik uation (2) tecomes; i
l E
ea (4) where:
K,w = 'the fraction of the efuuent concentration limit, used to implement i
10 CFR 20 for the site, attributable to the liquid radwas'c effluent line pathway.
- 5. For the service water system efnuent line, Equation (2)lycomes:
E c=-
(6) where:
K w - The fraction of the effluent concentration limit, used to implement 10 3
CFR 20 for the Station, attributable to the scivice water effluent line pathway.
- 6. For the Radwaste Facility efuuent line,lk uation (2) trcomes:
l C
ag e=
(3) where:
Kgw = The fraction of the cf fluent concentration limit, used to implement Rev.I 10 CFR 20 attributable to the Radwaste Facility efuuent line pathway.
- 7. The sum K.w + Ksw + K w shall not le greater than 1.0.
t R
1 I
I.
w L-.
~
VIRGINIA VPAP 2103 l'OWER RiiVISION 2 PAGE 16 OP 119 6.2.3 1.lquid Effluent Dose 1.imit
- a. Requirement At least once per 31 days, perfonn the dose calculation in 6.2.3.c and 6.2.3.d to ensure the dose or dose conunitment to the nmimum exposed memler 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 tuly
. 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 Rev.1 identifies causes for exceeding limits and defines conective actions taken to reduce releases of radioactive materials in liquid effluents to ensure that subsequent releases will tv in compliance with the above limits.
VIRGINIA VPAP.2103 10WiiR Rl! VISION 2 PAGl! 17 OF 119
- c. Surry Duse Contribution Calculations NOTE: 'lhyroid and G1 1.1.1 organ doses must le calculatni to detennine w hich is the critical organ for the period being considered.
Dose contributions shall le calculated for all radionuclides identified in liquid effluents released to unresuicted areas based on the equation:
D = t FM { CI AI (6) w here:
Subscripts = ni, refers to the total body dose (see Ikpiation (10))
0, refers to the organ dose (see liquation (11))
Rev.1 i, refers to individual radionuclide D=
the cumulative dose conunitment to the total txxty or critical organ fmm the liquid effluents for the time period t, in mrem the length of the time period over which C and F are averaged for allliquid t
=
i releases, hours M=
the mixing ratio (recipioeal of the dilution factor) at the point of exposure, dimensionless 0.2 from Appendix 11 A, Surry UFS AR F = the near field average dilution factor for C, duiing any liquid efDuent release; the ratio of the average undiluted liquid waste flow during release to the average flow fr.au the site discharge structure to unrestricted areas C=
the average concentration of radionuclide, i, in undiluted liquid ef 0uent i
during time period, t, from all liquid releases, in pCi/ml l
l l
l
1 VIRGINIA YPAP-2103 i
IOWIIR Rl! VISION 2 i
PAGE 18 OF 119 A, = the site related ingestion dose commitment factor to the totallxxty or critical
{
organ of an adult for eat h identified principal ganuna and beta emitter in mrem ml per hr-pci. Values for Ai are given in Attachment 5, Liquid Ingestion Pathway Dose Factors For Suny Power Station.
A,= 1.14 I?405 (21IIF + Sill,) DF, (7) i w heic:
1.14 li405 = 1 I?+06 pCi/pCi x 1 E+03 ml/kg + 8760 hr/yr, units conversion factor 21
= adult fish consumption, kg/yr. from NURl!G-0133 5
= adult invertebrate consumption, Kg/yr, from NURl!G 0133 lil
= the bioaccumulation factor for nuclide,i,in inveitebrates, pCi/kg i
per pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev.1 i
ilF; = the bioaccumulation factor for nuclide,i,in fish, pCi/kg per pCi/l, j
from Table A 1 of Re alatory Guide 1,109 Rev.1 DF, = the critical organ dose conversion factor for nuclide, i, for adults, in nuenVpCi, from Table E lI of Regulatory Guide 1.109, Rev, I d, North Anna Dose Contribution Calculations I
NOTE: Attachment 6, Nonh Anna Liquid Ingestion Pathway Dose Factor Calculation provides the derivation for I?quation (8).
i Dose contribution shall be calculated for a!! radionuelides identified in liquid effluents released to unrest 1icted areas based on:
1 D = EQi x Ili (8)
Whese:
Subscripts TB, refers to the total body dose (see Equation (10))
=
l 0, refers to the organ dose (see Equation (1 !))
Rev.1 l
1, refers to individual radionuclide D = the cumulative dose commitment to the total lxxty or critical organ from the liquid effluents for the time period t, in miem
VIRGINIA ypAP 2103 POWi!R Rl! VISION 2 PAGl: 19 OF i19 Ili = Dose Commitment Factors (mrent Ci) for adults. Values for Il are
/
i provided in Attaciunent 7, North Anna Liquid Ingestion Pathway Dose Conunitment Factors for Adults Q, = Total released activity for the comidered time period and the ith nuclide Qi = t x C x Waste Flow (9) i Where:
t
= the length of time over which C, and F are averaged for allliquid seleases, hours C; = the average concentration of radionuclide,i,in undiluted liquid effluent during time period, t, from any liquid icleases,in pCihnl
- e. Quarterly Cornposite Anal ses 3
For radionuclides not detennined in each batch or weekly composite, dose contribution to current monthly or calendar quarter cumulative sununation may !.e approximated by assuming an ave..ipe monthly concentration based on previous monthly or quarterly composite analyses, llowever, for reporting purposes calculated dose contribution shall be based on the actual composite analyses.
6.2.4 1.lquid Radwaste Treatment a Requirement
- 1. The Liquid Radwaste Treatment System and/or the Surry Radwaste Facility Rev,1 Liquid Waste System shall tc used to reduce the radioactive materials in liquid waste prior to discharge w hen projected dose due to liquid efnuent, from each reactor unit, to unrestricted areas would exceed 0.06 mrem to total baiy or 0.2 mrern to the ciitical organ in a 31 day period.
2 Doses due to liquid releases shall be projected at least once per 31 days.
l
VIRGINIA VPAP 2103 POWEH Rl! VISION 2 PAGE 20 OF i19
- b. Action if radioactis e liquid waste is discharge.1 without treatment and in escess of the above limits, within 30 days, prepare and submit to the NRC, a special report in Rev.I accordance with YPAP 2802, Notificatiois and Repons, that includes the following:
- 1. An explanation of w hy liquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-system, and the reason for the inoperability.
- 2. Actiom taken to restore inoperable equipment to operable status.
- 3. Summary desenption of actions taken to pievent a recunence,
- c. Projected Total llod,t 1)ose Uniculation
- 1. Detennine Dra, the total body dose from liquid ef0uents in the pievious 31 day period, per Equation (6) or (H) (Surry and North Anna, respectively).
- 2. Estimate R, the ratio of the estimated volume of liquid ef0uent releases in :he i
present 31 day period to the volume released in the previous 31-day period.
- 3. Estimate F, the ratio of the estimated liquid ef3uent radioactivity in the present i
31-day period to liquid effluent activity in the previr>us 31-day period (pCi/ml).
- 4. Determine PDra, the projected total ludy dose in a 31-day perimi.
PDrn = Dra (R F )
(10) i i
- d. Projected Critical Organ 1)ose Calculation llistorical data pertaining to the volumes and radioactivity of liquid ef0uents released in connection a4 -occific Station functions, such as maintenance or refueling outages, shall be used in projections as appropriate.
- 1. Determine D, the critical organ dose from liquid ef 0uents in the previous o
31-day period, per Equation (6) or (8)(Surry and North Anna, respectively),
- 2. Estimate R as in 6.2.4.c.2.
i
- 3. Estimate F as in 6.2.4.c.3.
i 4, Determine PD = projected critical organ dose in a 31-day period, o
PD = D (R F )
(1l) o o
i i
VIRGINIA VPAl' 2103 IOWl?R RiiVISION 2 PAGli 21 OF i19 6.2,5 1.lquid Sampling Radioactive liquid wastes shall be sampled and analyicd according to the sampling and analysis requirenwnts shown in Attachments 8 and 9. Radioactive IJyuid Waste Sampling and Analysis Program (Surry and North Anna, respectively).
6.3 Gaseous Radioactive Waste l',filuents 6.3.1 Gnscous 1:filuent Dose Hate 1. imitation
- a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and leyond the site boundary shallle limited to the following:
- 1. The dose rate limit for noble gases shall be s 500 nuenvyear to the total body and 5 3(XXI mrenvyear to the skin.
2, The dose rate limit for 1 131, for tritium, and for all radioactive materials in particulate form with half lives greater than 8 days shall be s 1500 nuenVyear to the crideal organ,
- b. Action i
1, if dose rates exceed the above limits, promptly decrease the release rate to within the above limits.
- 2. Dose rates due to noble gases in gaseous effluents shall be determined, continuously, 'o be within the limits specified in 6.3.1.a.
3 Dose rates due to 1 131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents shall be determined to tv within the above limits by obtaining representative samples and performing
- analyses in accordance with the sampling and analysis program specified on Attachments 10 and 11, Radioactive Gaseous Waste Sampling and Analysis Program.
VIRGINIA VPAP-2103 POWi!R Rl! VISION 2 PAGli 22 01: 119
- c. Calculallons of Gaseous I lfluent Dose Rates
- 1. The dose rate limit for noble gases shall tv determined to be within the limit by limiting the telease rate to the lessor of:
- E lKivv hivv + Kipv hyivl s 5(K)mrenvyt to the total tudy (12) i or.
(L v + 1.1hiipv) hq,vl s 3(W10 mrenVyr (13) 1.1hi vv) hivy 4
- E ((Livy +
i ip to the skin where:
Subscripts = vv, refers to vent releases from the building ventilation vent Rey,1 including Radwaste Facility Ventilation Vent:
py, icfers to the vent releases from the process vent; 1, icfet s to individual radionuclide Kivv. Kipv = The total body dose factor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide, i,in mrenvyt per Curie /sec. Factors are listed in Attachments 12 and 13, Gaseous lif fluent Dose I actors (Surry and North Anna, respectively)
- 1. ivy,Lipv = lhe skin dose factor for ventilation vents or process vent 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 hiivy, hiipv = 'the air dose factor for ventilation vents or procen vent release due to gamma emissions for each identified noble pas radionuclide, i, in mrad /yr per Curichec. Factors are listed in Attachments 12 and 13 D,vy, h,py = 1he release rate for ventilation vents or process vent of noble gas radionuclide, i, in gaseous effluents in Curie /see (per site) 1,1
= The unit conversion factor that converts air dose to skin dose, in mrenVmrad
VIRGINIA VPAP 2103 l'OWER Rl! VISION 2 PAGl! 23 OF 119
- 2. 'lhe dose rate limit for I 131, for tritium, and for all radionuclides in pasticulate fonn with half lives greates than 8 days, sha'l be detennined to Iw within the limit by restricting the release rate to:
EIPivvhivv+Pipv hq,v] s 1500 mrem /yr to the critical organ (14) i where:
F yy, Pipv = Ihe critical organ dose factor for ventilation vents or process i
vent for 1 131,113, and all radionuclides in particulate form with half lives greater than 8 days for the inhalation pathway, in mrem /yr per Cuiie/sec. Factors are listed in Attachments 12 and 13 h,vy,h,pv
'the release rate for ventilation vents or process vent of I-131,
=
113, and all radionuclides, i, in paniculate fonn with half lives greater than 8 days in gaseous effluents in Curie /see (per site)
- 3. All gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qvy.
l 6.3.2 Gaseous Monitoring Instrumentullon
- a. Requirement
- 1. The radioactive gaseous effluent monitoring instrumentation channels shown in 4 or 15, Radioactive Gaseous Efiluent Monitoring Instrumentation, shall be operable with alarnVtrip setpoints set to ensure that limits specified for noble gases in 6.3.1.a are not exceeded. Alarm / trip r
setpoints of these channels shall be determined and adjiisted in accordance with 6.3.2.d.
- 2. Each radioactive gaseous effluent monitoring instrumentation channel 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.
- _. _ _. _ _ -., _.. _ _. _. _. _ _. _. _ _ - _.~
~
VIRGINIA VPAP-2103 POWiiR Rl! VISION 2 l'AGli 24 OF 119
- b. Action
- 1. If a tadioactive pascous effluent monitoring instrumentatioa chann-1 alamt trip
/
setpoint is less conservatis e than required by 6.2.2.a. promptly:
1
- Suspend the release of tadioactive pascous effluents monitored by the afhyted channel und declare the channel inoperable; or i
Change the setpoint so it is acceptably conseirative 4
- 2. If the number of channels operable is less than the minimum channels required by tables shown in Attachment 14 and 15, take the action shown in those tables.
3, Return instruments to opesable status within 30 days. If unsuccessful, explain in the next Semiannual Radioactive littluent Release Repon why the inoperability was not cornvted in a timely manner,
- c. Applicable Monitors Radioactive gaseous elfluent monitors for w hich alarnVtrip setpoints shall tv determined are:
Instrument Number Release Point North Anna Surry
[
Process Vent GW-102, GW 1781 GW-102, GW-130 1 Rey, j Condensit Air I?jector SV-121. SV-221 SV-111, SV 211 Ventilation Vent A VG 104. VG-1791 N/A Ventilation Vent 11 VG ll3, VG 180-1 N/A Ventilatic.o Vent No. I N/A VG-104 V, ntilation Vent No. 2 N/A VG-110, VG 131 1
"~
Radwaste Facility Vent N/A RRM 101
VIR0lNIA VPAF 2103 POWi!R Rl! VISION 2 PAGli 25 OF 119 i
- d. Setpoint Calculations
- 1. Setpoint calculations for each monitor listed in 6.3.2.c shall maintain this relationship:
D2Dpy + Deae + D (15) vy whe ::
D 6.3.1.a dose limits that implement 10 CFR 20 for the Station, nuenvyr
=
1he noble gas Station boundary dose rate from proecss vent gaseous D
=
py effluent releases, mrem /yr D, = 1he noble gas Station boundary dose rate fror. <;ondenser air ejector gaseous effluent releases, mrenvyr 1he noble gas Station boundary dose rate from:
D
=
vy Surry:
Summation of the Ventilation Vents 1,2, and the Radwaste Facility vent gaseous ef fluent releases, Rev.1 mrenVyr North Anna: Summation of ventilation vent A plus 11 gaseous effluent releases, mienVyr
- 2. Setpoint values shall be detennined by:
R x 2.12 I! 03 in Can "
p (16) in where:
i m = The release pathway, process vent (pv), ventilation vent (vy)
Rev.1
. condenser air ejector (cae), or Radwaste Facility (rv)
C,n = 1he effluent concentration limit implementing 6.3.1.a for the Station, pCi/ml Rin = 1he release rate limit for pathway m determined from methodology in 6.3.1.c, using Xe-133 as nuclide to be released, pCi/see 2.12F-03 = CFM per ml/see F
= The maximum flow rate for pathway m, CFM rn l
l'
.,,.. -, _.. ~ ~
VIRGINIA VPAP 2103 i
POWi!R Rl! VISION 2 i
PAGli 26 OF i 19 NOTE: According to NUREG 0133, the radioactive cifluent radiation monitor alarm' trip setpoints should be based on the radioactive noble gases. It is not practicable to apply instantaneous alarnt' trip setpoints to integrating monitors sensiti',e to radiciodines, radioactive raaterials in particulate form, and radionuclides other than noble gases.
6.3.3 Noble Gas Effluent Air Dose 1.imit
- a. Requirement
- 1. The air dose in unrestricted areas due to noble gases released in gaseous effluens from ca, S unit at or beyond the site boundary shall be limited to:
- During any calendar quarter: 5 5 mrads for gamma radiation and s 10 mrads for trta radiation
- During any calendar year: s 10 mrads for gamma radiation and 5 20 mrads for beta radiation
- 2. Cumulative dose contribut ons for noble gases for the current calendar quarter i
and current calendar yen shall be determined in accordance with 6.3.3.c at least once per 31 days.
l
- b. Action if the calculated air dose from radioactive noble gases in gaseous 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 the Rey, I causes for exceeding the limits and defines correctis e actions that have tven 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.
VlltGINIA VPAl' 2103 l'OWER lt!!VlSION 2 PAGli 27 OF 119
- c. Noble Gas Effluent Air Dose Cnleulation Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qivv.
- 1. 'the air dose to areas at or beyond the site boundary due to noble gases sha4 be detennined by the following:
For gamma radiation:
Dp = 3,17E 08 E lM vy Qi,y + Mj y Qipyj (17) i p
i For beta radiation:
Db = 3.17E-08 % [Njyy Qiyy + N v Qj yj (18) ip p
i Where:
Subscripts = vv, refers to vent releases from the building ventilation vents, including the Itadwaste Facility Ventilation Vent and air ejectors llev. I pv, refers to the vent releases from the pmcess vent i, refers to individual radionuclide Dg = the air dose for ganuna radiation,in mrad Do = the air dose for beta radiation, in mrad
- Mivv, hiipv = the air dose factors for ventilation vents or process vent release due to gamma emissions for each identified noble pas radionuclide,i, in mradlyr per Curie /sec. Factors are given '.n Attachments 12 and 13 N vy, Nipv = the air do;c factor for ventilation vents or process vent release i
due to beta emissions for each identified noble gas radionuelide, i
i,in mrad /yr per Curie /sec. Factors are listed in Attachments 12 and 13 Divv, Qipv = the release for ventilation vents or process vent of noble pas radionuclide, i, in gaseous effluents for 31 days, quarter, or year as appropriate in Curies (per site)
- == -.
. a... -
..-.---.--a..
l VlltGINIA YPAl' 2103 10WEli Ill! VISION 2 PAGli 28 OF 119 i
6.3.4 I 131, 11 3, and Itadionuclide.s in Particulate l'orm I:lliuent I)ose I.linit I
l a.1(equirement
- 1. Methods shall be implemented to ensure that the dose to any organ of a memter of the public from 1 131, tritium, and all radionuclides in paniculate form with half-lives greater than 8 days in gaseous effluents released from the site to unresaicted areas from each reactor unit shall be limited:
i
+ During any calendar quarter: s 7.5 mrem to the critical organ
. During any calendar year: s 15 nuem to the critical organ
- 2. Cumulative dose contributions to a member of the public from ! 131, tritium, and radionuclides in particulate fonn with half lives greater than 8 days in gaseous efHuents released to unrestricted areas for the cunent calendar quarter and cunent calendar year shall te detennined at least once per 31 days in accordance with 6.3.4.c or 6.3.4.d.
- b. Action if the calculated dose from the release of I 131, tritium, rnd radionuclides in particulate form, with half-lives greater than 8 days, in gaseous elHuents exceeds any of the above limits, prepare and submit to the N1(C within 30 days, a special report in accordance VPAP 2802, Notifications and l<eports, that contains the:
Rev.I
- 1. Causes for exceeding limits.
l
- 2. Conective actions taken to reduce releases.
^
- 3. Proposed corrective actions to be taken to assure that subsequent releases will t
be in compliance with limits stated in 6.3.4.a.
i I
i l
VIRGINIA VFAF 2103 IU Wi!R HliVISION 2 FAGli 29 OF i19
- e. Surry Dose Calculallons Gaseous releases, not through the process vent, are considened ground level and shall be included in the determination of Q,vv. llistorical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection Rev.1 j
to specific Station functions, such as containment purges, shall tv used in the estimates as appropriate.
i
- 1. The dose, attributable to gaseous effluents at and tryond the site boundary that contain 1 131, tritium, and particulate-fonn radionuclides with half lives greater than 8 days, to the maximum exposed member of the public shall be determined by:
D, = 3.17E-08 E l(Rhi,yy Q,vv + Rhlipy Qipy) + (Rinv 0,vy + Ri pv0,pv)I(19) i I
Where:
I Subscripts = vv. refers to ver.t releases from the building ventilation vents, including the Radwaste Facility Ventilation Vent and Rev.1 air ejectors:
py, refers to the vent releases from the orocess vent Dr = the dose to the critical organ of the maximum exposed memtvr of the public in mrem I
Rht vy, Rhiipv = the milk pathway dose factor for ventilation vents or process
{
i vent release due to 1-131, tritium, and from all particulate-fonn radionuelides with half lites greater than 8 days, in miem/yr per Curie /sec. Factors are listed in Attachment 18, Critical Organ and Inhalation Dose Factors For Surry Ri vt, Riipv = the inhalation pathway dose factor for ventilation vents or i
process vent release due to 1 131, tritium, and from all
- paniculate form radionuclides with half lives greater than 8 days, in mrem /yr per Curie /sec. Factors are listed in 8 Q,vy, Q,pv = the release for ventilation vents or process vent of I-131, trhium, and from all pa~iculate-form radionuclides with half-lives greater than 8 days in Curies j
3.17 ILOS = the inverse of the number of seconds in a year l
l l
l
'F r-i4,-#
e
' % bgeer-y reWz,emyd" 4
9 g-e---sweg.1y&+su
+Piee Wgm" 2'*TP'i-T RT-w'SY'vM'-4 g1*gM t?+ % 89*tt'-d*4'-dM@***-TSP 44-yd-' pie"N+77-*ew W-14T T' Y h4-F-N'W'T'F'1TL4"'N'v+ypMM w -' Y-4-(Ypf'"
VIRGINIA VPAP-2103 POWER HliVISION 2 PAGli 30 OF 119
- d. North Anna Dose Calculations Gaseous releases, not through process vent, are considered ground level and shall be included in the detennination of Q,vy. llistorical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection to Rev.I specific Station functions, such as containment ; pes. shall be used in the estimates as appropriate.
- 1. The dose, attributable to paseous cf fluents at and beyond the site boundary that contain 1-131, tritium, and particulate-form radionuclides with half-lives greater than 8 days, to the maximum esposed memler of the public shall be detennined by:
Dr = 3.1711 OS E lRivy Q,vv + Ripv 0,pvi (20) 1 Where:
Subscripts = vv, refers to vent releases from the building ventilation vent; pv, refers to the vent releases from the process vent Dr = the dose to the critical organ of the maximum exposed member of the public in mrem R vy, R v = the dose factor for ventilation vent or process vent release i
ip due to 1-131, tritium, and from all particulate-fomi radionuclides with half-lives greater than 8 days, in mrent'yr per Curie /sec. Factors are listed in Attachment 19, Critical Organ and inhalation Dose Factors for North Anna Civv, Qipv = the release for ventilation s ent or process vent of 1-131, tritium, and from all particulate-form radionuclides with half-Rev.I lives greater than 8 days in Curies 3.17 E-08 = the inverse of the nun ber of seconds ia a year
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 31 OF 119 6.3.5 Gaseous Radwaste Treatment llistorical data pertaimng to the volumes and radioactive concentrations of gaseous effluents released in connection to specific Station functions, such as containment purges, shall be used in projected doses, as appropriate,
- a. Requirement
- 1. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive material in gaseous waste prior to 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 exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation averaged over 31 days. (North Anna)
Rev.1
- 2. The appropriate portions of the Gaseous Radwaste Treatment System shall le used to reduce radioactive materials in the gaseous waste prior to their discharge when the projected gaseous effluent air doses due to pscous 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 ever 31 days.
(Surry)
- 3. The Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceect u 3 mrem to the critical organ averaged over 31 days.
- 4. Doses due to gascot.s releases from the site shall be projected at least once per 31 days based on the calculations in 6.3.5.c, d, and e.
- b. Action If gaseous waste that exceeds of the limits in 6.3.5.a is discharged without treatment, prepare and submit to the NRC within 30 days, a special report in Rev.I accordance with VPAP-2802, Notifications and Reports, that includes:
- 1. An explanation why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or 3ubsystems, 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.
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 32 OF 119 i
- c. Projected Gamma Dose
- 1. Determine D, the 31-day gamma air dose in the previous 31-day period, g
per Equation (17).
- 2. Estimate R, the ratio of the estimated volume of gaseous effluent in the present g
31-day period to the volume released during the previous 31-day period.
- 3. Estimate F, the ratio of the estimated noble pas efnuent activity in the present g
31-day period to the noble gas effluent activity during the previous 31-day period ( Ci/ml).
- 4. Detennine PD, the projected 31-day gamma air dose.
g PD = Dg (R x P )
(21) g g
g
- d. Projected lieta Dose
- 1. Detennine D, the 31-day beta air dose in the previous 31 days, d
per Equation (18).
- 2. Estimate R and F as in 6.3.5.c.2 and 3.
g g
- 3. Detemiine PD, the projected 31 day beta air dose.
d PD = D (R x F )
(22) b d
g g
- 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 (19) or (20), where Dr = Dmax-
- 2. Estimate F, the ratio of the estimated activity from I-131, radioactive materials i
in particulate form with half-lives greater than 8 days, and tritium in the present 31-day period to the activity of I-131, radioactive materials in particulate form with half-lives greater than 8 days, and tritium in the previous 31-day period
-(pC/ml).
- 3. Determine PDnuu, the projected 31-day maximum exposed member of the public dose.
PDaua = Dmax (R x F )
(23) g i
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 33 OF 119 6,4 Total Dose 1.linit to Public From Uranium Fuel Cycle Sources 6.4.1 Requirement The annual (calender year) dose or dose commitment to the maximum exposed member of the public due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 miems to the total body or the critical organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).
6.4.2 Action
- a. If the calculated doses from release of radioactive materials in liquid or gaseous 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 tanks, whether limits in 6.4.1 have been exceeded.
- b. If the limits in 6.4.1 have been exceeded, piepare and submit to the NRC within 30 days a special report in accordance with VPAP-2802, Notifications and Reports, Rev.I that defines the corrective action to be taken to reduce subsequent releases and to prevent recurrence, and includes a schedule for achieving confonnance with the limits. Special reports, as defined in 10 CFR 20.405c, shall include:
- 1. An analysis that estimates the radiation exposure (dose) to the maximum exposed member of the public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the re eases 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.
3.- If the estimated dose exceeds the limits in 6.4,1, and if the release condition that violates of 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 report is considered a timely request, and a variance is granted until staff action on the request is complete.
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE 34 OP 119 6.5 Rndlulogical Environmental hionitoring 6.5.1 Monitoring Program
- a. Requirement
- 1. The Radiological Environmental hionitoring Program shall be conducted as specified in..ua;;hments 20 or 21, Radiological Environmental hionitoring Program.
- 2. Samples shall be collected frem specifie locations speci6ed in Attachment 22 or 23, Environmental Sample Locations.
- 3. Samples shall be analyzed in accordance with:
. Attachment 20 or 21 requirements
. Detection capabilities rc ired by Attachment 24 or 25, Detection Capabilities for Environmental Samp Analysis
. Guidance of the Radiological Assessment Branch Technical Position on Environmental hionitoring dated November,1979, Revision No. I
- b. Action
- 1. If the Radiological Environmental hionitoring Program is not being conducted as required in 6.5.1.a. prepare and submit to the NRC,in the Annual Radiological Environmental Operating Report required by Technical Specification (Surry T.S. 6.6.B.2 and North Anna T.S. 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 reporting 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 that:
. Identifies the causes for exceeding the limits, and
. Defines the corrective actions to be taken to reduce radioactive efnuents so that the potential 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
..- _~ - - -. - -
VIRGINIA VPAP-2103 IOWER REVISION 2 PAGE 35 OF 119 When more than one of the radionuclides listed in Attachment 26 or 27 are detected in the sampling medium, the report shall be submitted if:
concentration (1) concentration (2) 10 reporting level (1), reporting level (2) + "' >
- 3. When radionuclides other than those listed in Attachment 26 and 27 are detected and are the result of plant effluents, the report shall be submitted if the 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 report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
- 4. With milk or fresh leafy vegetable samples 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 fiom which sateles 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 Semiannual Radioactive Ef0uent Release Report. Include in the report a revised figure and table for the ODCM to reDect the new locations.
6.5.2 1.and Use Census
- a. Requirement A land use census shall be conducted and shall identify within a distance of 8 km (5 -
miles) the location in each of the 16 meteorological sectors of the following:
Nearest milk animal
. Nearest residence
+ Nearest garden greater than 50 m2 (500 ft ) that produces broad leaf vegetation 2
- 1. The land use census shall be conducted during the growing season at least once per 12 months using information which will provide the best results (e.g.,
door-to-door survey, aerial survey, local agriculture authorities). Land use census results shall be included in the Annual Radiological Environmental Operating Report.
VIRGINIA VPAP.2103 POWER -
REVISION 2 PAGE 36 OF i19 2, llroad leaf vegetation sampling of at least three different kinds of vegetation may le perfonned at the site toundary in each of two different direction sectors with the highest predicted deposition source strength (D/Qs)in lieu of the Rev.I garden census. Specifications for broad leaf vegetation sampling given in
, 0 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 Semiannual Radioactive Effluent Release Report.
- 2. If a land use census identifies locations that yield a calculated dose or dose commitment (via the same exposure pathway) 20 percent 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, having the lowest calculated dose or tiose commitments (via the same exposure pathway) may be deleted from the monitoring program after October 31 of the year in which this land use census was conducted. Identify new locations in the next Semiannual Radioactive E. iuent Release Report and include in the report revised figures and tables reflecting the new locations.
- 6.5.3 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.
i l
VIRGINIA VPAP-2103 IOWER REVISION 2 PAGE 37 OF 119
- b. Action
- 1. Analyses shall be perfomied as pan of the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies (Cross Check) Program and include:
Program Cross-Check Of:
Milk 1-131, Gamma, K, St-89 and St-90 Water Gross lleta, Gamma, 1 131,11 3 (Tritium), Sr-89 and Sr-90 (Illind - any combinations of above radionuclides)
Air Filter Gross Beta, Gamma, Sr-90
- 2. If analyses are not performed as required by 6.5.3.b, report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report.
- c. Methodology and Results
- 1. Methodology and results of the cross-check program shall be maintained in the contractor-supplied Nuclear Reactor Environmental Radiation Mordtoring Quality Control Manual, IWL-0032-361.
- 2. Results shall be reported in the Annual Radiological Environmental M..ioring
- Report,
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 38 OF i19 6,6 Reporting Requirements 6.6.1 Annual Radiological Environmental Operating Report Routine Radiological Environmcatal Operating Reports covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year, A single submittal may be made for the Station. Radiological Environmental Operating Reports shallinclude:
- a. Summaries, interpretations, and analysis of trends of results of radiological environmental surveillance activities for the report period, including:
. A comparison (as appropriate) with preoperational studies, operational controls, and previous environmental surveillance reports
. An assessment of the observed impacts of the plant operation on the environment
. Results of land use census per 6.5.2
- b. Results of analysis of radiological environmental samples and of e' mental radiation measurements taken per 6.5.1, Monitoring Program. Results shall be summarized and tabulated in the famiat of the table in the Radiological Assessment Branch Technical Position on Environmental Monitoring.
Rev. I
- 1. If some individual results are not available for inclusion with the report, the report shall be submitted, noting and explaining reasons for missing results.
- 2. Missing data shall be submitted in a supplementary report as soon as possible.
- c. A summary description of the radiological environmental monitorir,; program.
- 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.
- e. Results of Station participation in the Interlaboratory Comparison Program, per 6.5.3.
- f. Discussion of deviations from the Station's environmental sampling schedule per 0 or 21.
- g. Discussion of analyses in which the lower limit of detection (LLD) required by 4 or 25 was not achievable.
l I
i
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 39 OF 119 6.6.2 Semiannual Radioactive Effluent Release Report a, Requirement Radioactive Effluent Release Reports covering operation of the units during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. A single submittal may be made for the Station and should combine those sections that are common to both units. Radioactive Efnuent Release Reports shallinclude:
- 1. A summary of quantities of radioactive liquid and gaseous efnuents and solid
~
waste released. Data shall be summarized on a quarterly 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 ef0uents released from the Station during the previous calendar year. This assessment shall be in accordance with 6.6.2.b and shall be included only in Radioactive Effluent Release Reports submitted within 60 days after January I of each year.
- 3. A list of unplanned releases from the site to unrestricted areas, during the reporting period, that exceeded the limits in 6.2.1 and 6.3.1.
- 4. Major changes to radioactive 1: quid, gaseous, and solid waste treatment systems during the reporting period.
5, Changes to VPAP-2103, Offsite Dose Calculation Manual (see 6.6.4).-
- 6. A listing of new locations for dose cabdations or environmental monitoring
' identified by the land use census (see 6.5.2).
- b. Dose Assessment
- 1. Radiation dose to individuals due to radioactive liquid and gaseous ef0uents from the Station during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109.
Population doses shall not be included in dose assessments.
-VIRGINIA VPAP.2103 :
POWER REVISION 2 i
PAGE 40 OF 119 4
- 2. The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station shal. oc incorporated with the dose assessment perfonned 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 confonnance with the EPA Uranium Fuel Cycle Standard,40 CFR Part 190."
- 3. Meteorological conditions during the previous calendar year or historical annual average atmospheric dispersi: n conditions shall tv used for detennining gaseous pathway doses.
6.6.3 Annual Meteorological Data
- a. Meteorological data collected over the previous year shall be in the fann of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
- b. Meteorological data shall be retained in a file on site and shall be made available to the NRC upon request.
6,6.4 Changes to the ODCM Changes to the ODCM shall be:
- a. Reviewed and approved by Station Nuclear Safety ar,d Operating Committee (SNSOC) and Station Manager prior to implementation.
Rev.1
- b. Documented. Records of reviews shall be retained as Station records.
Documentation shallinclude:
- 1. Sufficient information to support changes, together with appropriate analyses or evaluations justifying changes.
i 1
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 41 OF 119 -
- 2. A determination that a change will not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations, and will maintain the level of radioactive effluent control required by:
+ 40 CFR 190 10 CFR 50.36a 10 CFR 50, Appendix I c, Submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of, or concurrent with the Semiannual Radioactive Ef fluent Release Report for the period of the report 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.
- d. ' Submitted to the Management Safety Review Committee (MSRC) Coordinator.
Rev. _1
[ Commitment 3.2.1]
l' l
( __
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 42 OF i19 7,0 RECORDS 7.I The following individual and packaged documents and copies of any related correspondence completed as a result of the perfonnance or implementation of this procedure are records. They shall be submitted to Records Management in accordance with VPAP-1701, Reconis Management. Prior to transmittal to Records Management, the sender shall assure that:
Each 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 and dated, as required by this procedure.
7.1.1 Individual Records None Rev.I 7.1.2 Record Packages
. Records of changes to the ODCM in accordance with 6.6.4
. Records of meteorological data in accordance with 6.6.3
. Records of sampling and analyses
. Records of radioactive materials and other effluents released to the environment
. Records of maintenance, surveillances, and calibrations 7.2 The following documents completed as a result of the implementation of this piocedure are not records and are not required to be transmitted to Records Management.
None i
l l
1
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 43 OF 119 ATTACilNIENT I (Page 1 of 1)
SURRY HAI)lOACTIVE LIQUID EFFl.11ENT MONITORING INSTRUMENTATION MINIMUM INSTRUMENT OPER Alli.E ACTION Cll ANNEl.S 1.
GROSS RADIOACTIVITY h10NITORS PROVIDING ALARh1 AND AUTONIATIC TERh11 NATION OF RELEASE (a) Liquid Radwaste Efiluent Line 1
I Rev.2 (b) Radwaste Facility Liquid Ellluent Line i
I Rev.1 2.
GROSS BETA OR GAhth1A RADIOACTIVITY hiONITORS PROVIDlNG ALARh1 BUT NOT PROVIDING AIRONIATIC TERhilNATION OF RELEASE (a) Circulating Water Discharge Line i
2 (b) Component Cooling Service Water Ellluent Line 4
2 gey, }
3.
FLOW RATE htEASUREhtENT DEVICES (a) Liquid Radwaste Elliuent Line l
5 NCV' I (b) Radwaste Facility Liquid Efiluent Line ACTION 1:
If the number of operable channels is less than required, efnuent 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 gamma emitters, as defined in Attachment 8, Surry Radioactive Liquid Waste Sampling and Analysis Program.
AC'llON 3:
If the number of operable channels is less than required, efnuent releases via this pathway shall be suspended.
_ _ - _ _ _ _ _. ~... _
VIRGINIA -
VPAP-2103 POWER REVISION 2 PAGE 44 OF 119 A'ITACilh1ENT 2 (Page 1 of 2)
NORTil ANNA RADIOACTIVE I.lQUID EFFl.UENT 510NITORING INSTRUh1ENTATION h11Nih1Uh1 INSTRUh!ENT OPERAllLE ACTION Cil ANNEl.S 1.
GROSS RAO!GACTIVITY h10NITORS PROVIDING ALARht AND AUTOhiATIC TERhtlNATION OF RELEASE Liquid Radwaste Efiluent Line 1
i r
- 2. GROSS BETA OR GAh1A RADIOACTIVITY h10Nrf0RS PROVIDING ALARh1BUTNOTPROVIDING AUTOh1ATIC TERhtlNATION OF RELEASE (a) Service Water System Effluent Line 1
I (b) Circulating Water System Effluent Line 1
4 3.
FLOW RATE h1EASUREhiENT DEVICES Liquid Radwaste Efiluent Line 1
2 4.
CONTINUOUS COh1 POSIT 13 SAh1PLERS AND SAh1PLER FLOW N10NITOR Clarifier Effluent Line 1-1
- 5. TANK LEVEL INDICATING DEVICES (Note 1)
(9 Refueling Water Storage Tanks 1
3 (b) Casing Cooling Storage Tanks 1
3 (c) PG Water Storage Tanks (Note 2) 1 3
(d) Boron Recovery Test Tanks (Note 2) 1 3
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 45 OF 119 ATTACllh1ENT 2 (Page 2 of 2)
NORTil ANNA RADIOACTIVE LIQUll) EFFI,UENT hlONITORING INSTRUSIENTATION ACTION 1:
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 gross radioactivity (beta or gamma) at a lower limit of detection of at least 1x104 pCi/g or an isotopic radioactivity at a lower limit of detection of at least 5x104 pCi/g.
ACTION 2:
If the number of operable channels is less than required, ef0uent releases via this pathway may contmue 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 /> 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 provided the tank liquid level is estimated during all liquid 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 tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
NOTE 2:
This is a shared system with Unit 2.
VIRGINIA -
VPAP-2103 -
POWER :
REVISION 2 PAGE 46 OF 119 ATTACllh1ENT 3 (Page1of1)
- SURRY RADIOACTIVE I,1 QUID EFFI,UENT 510NITORING INSTRUh1ENTATION SURVEll,1,ANCE REQUIREhlENTS w
CllA N N El CllANNEL SOURCE Cil ANNEL CilA N N El.
DESCRIPTION CilECK CllECK C Al.IllR ATION FUN ( l IN A l.: GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (a) Liquid Radwaste EfDuent Line D
PR R
Q (b) Radwaste Facility Liquid Effluent Line D
PR R
Q Rev.I
- 2. GROSS BETA OR O AMMA r
RADIOACTIVITY MONITORS PROVIDING ALARM BUTNOT PROVIDING AUTOMATIC TERMINATION OF RELEASE (a) Circulating Water Discharge Line D
M R
Q (b)- Component Cmling Service Water D
M R
Q System Ef0uent Line
- 3. FLOW RATE MEASUREMENT DEVICES
= (a) Liquid Radwaste r.fauent Line D
N.A.
R
-N.A.
(b) Radwaste Facility Liquid Efiluent Line D
N.A.
R N.A Rey, [
3.
l l
^
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 47 OF 119 NI'TACilNIENT 4 (Page I of 2)
NORTil ANNA IIAI)IOACTIVE 1lQUID EFFl UENT hiONITORING INSTRUhlENTATION SURVEll.l.ANCE REQUIRESlENTS C ilA N N El, Cil ANNEL C ll A N N El.
SOURCE CllA N N El.
l'UNC 1 ()N Al, DESCillPTION CilECK CilECK C Al.IllR ATION
- 1. UROSS RADIOACTIVITY N10NITORS PROVIDING ALARh1 AND AUTOh1ATIC TERh11 NATION OF RELEASE Liquid Radwaste Efiluent Line D
D R
Q (Note 1)
- 2. GROSS BETA OR GAhth1A RADIOACTIVITY h10NITORS PROVIDING ALARh1 BUT NOT PROVIDING AUTOh1ATIC TERh11 NATION OF RELEASE (a) Service Water System ElIluent Line D
h1 R
Q (Note 2)
(b) Circulating Water System Efiluent Line D
h1 R
Q (Note 2)
- 3. FLOW RATE h1EASUREh1ENT DEVICES Liquid Radwaste Efiluent Line D (Note 3)
N.A.
R Q
- 4. CONTINUOUS CON 1POSITE SAh1PLERS AND SAh1PLER FLOW N10NITOR Clarifier Efiluent Line N.A.
N.A.
R N.A.
- 5. TANK LEVEL INDICATING DEVICES (Note 6) f (a) Refueling Water Storage Timk D (Note 4)
N.A.
R Q
(b) Casing Cooling Storage Tank D (Note 4)
N.A.
R Q
(c) PG Water Storage Tanks (Note 5)
D (Note 4 N.A.
R Q
(d) Boron Recovery Test Tanks (Note 5)
D (Note 4)
N.A.
R Q
l
_ -.-. ~ -
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE 48 OF 119 ATTACIIMENT 4 (Page 2 of 2)
NORTil ANNA RADIOACTIVE I.lOUID EFFl.UENT MONITORING INSTRUMENTATION SURVEll.l.ANCE REQUIREMENTS NOTE 1:
The Channel Functional Test shall also demonstrate that automatic isolation of this pathway and control room alanu annunciation occur if any of the following conditions exists:
- a. instrument indicates measured levels above the alamvtrip setpoint.
- b. Instrument controls not set in operate mode.
NOTE 2:
The Channel Functional rest shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- a. Instrument indicates measured levels above the alarnVtrip setpoint, b.' Instrument cor. ils not set in operate mode.
NOTE 3:
Channel Check sht" onsist of verifying indication of flow during periods of release.
Channel Check sht r make 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, periodie, or batch tses are made.
NOTE 4:
During liquid additions to the tank.
NOTE 5:
This is a shared system with Unit 2.
NOTE 6:
Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable af hokling the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
l I
i I
l i
i
' VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 49 OF 119 NITACllMENT 5 (Page 1 of 1) 1.lQUID INGESTION PATilWAY DOSE FACTORS l'OR SURRY STATION UNITS I AND 2 Total Body Al Thytold Ag Gl-LLI Aj RedionucIIde mIfm31t mism.ht mI.itmit pCirmi pCI'ml pCI'ml H3 2 82E 01 2 82E 01 2 82E 01 Na 24 4 57E41 4 57E 01 4.57E-01 Cr $1 558E400 3 34E 01 140E +03 Mn 54 135E403 2.16E + 04 Fe 55 823E+03 2.03E +04 Fe 59 7.27E + 04 6 32E405 Co 58 135E 403 122E +04 Co-60 3 82E +03 3 2SE404 Zn45 2.32E +05 3 23E +05 Rb86 2 91E+02 123E+02 Sr 89 143E+02 8 00E402 So00 3 01 E + 04 3 55E +03 Y 91 2 37E +00 4 89E+04 Zr-95 3 46E+00 162E +04 Zr 97 813E-02 551E+04 Nb 95 134E +02 151 E+06 Mo 99 2 43E+01 2 96E+0?
Ru 103 4 60E+01 12SE +04 Ru-106 2 01E,02 1.03E +05 Ag-110m 8 60E +02 597E+05 St> 124 1.00E402 6 70E 01 7 84E+03 St> 125 4 20E+01 1.79E 01 194E+03 Te 125rn 2 91E+01 6 52E 01 8 66E+02 Te 127m 6 68E+01 140E+02 1.84 E +03 Te-129m 1.47E+02 3 20E+02 4 69E+03 Te-131m 5 71E+01 108E +02 6 80E+03 Tv 132 124E+02 146E +02 6 24E +03 1-131 1,79E + 02 102E 05 8 23E+01 l132 9 96E + 00 9 96E+02 5 35E+00 1133 3 95E+01 1.90E +04 1 16E+02 1-134 540E400 2 62E+02 1.32E-02 1-135 2 24E +01 4 01E+03 6 87E+01
- Cs 134 1.33E +04 2 85E+02 Cs 136 2 04E+03 3 21E+02 Cs 137 7.85E +03 2 32E402 Cs138 594E+00 5.12E 05 Ba-140 1.08E +02 3 38E +03 La-140 210E 01 5 83E+04 Ce 141 2 63E-01 8 86E+03 Ce-143 4 94E 02 167E404 Cs 144 9.59E + 00 6 04E+04 Np-239 191 E-03 711E +02
.__s VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 50 OF 119 ATTACIIMENT 6 (Page 1 of 4)
NORTil ANNA LIQUID INGESTION PATilWAY DOSE FACTOR CAI.CUI.ATION UNITS I AND 2 1.0 EQUATION (6)
D=tF fCAi i
where:
D=
cumulative dose conunitment to the total body or critical organ, from the liquid effluents for the time period t, in mrem length of time period over which C and F are averaged for all liquid releases, hours t
=
i F
the near field average dilution factor for C; during any liquid effluent release. Defined
=
as the ratio of the average undiluted liquid waste Dow during release to the average flow from the Station discharge structure to unrestricted areas f
the individual dilution multiplication factor to account for increases in concentration of
=
long-lived nuJides due to recirculation, listed on page 4 of 4 of this attachment. "f"is i
the ratio of the total dilution now oser the effective dilution flow C=
average concentration of radionuclide, i, in undiluted liquid effluent during time period, i
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 4 of 4 of this attachment, in mrem-ml per hr-pCi A = 1.14 E+05 (730/Dw + 21BF /Da) DFi i
i where:
1.14 E+05 = 1 E+06 pCi/pci x 1 E+03 ml/kg + 8760 hr/yr, units conversion factor 730 = adult water consumption, kg/yr, from NUREG-0133
VIRGINIA VPAP-2103 i
POWER REVISION 2 PAGE 51 OF 119 ATTACllMENT 6 (Page 2 of 4)
NORTil ANNA 1lQUID INGESTION PAT 11WAY DOSE FACTOR CALCULATION UNITS 1 AND 2 Dw = dilution factor from the near field area within one-quarter mile of the release-point to the potable water intake for the adult water consumption. Dw includes the dilution contributions from the North Anna Dam to Doswell (0.73), the Waste Ileat Treatment Facility (Cc/C ), and Lake Anna (C /C ). The potable L
L R water mixing ratio is calculated as:
1/ (Ce / C ) (C / C x 0.73) = Ca / (Cc x0.73)
L L
R where Ce / C and CR are the respective concentrations for the considered L
nuclide in the Discharge Channel, Waste lleat Treatment Facility (Lagoon) and the Reservoir. Calculation is per expressiom. 11.2-5,11.2-6, and i1.2-8 of the Nonh Anna UFSAR BFi = the bioaccumulation factor for nuclide,i, in fish, pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev. I Da
= dilution factor for the fish pathway, calculated as C /Ce where C and Ce are L
L the concentrations for the considered nuclide in the Discharge Channel and the Waste Heat Treatment Facility (Lagoon). Calculation is per Expressions 11.2-5, and l'.2-6 of North Anna's UFSAR DFi = the critical organ dose conversion factor for nuclide,i, for adults, in mrem /pCi, from Table E-11 of Regulatory Guide 1.109, Rev. I
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 52 OF 119 ATTACilMENT 6 (Page 3 of 4)
NORTil ANNA 1.lQUID INGESTION PATilWAY DOSE FACTOR cal.CULATION UNITS I Anis 2 2.0 EQUATION (8)
Equation (6) is simplified for actual dose calculations by introducing:
WASTE FLOW WASTE FLOW F = CIRC.(WATER) FLOW + WASTE FLOW " CIRC.1 LOW 7
and CIRC. FLOW I
- EFFECTIVE DIL. FLOW I
i Effective dilution How rates for individual nuclides "i" are listed on Attachment 7, North Anna Liquid Pathway Dose Commitment Factors for Adults. Then the total released activity (Qi) for the considered time period and the ith nuclide is written as:
Qi = t x C x WASTE FLOW i
and Equation (6) reduces to:
D=
Qi EFF,Di FLOWi i
For the long lived, dose controlling nuclides the effective dilution flow is essentially the over (dam) flow rate out of the North Anna Lake system (i.e., the liquid pathway dose is practically independent from the circulating water now rate. Ilowever, to accurately assess long range average effects of reduced circulating water flow rates during outages or periods of iow 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/see per pump.
By defining B = Ai/ EFF. DIL. FLOW, the dose calculation is reduced to a two factor i
i formula:
D = [ Qi x -B i 1
Values for B (mrem /Ci) and EFF. DIL. FLOW are listed in Attachment 7.
i i
l l
l
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE 53 OF 119 ATTACllhlENT 6 (Page 4 of 4)
NORTil ANNA LIQUll) INGESTION PATilWAY 1)OSE FACTOR CAI.CUI.ATION UNITS I AND 2 Total Hody Ag Critical Organ Al ladliidual lillution Redinnuclide m n m 'ig mum.hr y,gg ig,,gg,,
y,,g,,
ggli p
pCl/mi pCl/ml 11 3 14.9 6 lblNOO 6.thl.+00 Na-24 1.0 3.71 E + 0 L 3.711:401 Cr-51 1.7 1.100+00 Mn.54 7.0 h.62E+02 4.52 tM03 Fe 55 l 1.3 1.30F+02 5.561' +02 i e-59 2,2 9.4714 02 2.470 +0 3 Co.5 4 2,8 2.4914 02 1.1 IINO2 Co 60 13.3 8.27E+02 3.75 E +02 Zn-65 6.1 1.2 Mi'.+ 04 7.2514 04 Rb46 1.5 3.5 3 F+ 04 7.59 E + 04 Sr 89 2.3 6.70E+02 Sr-90 15.8 2.39 E + 05 Y 91 2.5 3.42E 01 Zr.95 2.7 2.98 E-.01 I.r-97 1.0 1.50E-04 3.27E 04 NN95 1.0 4.871:401 9.0714 0i Mo-99 1.0 7.4814 00 3.931h01 Ru-103 2.0 4,100 00 Ru-10h 7.6 2.65E+01 A 110m 6.2 4.94 E+ 00 8.32E+0J F
Sh-124 2.6 4.3714 01 2.08 E+ 00 Sb.125 11.4 2.4613 01 1.161+00 Te-125m 2.5 3.23E+02 8.73F+02 Te 127m 3.7 7.82 F +02 2.29E + 0 3 Te-129m 1.9 1.52E+03 3.5 80 +03 Te-131m 1.0 1.12iN 02 1351302 Tc 132 1.0 5.04E+02 5.3714 02 1 131 1.2 9.66E+01 1.69E
- 02 1 132 1.0 1.03E 01 2.950-01 1 133 1.0 3.47 E W) 1.141:+ 01 1-134 1.0 2.150. 02 6 001: 02 1 135 1.0 6 58E.01 1.78E+00 Cs-134 10.3 5.80E+05 7.09 E +05
~
Cs-136 1.3 6.O l F+ 04 8.351M04 Co 137 15 8 3.45 E+ 05 5.26E+05 Ca.138 1.0 9.18 E-01 1.85E+00 13a 140 1.3 2 65E *01 5.os E-01 1.a - 14.
1.0 4 47E-01 1.69E.02 Ce 141 1.8 2.14 E-02 1.X9E 01 Ce-143 1.0 1.35I:.04 1.22 E +00 Ce 144 6.6 1.41E+00 1.101W01 No-239 1.0 5.13I-04
- 9. 31 E-04 1
VIRGINIA VPAP-2103 POWER REVISION 2 PAGli 54 OF 119 ATTACilMENT 7 (Page1of1)
NAPS 1.1QU11) l'ATilWAY DOSE COMMITMENT FACTORS I?OR Al)UI.TS i = A Fi/ CIRC FLOW = A;/Elfluent Dilution Howj)
Ol i
1:ffectiv e Ilituttui l' low Total llady ill Critical Organ Ill g
g (cit / sect (mrem /CD
( m r em/CI) 11 3 2.2 n E + 02 2 6610 04 2.661:-04 Na-24 3.191N 01 1.07E.04 1 071:.04 Cr 51 1.99 E + 01 5,44 E-06 N/A Mn54 4.E8E+02 1.731002 9.081502 Ev-5 5 3 011% 02 4.23E 03 1.811002 l e.59 1.57E+01 5.91E-03 1,551102 Co-58 1.20E+03 2 040-01 9 100 04 Cn,60 2 55E+02
- 3. I slMQ
- 1.411502 Zn 65
- 5. foe + 02 5.74E-01 1.271 +00 Rb46 2.341: + 03 1.481001 3.1 E E.01 Sr N 1.46('+ 01
- 5.84E-03 N/A Sr.90 2.16 E+ 02 1.091' + 0 !
N/A F91
- 1. 3 41' + 03 2.50lM)6 N/A Zr.95 1.271:+03 2.30E-06 1.311506 -
h 97 3.39 E + 03 4 111 10 9.461-10 Nb95 3.25 E + 01 1,47E-04 2.740 04 Mo 99 3.30E+01 2.22 E.01 1.17 E-04 Ru 101 1.f4 th01 2.401. 05 N/A Ranto -
4=481 +02 5.80E-04 N/A A g-110rn 5.52E+02 E.78E-05 1.4 x1504 Sb 124 1.3215 01 3.25E 04 -
1,551505 Sb 125 2.98 E + 02 8.10E.04 3.kOE-05 Te 125m 1.35 E + 03 2.15 lbol 615E 03 Te-127m 9.16E+ 02 8 37E 03 2.461i-02 Te-129m 1.N2E+03 8.19E-03 1.930-02 Te-131m 3.3 R E +03
- 1. 27 E-04 192 E-04 Te-112 3.27 E + 03 1.51E 03 1,61 E 03 1-131 2.94 E + 03 3.22E 04 5.6 21 /.4 1132
- 3. 40 l'. + 03 2.98 E-07 8.5 Il' <07 '
~
3.2e 05 l134 3.40E+03 6.19 E-08 l.731b07 1 135 3.40E + 01 '
l.900-06 5.151b06 Cs-134 3.29 E + 02 1.731 +0!
- 2. l l E + 01 Cs 136
- 2 62E+01 2.25 E -01 3,12 E-01 Cs-137 2.15 f M 02 1.57F4 01 2.4014 01 Co-138 3.400 +0) 2.65 E-06 5.341506 11a 140 2.65 E + o3 9 81E-05 1.88 E-06 1.a-140 3.16ih03 1.31E 08 4.94 E.-0M Cc-141 1.8514 03 1.14E-07 1.00lM16 Cc 143 3.3714 03 3.93 E.10 3.55E 06 Oe144 5.1J[302 2.701' 05 2.101504 Np 239 132E+01 1,51E E 2.7 5 E-09
VPAP-2103 POWER REVISION 2 PAGE $5 OF 119 ATTACllA1ENT 8 (Page 1 of 3)
SURRY RADIOACTIVE LIQUID WASTE SAMPLING AND ANAL,YSIS PROGRAM Minimum L wer Limit of Liquid Release Sampling Type of Activity A" I S'S Detection (LLD)
Y Type Frequency l,requency Analysis (pCi/ml),(Note 1)
Principal Gamma
-p p
Emitters (Note 3) 5xl(r7 (Each Batch)
(Each Batch) 1 131 lx10-6 A. Batch Releases Dissolved and P
h1 Entrained Gases lx10-5 (One BatcW)
(Note 2)
(Gamma Emitters) 11-3 1 x10-5 P
M Composite (Each Batch)
(Note 4)
Gross Alpha lx10-7 P
Q Composite Sr-89, Sr-90 5x 10-8 (Each Batch)
(Note 4)
Fe-55 1 x 10-6 Principal Gamma Continuous W Composite Emitters (Note 6) 5x10-7 B. Continuous (Note 6)
(Note b) 1131 1 x10-6 Releases Dissolved and M
M Entrained Gases 1x 10-5 (Note 5)
Grab Sample (Gamma Emitters) 11-3 1 x10-5 Continuous M Composite (Note 6) -
(Note 6)
Gross Alpha lx 10-7 Continuous Q Composite Sr-89, Sr-90 5x10 8 (Note 6)
(Note 6)
Fe-55 1x 10-6
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 56 OF 119 A'ITACllMENT H (Page 2 of 3)
SUf:RY RADIOACTIVE LIQUID WASTE SAMPLfNG AND ANALYSIS PROGRAM Note 1: For a particular measurement system (which may include radiochemical separation):
4.66 33 LLD = E V. M x m6. y, g-W Where:
LLD = the "a priori"(before the fact) Lower Limit of Detection (as microcuries per unit mass or volume) (see 4.8) st3 = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute, epm)
Rev.1 E = the counting efficiency (as counts per disintegration)
V = the sample size (in units of mass or volume) 2.22x 106 = 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 as an a "posteriori" (after the fact) limit for a particular measurement.
l l
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 57 OF 119 NITACllMENT 8 l
(Page 3 of 3)
SURRY RADIOACTIVE LIQUID WASTE SAMPl.ING AND ANAL,YSIS PROGRAM Note 2: A batch release is the discharpe ofliquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and appropriate methods will be used to obtain a representative sample for analysis.
Note 3: The principal gamma emitters for which the LLD speciGeation applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co 60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. 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 reported.
Note 4: A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and for which the method of sampling employed results in a specimen that is representative of the liquids released.
Note 5: A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the 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.
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE $N OF i19 NITACllhlENT 9
'hpe I of 3) l NORTil ANNA HADIOACTIVE I.! QUID WASTR SAMPl4tNG ANI) ANAL,YSIS PROGRAh!
1.lquid Release Sampling MI"I'""!"
Type of Activity Imer Limit of Typ-Frequency
$""I "
Analysis Y
Detection (1.LD) 1 requency (pCi/ml),(Note !)
Principal Gamma p
p Emitters (Note 3) 5x10 7 (Each !!atch)
(llach llatch) 1.j3j j x;gg, liatch Releases Dissolvetl and p
M Entrained Gases 1x105 (Notes 2 and 7)
(One llatch/M)
(Gamma Emitters)
II3 1 x 10'5 P
M Composite (Each llatch)
(,qote 4)
Gross Alpha Ixio 7 P
Q Composite St 89, Sr-90 5x 10-8 (Each Ilatch)
(Note 4)
Fe-55 1 x 104>
Principal Ganuna Emitters (Note 6)
SX IU'I Continuous Continuous W Composite 1 131 lxto 6 Releases (Note 6)
(Note 6)
Dissolved and (Note 5)
Entrained Gases 1 x 10-5 (Ganuna Emitters)
Continuous M Composite H-3 lx10~5 (Note 6)
(Note P Gross Alpha lxto-7 Continuous Q Composite St-89, St 90 5x10 8 (Note 6)
(Note 6)
Fe-55 1x10 6
VillGINIA VPAP 2103 POWEll Rl! VISION 2 PAGE 59 OF i19 ATl'ACithlENT 9 (Page 2 of 3)
NORTil ANNA HAI)lOACTIVE LIQUll) WASTE SAA1Pl.ING AND ANAINSIS PROGilAM Note 1: For a panicular measurement system (which may include radiochemical separation):
'u>= E.v. m a 2.v. w o Where:
LLD = the "a nriori"(trfore the fact) Lower Limit of Detection as defined atxwe (as mierocuries per unit mass or volume) bee 4.8) sh = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute, cpm) lley.1 E = the counting efficiency (as counts per disintegration)
V = the sample size (in uc.its of mass or volume) 2.22x 106 = the numler of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable)
A = the radioactive decay constant for the pwticular radionuclide At = the elapsed time letween the midpoint of sample collection and time of counting Typical values of E, V, v and At should be used in the calculation.
The LLD is an "a priori"(tefore the fact) limit representing the capability of a measurement system and not as an a "posteriori"(after the fact) limit for a particular measurement.
VIRGINIA VPAP 2103 POWIiR RiiVISION 2 PAGI! 60 OF 119 ATTACilSIENT 9 (Page 3 of 3)
NORTil ANNA RADIOACTIVE l.lQUID WASTE SAMPLING AND ANAINSIS l'NOGRAM i
i Note 2: A batch release is the distharpe of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall le isolated, and then thoroughly mixed as the situation permits, to asstue representative sampling.
Note 3: The principal ganuna emitters for which the Ll.D specification applies exclusively are the following radionuclides: Mn 54, Fe-59, Co 58,00-60, Zn 65 Mo 99, Cs 134. Cs-137, Ce-141, and Cc 144 This list does not mean that only these nuclides are to be detected and reported. Other acaks that are measurable and identifiable, at levels exceeding the LLD, together with t1e 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 of liquid waste discharged and for which the method of sampling employed results in a specimen that is representative of the liquids released.
Note 5: A continuous release is the discharge ofliquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.
Note 6: To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream, Pilor to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the ef fluent releases.
Note 7: Whenever the secondary coolant activity exceeds 104 pCi/ml, the turbine building sump pumps shall be placed in manual operation and samples shall be taken and analyzed prior o a
release. Second ary 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 />.
4-ee---g+f'a
+ - -
gg ye g-p i m gyw----ts""'$"rr='*r
- "Mt V****e-"*""T"'-+'4M-W-Fw" 4
81'-**gyt-r'.mg-1-N"y' rami'erve--*
W-asy-'--r---*'T
-$+--'ppr-+e-Wy'N T'
w='
'*rNT'WC'*"-"1'"I--'TP"'---
-T'""r'"-fa'=+--**em T'
f
VIRGINIA ypAp.2193 POWER REVISION 2 PAGE 61 OF 119 A'ITACllMENT 10 (Page 1 of 4)
SURRY RADIOACTIVE GASEOUS WASTE SAMPLING ANI) ANAINSIS PROGilAM Gaseous Release Sampling Minlinuln Type of Activity UCl"'I"" (I lUI Lower Limit of
^ ""If
- Type Frequeney Analysis 1 equency (pCihnt), (Note 1) 1 gg;a$'; #[
Prior to telease.
Principal Gamma A. Waste Gas (Each Tank)
Emitters (Note 2)
IX10a f'turage (Grab Sample) lank c
Principal Gamma I*IU t Pri r to release.
Pn,ot to release.
Emitters (Note 2)
- 11. ConIainment Purge (Each PURGE)
(Each PURGE)
II3 IXIU*
C.Ventlintion Weekly Weekly Principal Ganuna
- x ;g.4 (1) Prorus Vent (Grab Sample)
Emitters (Note 2)
(2) Vent Vent #1
- 0) Vent Vent #2 (Note 3)
(Note 3)
Il 3 lx104 (4) Sitit Vent Continuous Weekly (Note 5)
I'I3I IXIU'i',
(Note 4)
(Charcoal Sample)
I). All Release Continuous Weekly (Note 5)
Principal Ganuna IXIU,3 (Note 4)
Particulate Sample limitters (Note 2)
Types as Weekly Continuous C"*o site Gross Alpha 1x10-11 listed in A.
(Note 4)
Pardeulate Sample 11, arid C.
Quarterly Continuous (Note 4)
Composite St-89, St 90 1 x10-li i'sticulate Sample Noble Gases Continuous Noble Gas Gross lieta Ix104 (Note 4)
Monitor and Gamma E. Condenser Weekly - -
Principle Ganuna Air Grab Sample -
Weekly Emitters (Note 2)
IXIU" Ejector (Note 3)
(Note 3) 11 3 ix394 l
~.., _ _ - _
_, ~.,. _.. _ _ - _ _ _ _. -. _ _ _ _ _... _. _ -
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE 62 OP 119 ATTACllMF,NT 10 (Pape 2 of 4)
SURRY H ADIDACTIVI' GASEOLIS WASTE SAMI't.ING AND ANAIMSIS l'H OG R A M I'fI"'hI[u(crs g gga aintna Prior to release.
Prior to release.
(Grab San.ple)
(Each telease 11-3 lxig6
. Continuors Chatcoal Sample F. Containinent g,g3g g gg.33 (Note 4)
(Not Continuous Particulatt..
- ie Principle Ganuna IXI*10 U"4 (Note 4)
(Note 6)
Einitters (Note 2)
Depressuri.
Composite Continuous Particulate Sample Gross Alpha 1 x10-10 zation (Note 4)
(Note 6)
Composite C t u us Paniculate Sample Sr 89, Sr 90 1x1010 (Note 6)-
b
VIRGINIA VPAP-2103 i
LOWER Rl!YlSION 2 l'AGI! 63 OF i19 ATTACllMENT 10 (Page 3 of 4)
SURRY HAl)l() ACTIVE (iASE(Itis WASTE SAMPI,1N(i ANI) ANAL,YSIS PRO (iRAM Note 1: For a particular measurement system (which may include radiochemical separation):
4.66 si, I'bU
- E. V. 2.2 2 x 106. y. e do t )
Where:
1 11D = the"a priori"(triore the f act)1 ower Limit of Detection as defined above (as microcuries per unit mass or volume)(see 4.8).
st, = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute, cpm).
E = the counting efficiency (as counts per disintegration).
Rev.1 V = the sample size (in units of mass or volume).
2.22x106 = the number of disintegrations per minute (dpm) per microcurie.
Y = the fractional radioche.nical 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 1.LD is an "a priori"(tefore the fact) limit representing the capability of a measurement l
system and not as an a "posteriori"(after the fact) limit for a particular measurement.
l L
l l
~ - _.... - -. _.. _.. _,. -., _,., -..
r ~ - - - -
VIRGINIA VPAP 2103 POWiiR Rl! VISION 2 PAGli 64 OF i19 l
ATTACllMENT 10 (Page 4 of 4)
SURRY R ADIOACTIVE GASI:OUS WASTE SAMPl ING AND ANAL,YSIS PROGRAM Note 2: The principal panuna emitters for which the Lt.D specification applies exclusively are the following radmnuclides: Kr 87, Kr 88, Xe 133, Xe 133m, Xe 135. Xe-135m, and Xc.
138 for gaseous emissions and Mn 54, Fe 59, Co 58, Co 60, Zn 65, Mo-99, Cs 134. Cs-137, Cc-141 and Cc 144 for particulate emissions. This list does not mean that only these nuclides are to be detected end reported. Other nuclides with halflives greater than 8 days, that are measurable and identifiable at levels exceeding the LI.D. together with the above nuclides, shall also be identified and reported.
Note 3: Sampiing and analysis shall also be peiformed following shutdown, startup, and w henever a thermal power change exceeding 15 percent of the rated thermal power occurs withhi a one hour period, when; Analysis shows that the dose equivalent 1 131 concentration in the prhnary cooh.nt a.
has increased more than a factor of 3; and b.
'ihe noble pas 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 snown for the time 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 pe 7 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 7 days following each shutdown, startup or thermal 10wer change exceeding 15 percent of rated thermal power in one hour and analyses shall x comple:ed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of charging. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> aie analyzed, the corresponding LI.Ds may be increased by a factor of 10. This icquirement upphes if:
a.
Analysis shows that the dose equivalent 1-131 concentration in the primary coolant has increased by a factor of 3; and b.
Noble pas monitor shows that effluent activity has increased more than a factor of 3.
Note 6: To be representative of the quantities and concentrations of radioactive materials in gaseous effluents, composite sampling shall employ appropriate methods which will iesult in a specimen representative of the effluent release.
I VIRGINIA YPAl' 2103 POWillt RliVISION 2 l' AGE 65 OF i19 ATTACllMENT 11 (P.ipe 1 of 3)
NORTil ANNA RADIOACTIVE (iASEOUS WASTE SAMPl.ING AND ANAL.YSIS PROGRAM i
I' '
II'
((';'"
Type of Activity g)l,yjgi3 j'I' I Liquid Release Sampling j
- )))
1ype Irequency Frequency (pCihnl). (Note 1) l
^ ""I " "
Y (Ifa'c$i k P'I"'I "I U""""3 E'I"
'#I""'C' A. Waste Gus E
(Each Tank)
Emitters (Note 2)
IX104 I
Storage Tank Grab Sample)
Principal Gamma jx$94 E'.' ' '" ' C I""'C' E'*,II#IC"'#*
Emitters (Note 2)
- 11. Col.taintnent PURGE (Each PURGli (Each PURGE) i Grab Sampic)
II'3 IXIU*
C. Ventilation Principal Ganuna txig4 Manthly Monthly limitters (Note 2)
(1) Process Vent (2) Vent, Vent A (Grab Sample)
(Note 3) g g,3 3 gg#
j (3) Vent. Vent 11 (Notes 3,4. and 5)
Continuous Weekly 1 131 1x]o-12 (Note 4)
(Charcoal Sample)
D. All Release Continuous Weekly Principal Ganuna
,jg (Note 4)
Part culate Sample Emitters (Note 2)
Types as Monthly listed in A,
'h""i' Ccmposite Gross Alpha 1xio ll-
)
Particulate Sample 11, and C.
Quarterly Continuous Composite Sr 89. St 90 lx10-Il (Note 4)
Particulate Sample l
Noble Gases Continuous Noble Gas Gross lleta lx106 (Note 4)
Monitor or Gamma E. Cond. Air Principle Ganuna Ejector Vent We:kly Weekly Emitters (Note 7)
IAIU^
Steam Gen.
(Grab Sample) lilowdown 11-3
.1x109 Vent I?. Containment Principle Gamma g,jga Vacuum Prior to release.
Prior to each Emitters (Note 2)
Sicatu
-(Grab Sample) release Ejector 11-3 1x10+
(Ilogger)
"'7dYwn--
e w
i-m -g W g mr
$r-ww-te--
- p-w-eog-g e-ywnp w y w - + + -a me 9 yg p--
g+- we n %gvgy,k,-.,yge-%+-yty---
r-g-rwe1r--y----dev-9---ggw w'gw-'+9 wt-ww-.r-TrW-8 gp v yr u p= g=-Tvre
VilKilNIA VPAl' 2103 POWi!R Rl! VISION 2 PAO!! 66 OF i19 ATTACllMENT 11 (Page 2 of 3)
NORTil ANNA RADIDACilVE GASEOlJS WASTE SAMPI,1NG AND ANAL.YSIS PROGRAM Note 1: For a particular measurement system (which may include radiochemical separation):
Rey,1 Ll D = E + V + 2.2 2 1(
+ Y + c('Ei Where:
LI.D = the "a prioni"(trfore the fact) Lower Limit of Detection as defined atove (as miesocuries per unit mass or volume)(see 4.8) si, = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute, cpm)
H = the counting efficiency (as counts per disintegration)
V = the sample site (in units of mass or volume) 2.22 x 106 = the number of disintegrations per minute (dpm) per microcurie Ya the fractional radiochemical yield (when applicable)
A = the radioactive decay constant for the particular radionuclide At a the clapsed time letween the midpoint of sample collection and time of counting Typical values o E, V, Y and At should be used in the calculation.
r The LLD is an "a priori"(before the fact) limit representing the capability of a measurement system and not as an a "posteriori"(after the fact) limit for a particular measurement.
l
VIRGINIA VPAP-2103 IUWER REYlSION 2 PAGE 67 OF 119 ATTACllSIENT 11 (Page 3 of 3)
NORTil ANNA RADIOACTIVI' GASEOllS WASTE SAh1PLING ANI) ANAL
- ISIS PROGRAh!
Note 2: The principal panuna emitters for w hlch the LLD specification applies exclusively are the following radionuclides: Kr 87, Kr 88, Xe-133, Xe-133m, Xc 135, Xc-135m, and Xe 138 for gaseous emissions and hin 54, Fe 59, Co 58 Co 60, Zn 65, hio 99, Cs 134, Cs-137, Ce 141 arat Cc 144 for particulate emissions. This list does not mean that only these nuclides are to le detected and te torted. Other peaks that are measurable and identifiable, at levels exceeding the LL ), together with the above nuclides, shall also le identified and reported.
Note 3: Sampliag and analysis shall also be perforrned following shutdown, startup, and whenever a thennal power change exceeding 15 percent of the rated thermal power occurs within a one hour period,if:
a.
Analysis shows that the dose equivalent 1 131 concentration in the primary coolant is greater than 1.0 pCi/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 time period covered by each dose or dose rate calculation made in accordance with subsections 6.3.1, 6.3.3, and 6.3.4.
Note 5: Samples shall be changed at least once per 7 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 7 days following each shutdown, startup or thermal 3ower change exceed:ng 15 percent of iated thermal power in one hour and analyses shall ye completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of charging. 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 1.LDs may be increased by a factor of 10. This requirement apphes if:
a.
Analysis shows that the dose equivaler,t 1 -131 concentration in the primary coolant is greater than 1.0 pCi/gm and; b.
Noble gas monitor shows that effluent activity has increased more than a factoi of 3.
Note 6: Whenever the secondary coolant activity exceeds 104 pCi/ml, sam ales shall be obtained and analyzed weekiv. The turbine building sump pumps shall be p aced in manual operation and samples shall be taken and analyzed prior to release. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for pross activity or gamma isotopic activity withm 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 specification applies exclusively aie the i
following radionuclides: Kr-87, Kr 88, Xe-133, Xc-133m, Xe-135, Xe 135m, and Xe-138 for gaseous emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identinable, at levels exceeding the LLD together with the above nuclides, shall also be identified and reported.
l
... ~ - - -. - - -. _ - -. -..,..
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE 68 OF 119 NITACllMENT 12 (Page 1 of 3)
GASEOUS EFFI,UENT DOSE FACTORS FOR SURRY POWER STATION (Ganuna and lieta Dose Factors)
X/Q = 6.0E-05 sec/m3 at 499 meters N Direction Dose Factors for Ventilation Vent K vy Livy M vy Nivy i
i Noble Gas Total Body Skin GrT.T..a Air lieta Air Radionuelide
. mr em/yr.
_ mtem/yr mrad /yr mrad /yr Curie /Sec Curie /Sec Curie /See Curie /Sec Kr-83m 4.54E400 1.I6E403 1.73E+04 Kr 85m 7.02E+04 8.76E404 7.38E+04 1.18E+05 Kr 85 9.66E+02 8.04E404 1.03E+03 1.17E+05 Kr 87 3.55E+05 5.84E405 3.70E+05 6.1 HE405 Kr-88 8.82E+05 1.42E+05 9.12E+05 1.76E405 Kr-89 9.96E405 6.06E+05 1.04E+06 6.36E+05 Kr 90 9.36E+05 4.37E+05 9.78E405 4.70E405 Xe 131m 5.49E+03 2.86E +04 9.36E+03 6.66E+04 Xe-133m 1.51E+04 5.96E J4 1.96E+04 8.88E+04 Xe-133 1.76E404 1.84E+04 2.12E404 6.30E404 Xe-135m 1.87E405 4.27E4 04 2.02E+05 4.43E404 Xe-135 1.09E405 1.12E+05 1.15E+05 1.48E405 Xe-137 8.52E+04 7.32E+05 9.06E+04 7.62E+05 Xe-138 5.30E+05 2.48E405 5.53E+05 2.85E+05 Ar 41 5.30E+05 1.61 E+05 5.58E+05 1.97E405
VIROINIA VI'Al* 2103 l'OWER REVISION 2 l' AGE 69 Ol; i19 ATTACllMENT 12 (l' ape 2 of 3)
GASEOUS El?Fl.UENT DOSE l' ACTORS l'OR SURRY l'OWER STATION (Gamma and lieta Dose Factors)
X/Q = 1.0E-06 sec/m3 at 644 meters S Direction Dose Factors for l'rocess Vent Kinv I ipv Mv Nipv ip Noble Oas Totalliody Skin Gamma Air Beta Air Radionuclide mrem /yr mrem /yr mnul/JL
.in ra d/yr __
Curic/See Curie /Sce Curie /Sec Curic/Sec Kr 83m 7.56E 02 1.93E4 01 2.88E402 Kr 85m 1.17E+03 1.46E+03 1.2IE403 1.97E403 Kr 85 1.61E401 1.34E +03 1.72E+01 1.9513403 Kr-87 5.92E+03 9.73E403 6.17E+03 1.03E404 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr89 1.66E+04
- 1. ole 404 1.73E404 1.06E+04 Kr.90 1.56E+04 7.29E+03 1.63E404 7.83E403 Xe 131m 9.1 SE+01 4.76E+02 1.56E+02 1.I1E+03 Xe 133m 2.51 E+02 9.94E402 3.27E402 1.481!403 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.0$H403 Xc 135m 3.12E403 7.l lE4 02 3.36E+03 7.39E4 02 Xe 135 IflE403 1.86E403 1.92E403 2.46E403 Xe 137 1.42E+03 1.22E404 1.51E403 1.27E+04 Xe 138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E403 3.28E+03 L
...., ~.
.. ~.
VIRGINIA VPAl' 2103 POWER Hl! VISION 2 PAGl! 70 Ol' i19 ATTACllMENT 12 (Page 3 of 3)
OASEOUS EFFl UENT DOSE FACTORS FOR SURitY POWER STATION (Inhalation Pathway Dose Factors) i Ventilation Vent 7/Q = 6.013-05 sec/m at 499 meters N Direction 3
Pmeess Vent 7JQ = 1.0E-06 sec/m at 644 meters S Direction Pivv Pipv Radionuclide Jnrem/vr
.nntn(tt_
Curie /see Curie /see 113 6.75E404 1.12E403 Cr 51 5.13E+03 8.55E401 Mn-54 ND ND Fe 59 ND ND Co58 ND ND 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 3.64 E +05 6.07E+03 Te-129m 3.80E405 6.33E+03 Cs-134 ND ND.
Cs-136 ND ND Cs 137 ND ND th 140 ND ND Ce-141 ND ND Cc-144 ND ND l-131 9.75E408 1.62E+07 ND - No data for dose factor according to Reg. Guide 1.109, Rev.1.
l L
l
VIRGINIA VI'AP 2103 POWER REVISION 2 PAGE 71 OF i19 i
ATTACilMENT 13 (Page 1 of 3)
GASEOUS EFFl.UENT DOSE FACTORS FOR NORTil ANNA POWER STATION l
(Gamma and lleta Dose Factors)
X/Q = 9.3E-06 sechn3 at 1416 meters SE Direction Dose Factors for Ventilatlun Vent Kivy Livy M vy N vy i
i Noble Oas Total llody Skin Gamma Air lieta Air Radionuclide mrem /yt
. mrem /yr mradlyr.
_ mrad /yr rurie/Sec Curie /See Curie /Sec Curic/Sec Kr 83m-7.03E 01 l.79E402 2.68E+03 Kr 85m 1.09E404 1.36E404 1.14E+04 1.8311404 Kr-85.
1.50E+02 1.25E404 1.60E+02 1.81E404 Kr 87 5.51E+04 9.05E404 5.74E+04 9.58E404 Kr 88 1.37E405 2.20E+04
- 1.41 E+05 2.72E+04 Kr 89 1.54E+05 9.39E404 1.61E+05 9.86E404 Kr 90 1.45E+05 6.78E+04 1.52H405 7.28E404 Xe 131m 8.51 E+02 4.43E+03 1.45E+03 1.03E404 Xe-133m '
2.33E+03 9.24E+03 3.04E403 1.38E+04 Xc 133 2.73E+03 2.85E+03 3.28E+03 9.77E+03
' Xe-135m 2.90E+04 6.61 E+03 3.12E+04 6.87E403 Xc 135 1.68E+04 1.73E+04 1.79E+04 2.29E404 Xe-137 1.32E+04 1,13U+05 1.40E+04 1.I8E405 Xe 138 8.21 E+04 3.84E+04 8.57E+04 4,42E404 Ar-41 8.22E+04
- ..SOE+04 8.65E+04 3.05E+04
'I t
4 'v v, v-vv...
-,,,-,r-
.~e'
., _.---c.~
m,.,%,-,~ ~,,,-w w%,r r.,-,,.v w.w-,
,w,
.,,-y,,-r.,.rn-,,,,wm-E._,,w-r,-,w--v-,vwn--,--.
,,r,,r.,.--s-,y-w-,,-v
VIRGINIA VI'Al'-2103 l
l'OWER REVISION 2 l'AGli 72 01: 119 ATTACilhlENT 13 l
(l' age 2 of 3)
GASEOUS EFI'I.UENT DOSE FACTORS l'OR NORTil ANNA l'OWER STATION (Gamma and lieta Dose I; actors)
T 3
X/Q = 1.2E 06 sec/m at 1513 meters S Direction Dose Factors for l'rocess Vent Kipv Lipv Mipv Nipv Noble Gas Totaillody Skin Gamma Air lieta Air Radionnelide mrem /yr-
.mtem/yr
.mindA r mrad /yr_
Curie /See Curie /See Curie / hec Curie /Sec 2.32E401 3.46E402 Kr-83m.
9.07E 02 Kr-85m 1.40E+03 1.7511403-1.48E403 2.36E403 Kr 85 1.93E+01 1.61E+03 2.06E+01 2.34E403 Kr 87 7.10E403 1.17E404 7.40H403 1.24E404 Kr 88 1.76E+04 2.84E403 1.82E404 3.521M)3 K 89 1.99E+04 1.21E404 2.08E404 1.27E404 Kr 90 1.87E404 8.75E+03 1.96E+04 9.40E+03 Xe 131m 1.10E+02 5.7 I E+02 1.87E402 1.33E403 Xe 133m 3.01E402 1.19E+03 3.92E+02 1.78E+03 Xe-133 3.53E+02 3.67E402 4.24E402 1.26E403 Xe 135m 3.74E403 8.53E402 4.03E403 8.87E402 Xe 135 2.17E+03 2.23E+03 2.30E403 2.95E403 i
Xe-137 1.70E+03 1.46E+04 1,81E403 1.52E+04 Xe-138 1.06E+04 4.96E+03 1.11 E+04 5.70E403 Ar-41 1.06E+04 3.23E+03 1.12E404 3.94E403
VIRGINIA VI'AP 2103 IOWER kl!VISIDN 2 PAGli 73 OF i19 l
NITACllMENT 13 (Page 3 of 3)
GASEOUS EFFl.UENT DOSE FACTORS FOR NORTil ANNA POWF.R STATION (Inhalation Pathway Dose Factors)
Ventilation Vent X/Q = 9.3E 06 sec/ml at 1416 meters SE Direction 3
Process Vent X/Q = 1.21!.06 sechn at 1513 meters S Directiu l'ivv l'ipv Radionuclide jnrem/yr
.nunulyL Curie /see Curie /sec 11 3 1.0511404 1.35E403 Cr 51 7.951!402 1.02ii40' Mn.44 ND ND
]
Fe 59 ND ND Co 58 ND ND Co 60 ND ND 7a-65 ND ND Rb-86 ND ND Sr90 ND ND Y 91 ND ND Zr 95 ND ND Nb 95 ND ND Ru 103 ND ND Ru 106 ND ND Ag llom ND ND Te-127m 5.641!+04 7.28E403 Te-129m 5.88E404 7.59E403 Cs 134 ND ND Cs-136 ND ND Cs 137 ND ND Ha140 ND ND Ce 141 -
ND ND Cc 144 ND ND l 131 1.51 E408 1.95E407 ND - No data for dose factor according to Reg. Guide 1.109, Rev.1.
l
=..
i Vil(GINIA VPAl'.2103 POWElt RFVISloN 2 PAGE 74 Oli l 19 ATI ACilh11'.NT 18 (Page 1 of 2)
SURRY HAlllOACTIVE GASEOUS EFFl.UENT hlONITORING INSTRUh1ENTATION i
h11Nih1UM INSTRUh1ENT OPER Alli.E ACTION Cil ANNEl,S 1.
l'ROCl!SS VENT SYSTliht (a) Noble Oas Activity hionitor. Providing Alann and i
Autornatic Tennination of Release i
1 (b) lodine S:unpler 1
2 (c) Particulate Sarnpler 1
2 (d) Proceu Vent Flow Rate hionitor i
3 (c) Sampler Flow Rate hiemuring Device 1
3
- 2. CONDENSER AIR IUECTOR SYSTEh1 (a) Grou Activity hionitor 2 (one per unit) 1 (b) Air !!jector Flow Rate hicasuring Device 2 (one per unit) 3
- 3. VENTILATION VENT SYSTEh1 (Note 1)
Rey,1 (u) Noble Gas Activity hionitor i
I (b) h>Jine Siunpler 1
2 l
(c) Paniculate Siunpler 1
2 (d) Ventilation Vent Flow Rate hionitor 1
3 (e) Sampler i low Rate hicasuring Device 1
3 1
Note 1: One each for the Ventilation Vent 1 & 2 and Radwaste Facility Ventilation Vent effluent points-Rev.I 1
l l
_ -,.., ~. -,---__.--_,--,.-._.--..__-.i-.-.... - - - _ -. _ - - - - - _. - - _...
VIRGINIA VPAP 2103 LOWER RiiVISION 2 PAGli 75 012119 NITACilMENT 14 (Page 2 of 2)
St!RRY RAI)lOACTIVE GASEOUS EITI,UENT MONITORING INSTRUMENTATION o
ACTION 1:
If the nuinber of operable channels is less than required, etfluent seleases via this path may continue provided grab sainples 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 sarnples 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 />.
i AC110N 2:
If the number of operable channels is less than required. effluent releases via the effected path may continue provided samples are continuously collected within one hour with auxiliary sampling equipment as tequired in Attachment 8.
AC110N 3:
If the number of operable channels is less than required, effluent releases via this 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
,.nn....
,,y
VIRGINIA VI'Ali.2103 l'OWER Rl! VISION 2 l'AGB 76 Ol' 119 NITACllhlENT 15 (Page 1 of 2)
NORTil ANNA RADIDACTIVI: GASEOUS EITi.UENT MONITORING INSTRtlMENTATION MINIMUM INSTR 11MI:NT Ol'ER Allt.E ACTION Cll ANNEl.S 1.
l'ROCliSS VENT SYS111hi (a) Noble Ons Activity hionitor + l'roviding Alarrn aral Automatic Terinination of Release 1
2, 4 (b) lodine Sampler i
2, 5 (c) l' articulate S unpler 1
2, 5 (d) I'rocess Vent Flow Rate hionitor 1
1 (c) Sainpler Flow Rate hieasuring Iksice 1
1 2.
CONDENSER A1R FJIICTOR SYS'111h1 (a) Gross Activity hionitor 1
3 (b) Flow Rate hicasuring ikvice 1
1 l(cy.1 3.
VENTILNilON VENT SYS111h1(Shared with Unit 2)
(a) Noble Gas Activity hionitor 1 (Note 1) 2 (b) hiine Sarnpler I (Note 1) 2 (c) Particulate Stunpler I (Note 1) 2 (d) Flow Rate hionitor 1 (Note 1) 1 (e) Samplet Flow Rate hicasuring Device 1 (Note 1) 1 Rey,1 Note 1: One per vent stack
- _.-. _. _. ~
VIRGINIA VPAP 2103 POWillt itliVISION 2 PAOli 77 OF 119 NITACllMIONT 15 (Page 2 of 2)
NORTil ANNA HAI)lOACTIY10 GASICOllS I?Fiti.lil:NT MONITOHING INSTHl1 MENTATION ACrlON 1:
If the number of operable channels is less than saluiral, elfluent releases via this path may continue provided the flow rate is estinutal at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACrlON2:
If the numter of operable channels is less than tequhed, effluent releases via this pathway 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 me analyzal for gross activity or ganuna isotopic activitv 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 pathway nuy contmue provided the frequency of the grab samples required by Technical Specification requirement 4.4.6.3.b is increased to at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and these samples are analyzed for pross activity or ranuna isotopic activity within H hours.
ACI'lON 4:
If the numler of olvrable channels is less than rnluired, the contents of the Waste Gas Decay Tanks may be released to the environment provided that prior to initiate the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the Station Staff independently verify the release rate calculan,ons and disc harge valve lineup; 7
Otherwise, suspend release of Waste Oas Decay Tank elfluents.
' ACrlON 5:
If the number of operable channels is less than required, effluent releases from the Waste Gas Decay fanks may continue provided samples are continuously collected with auxiliary sampling equipment as requiralin Attachment 11.
---m--_,
..w,wng-.,
,...,,np-.-cy,,
,,,, - m,
,.,,.---,.--.,.,----w-,-
Vil(GINIA VI'Al'.21(O IUWi!R ltliVISION 2 l'AGI: 7S 01' 119 ATTACllSil:NT l(i (l'. ige 1 of 1)
StillitY lt ADIDACTIVI: (i ASI:OllS 1:l'I'l.111:NT NIONITOl(IN(i INSTittihil'NTATION StiltVI:ll.i. ANCI: 1(l'()llll(1:Sil:NTS CII AbNI I' l(cv.1Cil A NNI:1, Cil A N NI:1.
hot!!!OI; Cll A NNI:1.
I'. t I
NA Dl:N C it ill l O N Clli:t h Clll-:CK C A l.Illit Cl ION
, g 1.
l'110CI:SS VI'.N1 SYSTI:ht (a) Noble Gas Aethity hionitot. l'uniding Alariri atul Autoritatic Teritiiiottnisi of llelease 11 hi. '
It Q
tb) latine Sanipler W
N.A.
N.A.
N.A.
(c) l' articulate Satnpler W
N.A.
N.A.
N.A.
(d) l'rocess Vent 1 low l< ate hionitor D
N.A.
It N.A.
(c) S;unpler I' low Itate hicaturing Device D
N.A.
SA Q
ROV I 2.
CONDI:.NSI.it Allt UlrlOlt SYSilihi (a) Grow Aethily hionitor D
h1 11 Q
(b) Air Iljet tot 1: low Itate hicasuring D
N.A.
11 N.A.
Ikvisc 3.
VENTil ATION VINI'SYSTl:N1 (a) Noble Gas Activny hionitor D
h1 it Q
(b) laime Sampler W
N.A.
N.A.
N.A.
(c) I'.ath ulate S:unpler W
N.A.
N.A.
N.A.
(d) Ventilanon Vent I: low Itate hionitor D
N.A.
11 N.A.
(
(e) Sampler I' low Itate hicasuring Devise D
N.A.
SA y
lg k
ir l.'
- l'I'iOT to CACI) Waste Gas Deca)' Taiik relt.ase r
VIRGINIA VI'AP 2103 l'OWliR Rl!VlSION ?
i l'AGli 79 01: 119 ATTACllh!ENT 17 (l' ape 1 of 2)
NORTil ANNA RADIOACTIVE GASEOt1S 1:lfl?l.t1ENT h!ONITORING INSTRllalENTATION StJHVEll.i.ANC10 REQlllREh!ENTS
- CllANNEl, CilANNEl, CllANNEL SOURCl:
Cil A NN t:1.
l' UNCI NA DESCHIPTION Cill:CK C lll'.C K C Al.IllR A TION 1.
PROCESS VENT SYSTEh!
(a) Noble Gas Artisity hionitor hosiding Alarm and Automatic Termirutitui of Release D
l' R
Q (Note 1)
T
- (b) lodine Sampler W
N.A.
N.A.
N.A.
[
(c) Particulate Sampler W
N.A.
N.A.
N.A.
j (d) Process Vent Flow Rate Monitor
'D N.A.
R Q
(c) 5:unpletIlow Rate Measuring Device D (Note 3)
N.A.
SA N.A.
Re% 1 i
- 2. CONDENSER AIR FJECTOR SYSTEM (a) Noble Ons Activity Monitor D
M R
Q (Note 2)
(b) Flow Rate Measuring Device D
N.A.
R N.A.
Rev.1 3.
VENTILATION VliNT SYSTl!M (Shared with Unit 2)
(a) Noble Gas Activity Monitor D
M R
Q(Note 21 (b) latine Sampler W
N.A.
N.A.
N.A.
(c) Partleulate Sampler W
N.A.
N.A.
N.A.
(d) Flow Rate Monitor D
N.A.
R Q
(c) Samples Flow Rate Measuring Device D (Note 3)
N.A, SA N.A.
Rev.1 m
- - -w,.rt-ce t w-ee e-.
--v,.--
,-rwm,v-,7%---,m--m,.
---,mm,----q
-wr-,.e.-,-.-,.e,,v-ve.sm
--.--y.
.rr-v-
-.a-+vw-irv--r--%ve
-s--e.~---=--e-r=+*w-e e-v
VIRGINIA VPAP 2103 POWER RiiVISION 2 PAGE 80 OF 119 f
9 ATTACllhlENT 17 (Pape 2 of 2)
NORTil ANNA RADIOACTIVE GASEOt!S EFFl.t1ENT AlONITORING i
INSTHtJS1ENTATION SURVEll.l.ANCE REQUlHEhlENTS l
Note 1:
The Channel Functional Test shall also demonstrate that automatie isolation of this pathway and contn.! room alarm annuncias' 1 occur if any of the following, conditions exists:
i
- a. Instrument indicate measured levels above the alam1/ttip selpoint.
- b. Instrument controls not set in operate mode.
Note 2:
The Channel Functional Test shall also demonstrate that control room alarm annunciation occurs if any of the idlowing conditions exists:
- a. Instrument indicates measured levels above the alarm setpoint.
- b. Instrument controls not set in operate mode.
Note 3:
Channel Checks shall consist of verifying indication of How 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, periodie, or batch releases are made.
VIRGINIA Vl'Al' 2103 l'OWiiR Rl! VISION 2 l'AGli 8101: 119 ATI'ACllMI:NT IN (l' age i of 2)
CRITICAL ORGAN AND INilAl,ATION DOSI: I? ACTORS FOR SURRY (Critical l'athway Dose 1: actors)
Ventilation Vent D/Q = 9.0l! 10 nr2 at $150 incters S Direction l'iocess Vent D/Q = 4.3E 10 in 2 at $150 meters S Direction RM vy RMipv i
Radionuclide antern/vr Jnit111/JL Curie /sce Curic/see 11 3 7.20l!402 3.121?+02 Mn54 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 St-90 ND ND Y 91 ND ND Zr 95 ND ND Nb 95 N';
ND Ru 103 ND ND Ru-106 ND ND Ag-ll0m ND ND Te-127tn 8.0613404 3.851!404 Te-129m 1.25E+05 5.98E404 1 131 6.21E408 2.9711408 Cs 134_,
ND ND Cs-136 ND ND Cs 137 ND ND lla-140 ND ND Ce 141 ND ND Cc-144 ND ND ND - No data for dose factor according to Reg. Guide 1,109, Rev.1.
l t
[,_..__._,..
VIRGINIA VI'Al' 2103 IOWER Rl! VISION 2 l'AGli 82 OF 119 i.
NI'TACilMENT 18 (Page 2 of 2)
CRITICAL, ORGAN AND INilAI ATION 1)DSE L'\\CTORS FOR SURRY (Inhalation Pathway Dose Factors) i Ventilation Vent X/Q = 3.0E-07 sec/m at $150 meters S Direction 3
Process Vent X/Q = 1.3E 07 sechn at $150 meters S Direction
' 'iyy Riipv Radionuclide mil 1L
.nue m/yr.
Curic/sec Curie /sec
~
11 3 1.94E+02 8.41E401 Cr-51 1.7311+01 7.4815400 Mn 54 ND ND Fe-59 ND ND
~
Co 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 1.4611403 6.33E+02 Te-129m 1.64E403
- 7. I 21?+02 t
1-131 4.45E406 1.93E+06 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 according to Reg. Guide 1.109, Rev.1.
l
YlRGINIA Vl'Al' 2103 IOWiiR RiiVISION 2 l' AGE 83 01: 119 NITACllMINI' 19 (l' age 1 of 1)
CRITICAL, ORGAN DOSE I? ACTORS FOR NORTil ANNA Rev.1 (Critical l'athway Dost Factors)
Ventilation Vent D/Q = 2.4E 09 nr2 at 32$0 nieters N Direction l'rocess Vent D/Q = 1.11! 09 nr2 at 32$0 meters N Ditection Rivv Ripv Radionuclide
_nuem/vr
.lurem/vr Cutie /see Curie /see H3 1.7313 +03 9.36B402 Mn 54 ND ND Fe 59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb 86 ND ND Sr89 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 3
Te-127m 1.97E405 9.04E404 Te 129m 2.95E+05 1.35E405 1131 1.45E+09 6.72E+08 Cs 134 ND ND Cs 136 ND ND
~
Cs 137 ND ND i-13a-140 -
ND ND Cc-141 ND ND Ce-144 ND ND ND No data for dose factor according to Reg. Guide 1.109, Rev.1.
I i-l'
.._.,l.....__.,..
,._4 s.-_.
VIRGINIA VPAP-2103 POWiiR RiiVISION 2 PAGli 84 OF i19 NITACllh1ENT 20 (Page 1 of 2)
SURRY HADIGI,0GICAl, ENVIRONhlENTAl. A1PNITORING l'ROGRAh!
Exposure Pathway Number of Sample and Collectlun Type and 1'requency of und/or Snmple Sample 1,ucation 1'requency Analysis
- 1. DIRECT RADIATION About 40 Routine Monitoring stations to tv placed as follows:
- 1) Inner Ring in general area of site boundary with station in each sector.
GAMMA DOSE
- 2) Outer Ring 6 to 8 km Quarterly Quanerly from the site with a station in each sector 3)The balance of the 8 dosimeters should be placed in special interest areas such as population centers nearby residems, schools, and in 2 or 3 areas to serve as controls.
- 2. AIRilORNE Samples from 7 locations:
a) I sample from clo e to Hadiciodine Cannister the site boundary location of the highest 1131 Analysis Weekly calculated annual-average ground level Continuous hgdcuhte Sampkt DS.
Sampler Gross twta radioactivity Radiciodines and Particulates b) 5 sample locations 6.g operata)n wnh analysis following filter km distance located in a sample collection change; concentric ring around
- weekly, Station.
Gamma tsotopic
"" 1 *i' f ' *P *i'#
Y I samP e from a control (by location) quarterly l
c) location 15 30 km dhtant, providing valid background data.
-,---.-,--,,~,,-.~...m.-,
~.----m%
vce.
.-,wy,-----,,.-_.,n,...-,,-er
,,,e,.,<..,.,
+.
e,-+,
VIRGINIA VPAP-2103 IOWER RiiVISION 2 l' AGE 85 01; 119 A'ITACithlENT 20 (Page 2 of 2)
SURRY RADIGI.OGICAl ENVIRONMENTAL, MONITORING PROGRAM Espmure Pathway Number of Sainple and Collection Type and l'requency of and/or Sample Sainple 1.ucation l'requency Analysis
- 3. WATERilORNE Ganuna isotopic analysis a) I sample upsucam monthly; a) Surface hionthly Sample Compos.te for tritniin b) I sample downstream i
analysis quarteily, ind tritiuin b) Ground Sample from 1 or 2 sources Quanctly l "{3 sis a
r' t fimn G in1: i iic analysh Cf "; g C) ra t i e i it Semi-Annually potential reercational value 0 * '"P.#' II
- YICI"IIF I Ganuna iwtopic analysis I
Semi Annually semi annually d) Silt the Station
- 4. INGliSTION a) 4 samples from milking animals in the vicinity of
- Station, a) Milk b) I sample from milking Monthly "fn')
- i t1-animals at a control-location (15 30 km distant)
[0i i ith of t$i $t tionIli M nthly Ganuna isotopic on edibles b) 5 samples of clams in the vicinity of the Ili Monthly Gamma isotopic on edibles Station.
b) Fish and c) I sampling of crabs invertebrates from the vicinity of the Annually Ganuna isotopic on edibles Station.
d) 2 samples of fish from I "
( $thfi I h te I er !,
Semi-Annu lly Gamma isotopic on edibles cel) a) I sample corn p
n Hble c) Food Products b) I sample soybean Annually rti si c) I sample peanuts
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 86 OF 119 i'
ATTACllhll?NT 21 l
(Page 1 of 4)
NORTil ANNA HADIGI.OGICAls ENVIRONhlENTAI, h!ONITORING l_
PROGR A h1(Note 1)
Exposure Pathway Number of Sample and Collection T pe and Frequency of 3
i and/or Sample Sample Location (Note 2)
Frequency Analysis 1, DIRECT RADIATION i
(Note 3) i 36 routine monitoring i
stations either with two or more dosimeters or with one instrument for measuring and recording dse rate continuously to be placed as follows:
- 1) An iner ring of staions, one in each n.eteorological sector i
within the site boundary.
GAhih1A DOSE
- 2) An outer ring of Quarterly Quanerly stations, one m each meteorological sector within 8 km range from the site
- 3) The balance of the stations to be placed in j
specialinterest areas i
such as population i
centers, nearby residences, schools, and in 1 or 2 areas to sene as control stations, e.
~. -
--=
~
VIRGINIA VPAP-2103 POWER REVISION 2 PAGli 87 OF 119 ATTACilhlENT 21
-(Page 2 of 4)
NORTil ANNA RADIOL.OGICAl, ENVIRONhlENTAl, AlONITORING PROGRAh!
Exposure Pathway Number of Sample and Collection Type and Frequency and/or Sample Sainple 1.ocation(Note 21 l'requency of Analysis
- 2. AIRBORNE Samples from 5 locations:
a) 3 samples from close to the 3 site boundary Endioiodine Cannister locations (in different sectors) of the highest 1-131 analysis, weekly calculated historical annual average ground Continuous Particulate Samol t t
level D/Q.
- sampler, Rev.1
[l(n I'ty analysis Radioic dines and N1 h honi k operation with vicinity of a community sample collection following filter having the highest weekly change; (Note 4) calculated annual average ground level Gamma isotopie D/Q.
at.alysis of composite c) I sample from a control (by location) location 15-40 km quarterly (Note 5) distant and in the least prevalent wind direction
- 3. WATERBORNE Samples from 3 locations:
Gamma isotopic analys.is I 33*P C UP'l'C"*
monthly. (Note 5)
Res,.,
I "I
a) Surface Grab hionthly b-) I sample downstream Composite for uitium c) I sample from cooling analysis quarterly.
lagoon Sample from I or 2 sources Gamma isotopic and b) Ground only if likely to be affected.
Grab Quarterly tritium analysis quanerly (Note 5) 1 sample from downstream Gamma isotopie analysis c) Sediment area with existing or Semi-Annually potential recreational value semi-annually (Note 5) l l
VIRGINIA VPAP-2103 POWER RI' VISION 2 PAGE 88 OF 119 ATI'ACllMENT 21 (Page 3 of 4)
NORTil ANNA RADIOL.OGICAl, ENVIRONMENTAI, MONITORING PROGRAM Exposure Pathway Number of Sample and Collection Type nnd Frequency of and/or Sample Sample 1.ocation(Note 2)
Frequency Analysis 4, INGESTION a) Samples from milking animals in 3 locations within 5 km distance having the highest dose potential. If there are none, then, I sample from milking animals in each of 3 areas between 5 to 8 km distant Monthly at Gamma isotopic (Note 5) a) M;1k(Note ?)
where doses are calculated all times.
and 1-131 analysis to be greater than 1 mrem monthly.
per yr. (Note f4 b) I sample from milking animals at a controllocation (15-30 km distant) and in the least prevalent wind direction).
a) I sample of commercially and recreationally important species (bass, sunfish,
- b. Fish and catfish)in vicinity of plant Semiannually Gamma isotopic on edible Invertebrates discharge 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 ground level D/Q if milk sampling is not Monthly if Gamma isotopic (Note 5) c) Food Products performed.
available, or and 1-131 analysis, b) I sample of broad leaf at harvest vegetation grown 15-30 km distant in the least prevalent wind direction if milk sampling is not performed
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 89 OF 119 ATTACilh1ENT 21 (Page 4 of 4)
NORTil ANNA RADIOLOGICAL ENVIRONhlENTAL S10NITORING PROGRAh!
Note 1: The number, media, frequency, and location of samples may vary from sitt to site. This table presents an acceptable minimum program for a site at w hich each entry is applicable. Local site characteristics must be examined to detennine if pathways not covered by this table may significantly contribute to an individual's dose and be in:luded in the sampling program.
Note 2: For each and every sample kication 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 pennitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons, if specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to 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 6.6.1. 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 alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 d;js in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to 6.6.2, identify the cause of the unavailability of samples for that pathway and identify the new locations for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Repon and also include in the report revised figures and tables from the ODCM reflecting the new locations.
Note 3: One or more instruments, such as a pressurized ion chamber, for measuring ad recording Jose rate 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 Rev.I 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 wiected to obtain optimum dose infomtation with minimal fading.
Note 4: Airborne particulate sample filters shall be analyzed for gross oeta 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 thoren daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma t
isotopic analysis shall be performed on the individual samples.
l Note 5: Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the 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 (Pg. 3 of 4, Attachment 21) l l
m,r J.-
A 4
emJ K
==iJ-+4-[b+4f.=R.44eb2.-D A J J44"h
/-. --.
,,-4 S-i
$--n-.q--
=M.,,4-,m3
-,r.1 J
4 #
4..,.
A.+A.-m-4M-..E,.e
-*-4*-ma*A.1...AJ>Aa.iimAs A
-,-42-eE s
-A.mih4._m.m344. 4_M i
- VIRGINIA VPAP-2103 POWER-REVISION 2 PAGE 90 OF 119 ATTACllMENT 22 (Page 1 of 4)
SURRY ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE LOCATION DISTANCE DIRECTION REMARKS M EDI A--
(MILES)
Site Boundary Air Charcoal and Surry Station (SS) 0.37 NNE Location at Sector Particulate with liighest D/Q Hog Island Reseire (HIR) 2.0
.N N E Bacons Castle (BC) 4.5 SSW Alliance (ALL) 5.1 WSW Colonial Parkway
-(CP) 3.7 NNW Dow Chemical (DOW) 5.1 ENE Fort Eustis (FE) 4.8 ESE Newport News
- (NN) 16.5 ESE Control Location Environmental Control -
(00)
Onsite **
TLDs West North West (02) 0.17 WNW Site Boundary Surry Station Discharge 0.6 NW Site Boundary (03)
North North West (04) 0.4 NNW Site Boundary North (05) 0.33 N
Site Boundary North North East (06) 0.28 NNE Site Boundary North East (07) 0.31 NE Site Boundary East North 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 2 PAGE 91 OF 119 1
NITACllh1ENT 22 (Page 2 of 4)
SURRY ENVillDNh1 ENTAL SAh1PI,1NG I.OCATIONS SAh1PLE LOCATION DISTANCE DIRECTION REh1 ARKS
.h1EDIA
- (h11LES)
Environmental Bacons Castle (20) 4.45 SSW Approx. 5 miles TLDs Route 633 (21)
- 3.5 SW Approx. 5 i ailes Alliance (22) 5.1 WSW Apprcx. 5 uiles Surry (23) 8.0 WSW Population Center-4 Route 636 and 637 (24) 4.0 W
Approx. 5 miles Scotland Wharf (25) 5.0 WNW Approx. 5 miles Jamestown (76) 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--
i.
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 -
hiilk lee Hall 7.1 ENE-Epp's 4.8 SSW Colonial Parkway 3.7 NNW--
Judkin's 6.2 SSW-William's 22.5 S
Control Location L
i i
l t
i
.. +,
.... ~,
.. ~.
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 92 OF i19 ATTACllhlENT 22 (Page 3 of 4)
SURRY ENVIRON 51 ENTAL, SAhlPl.ING 1.OCATIONS SAMPLE I.OCATION I)lSTANCE DIRECTION R Ehl A R KS hlEI)lA (Sill.ES)
Well Water Surry Station Onsite * *
- l-log Island Reserve 2.0 NNE Bacons Castle 4.5 SSW Jamestown 6.3 NW Slade's Farm 2.4 S
State Split Crops
(
Br ek's Farm 3,8 S
State Split 3, an )
Poole's Garden 2.3 S
State Split Crops Carter's Grove Garden 4.8 NE State Split (Cabbage, Kale)
C ntr Ilaation Ryan's Garden (Chester, \\ a.)
River Water Surry Station intake 1.9 ESE (Bi-monthly) llog Island Point 2.4 NE Newport News 12.0 SE Chicahominy River 11.2 WNW Control 1.ocation l
Surry Station Discharge 0.17 NW River Water Surry Discharge 0.17 NW (Monthly)
Scotland Wharf 5.0 WNW Control Location Sediment (Silt)
Chicahominy River 11.2 W N'W Control Location Surry Station intake 1.9 ESE Surry Station Discharge 1.0 NNW 11og Island Point 2.4 NE Point of Shoals 6.4 SSE Newport News 12.0 SE
VIRGINIA VPAP.2103 POWER REVISION 2 PAGE 93 OF 119 ATTACilhlENT 22 (Page 4 of 4)
SURRY ENYlltONh1 ENTAL. SAhlPI,1NG I.OCATIONS SAhlPI E I.OCATION DISTANCE DlitECTION lil'51 A R KS hlEDIA (h111.ES)
Clams Chicahominy River 11.2 WNW Control Location Surry Station Discharge 1.3 NNW liog Island Point 2.4 NE Jamestown 5.1 WNW Lawne's Creek 2.4 SE Oysters Deep Water Shoals 3.9 ESE Point of Shoals 6.4 SSE Newport News 12.0 SE Crabs Surry Station Discharge 0.6 NW Fish Surry Station Discharge 0.6 NW Shoreline llog Island Reserve 0.8 N
Sediment Burwell's Bay 7.76 SSE Onsite Location -in Lead Shield Onsite sample of Well Water - taken from tap-water at Surry Environmental Building.
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 94 OF 119 ATTACilhlENT 23 (Pape 1 of 4)
NORTil ANNA ENVIRONhlENTAl, SAhlPI,1NG 1.OCATIONS Distance and I)irection From Unil No. I Sample 1.ocation Station Distance Direction Collection It EM A R KS Media No.
(Miles)
Frequency NAPS Sewage Treatment 0" ""I N
01 0.20 NE Y
On-Site Environmental Plant Annually D8 0""""I N
Frederick's Itt!! -
02 5.30 SSW Y
Annually 0" ""I N Y
Minend,YA 03 7.10 WSW Annually O**1"I N Y
Warcs Crossrasts 04 5.10 WSW Annually O*'""I N
Y Route 752 05 4.20 NNE Annually Sturgeon's Creek Marina 05A 3.20 N
Qu rterly&
Annually 0""""IY N Levy, VA 06 4.70 ESE l
Annually Bumpass, VA 07 7.30 SSE Quanaly &
Annually End of Route 685 21 1.00 WNW Quarterly &
Exclusion Annintily Boundry Route' 700 22 1.00 WSW Quarterly &
Exclusion -
Annually Botuutary
" Aspen Ilills" 23 0.93 SSE Quarterly &
Exclusion j
1 Annually Bomskiry 0""""I N Y
Control Orange, VA 24 22.00-NW Annually Bearing Cooling Tower N 1/33 0.06 N
Omuterly On-Site Sturgeon's Creek Marina N-2/34 3.20 N
Quanerly p
Parking let "C" NNE-3/35 0.25 NNE Quanerly On Site L
Good flope Church NNE-4/36 4.96 NNE Ottuterly Parking Lot "B" NE-5/37 0.20 NE Qwuterly On-Site Lake Anna Marina NE-6/38 1.49 NE Qututerly l
Weather Tower Fence ENE-7/39 0.36 ENE Quarterly On-Site Route 689 ENE.8/40 2.43 ENE Quarterly Near Training Facility E-9/41 0.30 E
Quanerly On-Site
. ~. _. _ -. _.. _. - _ - _. _ _...., _. _. _
VIRGINIA VI'Al'-2103 POWER RiiVISION 2 l'AGI! 95 OI: 119 ATTACilhlENT 23 (Pape 2 of 4)
NORTil ANNA ENVIRONhlENTAl SAhlPl.ING 1.OCATIONS I)istance and 1)irection l'roin Unit No. I Sample
- 1. oration Station Distance Direction Collection REM AltKS hiedia No.
(Miles)
I'requene)
Environmental
" Morning Glory llill" E-10/42 2.85 E
Qtruterly TLDs Island Dike ESE-11/43 0.12 ESE Qu:u1erly On-Site (cont.)
Route 622 ESE-12/44 4.70 ESE Ottuterly 1
11iology Lab SE 13/t5 0,75 SE Quarterly On-Site Route 701 (D.un Entrance)
SE-14/46 5.88 SE Qu:uterly
- Aspen ilills" SSE-15/47 0.93 SSE Qttuterly Exclusion iloinduy Elk Creek SSE-16/48 2.33 SSE Otsu1erly Rey, I Warehouse Compound S 17/49 0.22 S
Qu.uterly On-Site Gate Elk Creek Church S 18/50 1.55 S
Ottuterly NAPS Access Road SSW-19/51 0.36 SSW Quanctly On-Site Route 618 SSW-2(V52 5.30 SSW Quanerly gey,1 NAPS Access Road SW-21/53 0.30 SW Quanerly On-Site Route 700 SW-22/54 4,36 SW Quanerly 5(K) KV Tower WSW 23/55 0.40 WSW Quarterly On Site Route 700 WSW 24/56 1.00 WSW Quarterly Exclusion Bourdiry NAPS Radio Tower W 25/57 0.31 W
Quarteily On-Site Route 685 W 2458 1.55 W
Qiculerly End of Route 685 WNW 27/59 1.00 WNW Quarterly Exclusion Ihwrduy
- 11. Purcell's Private Road WNW-28/N1 1.52 WNW Otutrterly Rev.1 Eral of #1/#2 Intake NW-29/61 0.15 NW Quanerly On-Site Lake AnnaCampground NW 30/62 2.54 NW Quarterly
- 1/#2 Intake NNW-31/63 0.07 NNW Quarterly On-Site Route 208 NNW-32/M 3A3
-NNW Quarterly Humpass Post Of0cc C-1/2 7,30 SSE Quarterly Control Orange, VA C-3/4 22.00 NW Quanerly Control Mineral. VA C-5/6 7.10 WSW Quarterly Control Louisa, VA C-7/8 11.54 WSW Quarterly Control
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 96 OF i19 ATTACllMENT 23 (Page 3 of 4)
NORTil ANNA ENVIRONMENTAL. SAMPI,1NG 1.OCATIONS I)istance and 1)irection From Unit No. I Sample Location Station Distance Direction Collection llEM Alt KS Media No.
(htiles)
Frequency NAPS Sewage 01 0.20 NE W a kly On-Site Airborne Treatment Plant Particulate Frederick's llall 02 5.30 SSW Weekly and hiineral. V A 03 7.10 WSW Weekly Ratioiodine Wares Cmssants 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 Exclusion Boundary Route 700 22 1.00 WSW Weekly Exclusion Boundary
" Aspen Hills' 23 0.43 SSE Weekly Exclusion Boun&ry Orange, V A 24 22.00 NW Weekly Control Waste lleet Treatment Surfre Facility (Second Cooling 08 1.10 SSE hionthly Water Lagoon)
North AnnaRiver (upstream) Rt 669 liridge 09A 12.9 WNW hionthly Control (Brook's Bridge)
Rev.2 North Anna River 11 5.80 SE Monthly Rev.1
((k)wnstream)
- ", ' "j' Biology Lab OlA 0.75 SE Quarterly g
Waste lleat Treatment Facility (Second Coolmg 08 1.10 SSE Semi-Annually Aquatic Lagoon)
Sediment Nont e ia River 09A 12.9 WNW Semi-Annually Control riey* 1 (upstream) Rt 669 Bridge
~
(Brook's Bridge)
North AnnaRiver 11 5.80 SE Semi-Annually (downstream)
Shoreline Soil Lake Anna (upstream) 09 2.20 NW Semi-Annually Soil 01 0.20 NE Once per 3 yrs On-Site Tr tm -
I nt l
l
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 97 OF i19 ATTACilhlENT 23 (Page 4 of 4)
NORTil ANNA ENVIRON 41 ENTAL SAh1Pl.ING LOCATIONS I)istance and Direction From Unit No. I Sample Location Station Distance Direction Collection REhl A R KS hledia No.
(hlites)
Frequency Soil Fredericks Ild!
02 5.30 SSW Once per 3 yrs Rev.1 (cont.)
hiineral, VA 03 7.10 WSW Once ter 3 yrs Wares Crossnxxis (M
5.10 WNW Once Irr 3 yrs Route 752 05 4.20 NNE Once per 3 yrs Sturgeon's Creek h1arina 05A 3.20 N
Once per 3 yrs Rev.1 Levy, VA 06 4.70 E aE Once Irr 3 yrs Bumpass, VA 07 7.30 SSE Once per 3 yrs End of Route 685 21 1.00 WNW Once per 3 yrs Exclusion floundary Route 700 22 1 00 WSW Once per 3 yrs Exclusion Boundary
" Aspen Hills" 23 0.93-SSE Once per 3 yrs Exclusion floundary Orange, VA 24 22.00 NW Once per 3 yrs Control Holladay Dairy 12 8.30 NW hionthly hiilk (R.C. Goodwin) 8
?, c 3 3[di) 13 5.60 SSE hionthly Waste lleat Treatment Facility (Second Cooling 08 1,10 SSE Semiannually Fish.
Lagoon)
Rev.1-Ide Orange 25 16.50 NW Semiannually Control Route 713 14 varies NE Food Products Route 614 15 varies SE hionthly (Broad Leaf Route 629/522 16 varies NW if an.ilable,or Control vegetation)
Route 685 21-varies WNW at harvest
" Aspen Ilills" Area 23 varies SSE
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 98 OF i19 ATTACilh1ENT e4 (l' age 1 of 2)
DETECTION CAPAlllLITIES FOlt SURRY STATION ENVIRONhlENTAI, SAhll'LE ANALYSIS (Note 1)
LOWER Lih11T OF DETECTION (LLD)
Airborne F,ood Sediment Water Particulate Fish h1 ilk Analysis l'roducts (pCl/kg)
(pCill) or Gases (pCi/kg)
(pCi/l)
(pCi/kg)
(wet)
(N te 2)
(pCi/m3)
(wel)
(wet)
Gross beta 4
0.01 113 2,000 hin-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 l
Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 Note 1: Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are givu 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.
I
i VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 99 OF 119 ATTACllhlENT 24 (Page 2 of 2)
DETECTION CAPAlllLITIES FOR SURRY STATION ENVIRONh1 ENTAL SAhlPLE ANALYSISWote O LOWER Lih11T OF DETECTION (LLD)
Note 1: For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD =
E. V. 2.22 x 106, y. exp (- A A)
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) sd = the standard deviation of the background counting rate or of the counting nite of a blank sainple as appropriate (as counts per minute, cpm)
E = the counting efficiency (as counts per disintegration)
Rev.I V = the sample size (in units of mass or volume) 2.22 x 106 = the number of disintegrations per minute (apm) 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)
Typical values of E, V, Y and At shoulti 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 an a "posteriori" (after the fact) limit for a particular measurement.
VIRGINIA VPAP.2103
- POWER REVISION 2 PAGE 100 OF 119 ATTACilhlENT 25 (Page 1 of 2)
DETECTION CAPAlllLITIES FOR NORTil ANNA STATION ENVIRONhlENTAl.
SAhlPLE ANALYSIS (Note 1)
LOWER LIhllT OF DETECTION (1.1.D)-
Airborne Water Particulate Fish hillk Pr >h ' cts' ' i'"h')'
Analysis i'i (pCi/l) or Gases (pCi/kg)
(pCill)
(pCi/kg)
(wet)
(Note 2)
(pCi/in3)
(wet)
(weg Gross beta 4
0.01 11-3 2,000 Mn-34 15.
130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 l
l-131 (Note?) 1 0.07 1
- 60 gey, g-
- Cs-134 15-0.05 130 15 60 150 Cs;137-18 0.06 150 18
-80 180 Ba La-140 15 15 Note 1: - This list does not (nean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.8.
- Note 2: This LLD value is for drinking water samples.
1 1
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 101 OF 119 ATTACllh1ENT 25 (Page 2 of 2)
DETECTION CAPAllil.ITIES FOR NORTil ANNA STATION ENYlRONh1 ENTAL SAh1PLE ANAIJSIS(Note 1)
LOWER I.th11T OF DETECTION (LI.D)(Note 3)
Note 3: For a particular measurement system (which may include radiochemical separation):
4.66 sh LLD =
E. V 2.22 x 106. y.exp(.xA)
Where:
LLD = the "a priori"(before the fact) Lower Limit of Detection as defined almve (as microcuries per unit mass or volume)(see 4.8) sh = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute, cpm)
E = the counting efficiency (as counts per disintegration)
Rev.I V = the sample size (in units of mass or volume) 2.22 x 106 = 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 clapsed time between sample collection (or end of the sample 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) 1imit representing the capability of a measurement system and not as an a "posteriori" (after the fact) limit for a particular measurement.
l
!t-l l
_. _. ~. _....
VIRGINIA VPAP-2103 POWER RiiVISION 2 PAGE 102 OF 119 l
ATTACilhlENT 26 (Page1of1)
REPORTING LEVEL S FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONhlENTAI. SAhlP12S AT SURRY STATION Airborne I ' 'I p,.,,"g [, (,, 3 Analysis ater Particulate Fish hlilk (ptill)
.or Gases (pCi/kg, wet)
(pCill)
(pCihn3)
(pCl/kg, wet)
Il-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 Da-La 140 200 300 Note 1: - Reporting level for the ground (drinking) water samples required by Attachment 20. The reporting level for the surface (non-drinking) water samples required by Attachment 20 is 20 pCi/1.
- - ~. ~. -. -.
~.
LV IR G'I NIA.
VPAP-2103 LOWER REVISION 2 PAGE 103 OF 119 ATTACilh1ENT 27 (Page1of1)
REPORTING LEVEL.S FOR RADIOACTIVITY CONCENTRATIONS IN ENYlRONh1 ENTAL, SA51Pl.ES AT NORTil ANNA STATION 1
Airborne Food
- Water Particulate Fish 51llk Analysis (pCill) or Gases (pCl/kg, wet)
(pCill) gp[,;/"','C[*
,, )
(pCihnh H-3 20,0(X)0)
Mn-54 1,000 30,000 I
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 water samples.
L nn.,- - - - -, --e
,,.-.---,,e
...---.,,.-~<,n-,-
,n.r-
.c,-
m e
VIRGINIA VPAP-2103
-t POWER REVISION 2 PAGE 104 OF 119 ATTACllhlENT 28 (Page 1 of 8)
SURRY AIETEOROI.OGICAl., I.lQUID AND GASEOUS PATilWAY ANAL,YSIS 1,0 51ETEOROI.OGICAl, ANAL,YSIS 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 hieteorological Data, Parameters, and Slethodology Onsite meteorological data for the period January 1,1979, through December 31,1981, was used in calculations. These data included wind speed, wind direction, and differential temperature for the purpose of detennining 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 AT158.Pti-28.2ft ana 28.2 foot wind data, and the portions characterized as mixed mode were based on ATtsgsti.28.2ii and 158.9 ft wind data.
X/Q's and D/Q's 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 airtlow 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 l
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 Hat 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 ',16 m2 containment minimum cross-sectional area. The effective release height used ir e axed mode release calculations was based on a process vent release height of 131 ft, and p urne rise due to momentum for a vent diameter of 3 in. with plume exit velocity of 100 ft/sec.
l'
m VIRGINlA VPAP-2103 POWER REVISION 2 PAGE 105 OF 119 ATTACllMENT 28 (Page 2 of 8)
SURRY METEOROI.OGICAl., I.lQUll) ANI) G ASEOUS PATilWAY 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 I and 2 Virginia Electric and Power Company Updated Final Safety Analysis Report Table 1 I A 11.
X/Q and INQ values were calculated for the nearest site boundary, resident, milk cow, and vegetable garden by sector for process vent and ventilation vent releases. X/Q values were also calculated for the nearest discharge canal bank for process and ventilation vent releases.
According to the definition for short temiin NUREG-0133," Preparation cf Radiological Ef0uent Technical Specificatious 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 tenn 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 average 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 kication 499 meters N sector.
3 For process vent releases, the site boundary X/Q value was 1.0E-06 sec/m 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 hication 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 1-131, and from all radionuclides ia particulate form with half-lives greater than 8 days was through the grass-cow-milk 1 athway. The D/Q value from ventilation vent releases resulting in the maximem exposure was 2
9.0E 10 per m at a location 5150 meters S sector, For process vent releases, the D/Q value was 4.3E-10 per m2 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 uc/m3, and 1.3E-07 sec/m3 for process vent releases at a location 5150 meters S sector. The inhalation pathway is the only other pathway existing at this location. Therefore, the X/Q values given for tritium also apply for the inhalation pathway.
VIRGINIA VPAP-2103 IOWER REVISION 2 PAGE 106 OP 119 ATTACllMENT 2N (Page 3 of 8)
SURRY METEOROLOGICAL, LIQUID AND GASEOUS PATilWAY ANALYSIS 2.0 LIQUID PATilWAY 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 4
Ef0uents.
2.2 Data, Parameters, and Methodology Radioactive liquid effluent release data for the years 1976,1977,1978,1979,1980, and 1981 was compiled from the Surry Power Station ef0uent 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 James 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 rathway do not exist at this location. Access to the discharge canal by the general public is gained two ways: access for bank fishing is controlled by the Station and is limited to Virginia Power employees or guests of employees, and boating access is open to the public 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 irdividual 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, 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 invertebrates.
Dose to an individual fishing on the discharge bank was determined by multiplying the annual dose calculated with LADTAP by the fractional year the individual spent fishing in the canal.
VIRGINIA VPAP-2103 POWER -
REVISION 2 I' AGE 107 OF 119 ATTACllMENT 28 (Page 4 of 8)
-SURRY METEOROLOGICAL, LIQUID AND GASEOUS PATilWAY ANALYSIS 2.3 Results For the years 1976,1977, 9,1980, and 1981, the invertebrate pathway resulted in the largest dose In 1978 the fish pathway resulted in the largest dose. The maximum exposed -
member of the public was determined to utilize the James River. The critical age group was the adult and the critical organ was either the thyroid or GI-LLI. The ingestion dose factor, Ai,in 6.2.3 includes the fish and invertebrate pathways. Ai ose factors were calculated for the total d
body, thyroid, and GI LLI organs.
. 3.0 GASEOUS PATilWAY ANALYSIS 3.1 Purpose A gaseous effluent pathway analysis was perfomied 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 and 6.3.3.a. The analysis also included a detennination of the location, pathway, and critical organ, of the maximu.n exposed member of the public, as a result of the release of I 131, L
tritium, and for all radionuclides in particulate form with half lives greater than 8 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 I-131, tritium, and particulates to demonstrate compliance with
' 6.3.1.a.
l^
l3.2-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 accessible to the public inside site boundary. The largest X/Q value was determined to be 6.0E-05 sec/m3 at site e
boundary for ventilation vent releases at a location 499 meters N direction, and 1.0E-06 sec/m3 p
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.
T'T-T-
- 7 94%SW dp 4965i g8p-eyarew--=WW4a 1
e-
-ptr--p-
"*t; tr -
Tu T wr asM'.
9-Ng-'---'N-ww tt~M 4 7 *
8
N'Y TTn'**
y' W
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 108 OF i19 ATTACilhlENT 28 (Page 5 of 8)
SURRY METEOROLOGICAL, LIQUID AND GASEOUS PATilWAY ANAliSIS 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and X/Q values determined for maximum noble gas doses can be used to determine the maximum dose form 1 131, tritium, and for all radionuclides in particulate foim with half lives greater than 8 days for the inhalation pathway.
The NRC computer code GASPAR," Evaluation of Atmospheric Releases", Revised 8/1997, was run using 1976,1977,1978,1979,1980 and 1981 Surry Power Station gaseous effluent release report data. Doses from 1-131, tritium, and particulates for the inhalation pathway were 3
calculated using the 6.0E-05 sec/m site tvundary X/Q. Except for the source term data and the X/Q value, computer code de: fault parameters w.re 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. In 1979, the teen was the critical age group. Ilowever, 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 Kivy, L vy, Mivy, and N vv 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/m, and multiplying by the 3
ventilation vent site boundary X/Q value of 6.0E-05 sec/m3 The same approach was used to calculate the gamma and beta dose factors Kipy, Lipv, Mipv, and Nipv in Attachment 12 using 3
the process vent site boundary X/Q value of LOE-06 sec/m.
- Inhalation pathway dose factors Pivy and Pipv in Attachment 12 were calculated using the equation:
P = K' (BR) DFA (X/Q (mrenpyr per Curie /sec) i i
where:
K' = a constant of unit conversion,1E+12 pCi/Ci BR = the breathing rate of the child age group,3700 m3/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 3
X/Q = the ventilation vent site boundary X/Q,6.0E-5 sec/m, or the process vent site 3
boundary X/Q.1.0E-06 sec/m as appropriate i
I I
I
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 109 OF 119 ATTACllMENT 28 (Page 6 of 8)
SURRY METEOROI.OGICAl.,1,1 QUID AND GASEOUS PATilWAY ANAL,YSIS 6.3.4.a, requires that the dose to the maximum exposed member of the public from 1 131, tritium, and from all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to the specified limits. Dose calculations were perfonned for an exposed member of the public within site tvundary 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 milk-cow pathways with the largest D/Q values using the NRC computer code GASPAR.
It was determined that the member of the pt.blic 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 X/Q 3
at this location was determined to be 7.8E-05 sec/m at 290 meters NW direction. After 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 individual would receive at site boundary.
The member of the public receiving the largest dose beyond site boundary was determined to be located 5150 meters S 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 1976,1977,1978, 1979,1980 and 1981 the dose to the infant from the grass-cow-mild 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 infant, exposed through the grass-cow-milk pathway, critical organ thymid, at a location 5150 meters S sector. The only other pathway existing at this location for the infant is the inhalation.
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE I10 OF 119 ATTACilMENT 28 (Page 7 of 8)
SURRY METEOROl.OGICAl., I.lQUID AND GASEOUS PATilWAY ANAI,YSIS The RM vy and RM v dose factors, except for tritium,in Attachment 18 were calculated by i
ip multiplying the appropriate D/Q value with the following equation:
(
RMi = K' b I"ad Fm (r) (DFL )
.b + '
P
-A tt i
i c
Ai + Aw
- P s
where:
K' = a constant of unit conversion,1E+12 pCi/Ci
~
QF = cow's consumption rate,50,in Kg/ day (wet weight)
Uap = infant milk consumption rate,330, liters /yr Y = agricultural productivity by unit area of pasture feed grass,0.7 Kg/m2 p
Ys = agricultural productivity by unit area of stored feed,2.0, in Kg/m2 Fni = stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev. I r = fraction of deposited activity retained on cow's feed grass,1.0 for radiciodine, and 0.2 for particulates DFL = thyroid ingestion dose factor for the ith radionuelide for the infant, in mrem /pCi, from i
Table E 14, Regulatory Guide 1.109, Rev.i
- Ai = decay constant for the ith radionuclide, in s e-1 Aw = decay constant for removal of activity of I.af and plant surfaces by weathering, 5.73E-07 sec 1 (corresponding to a 14 day half-life) tr = transport time from pasture to cow, to milk, to receptor,1.73+05,in seconds th = transport time from pasture, to harvest, to cow, to milk, to receptor,7.78E+06, in seconds f = fraction of year that cow is on pasture,0.67 (dimensionless),7.78E406 in seconds p
f = fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensionless 3
Parameters used above were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev. l.
1
-r-e,
--v
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 111 OF 119 NI'TACllMENT 28 (Page 8 of 8)
SURRY METEOROLOGICAL.,1 lQUID AND G ASEOUS PATilWAY ANAL,YSIS Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used:
Rn.3 = K' K'" Fm QF Uap (DFLii.3) [0,75 (0.5/11)) x X/Q where:
K"' = a constant of unit conversion 1E+03 gnVkg 11 = absolute humidity of the atmosphere,8.0, gnVm3 0.75 = the fraction of total feed that is water 0.5 = the ratio of the specific activity of the feed grass to the atmospheric water l
X/Q = the annual average concentration at a location 5150 meters S sector 3.0E-07 see/m3 3
for ventilation vent releases, and 1.3E-07 sec/m for the process vent releases Other parameters have been previously defined.
ne inhalation pathway dose factors Ri vv and Ri v in Attachment 18 were calculated using the i
ip following equation:
Rlj = K' (13R) DFAi (X/Q) (mrem /yr per Curie /sec) where:
K' = a constant of unit conversion,1E+12 pCi/Ci 3
IIR = breathing rate of the infant age group,1400 m /yr, from Table E-5, Regulatory Guide 1.109, Rev.1 DFAi = thyriod organ inhalation dose factor for infant age group for the ith radionuclide, in mrenVpCi, from Table E-10, Regulatory Guide 1.109, Rev.1 3
X/Q = ventilation vent X/Q,3.0E-07 sec/m, or the process vent site boundary X/Q, 3
1.3E-07 sec/m, at a location 5150 meters S sector.
The GASPAR computer runs using 1976,1977,1978,1979,1980 and 1981 Surry effluent release data were reviewed to determine the percent of total dose from the cow milk and inhalation pathways for 1-133.1-133 contributed less than 1 percent of the total dose to an infant's thyroid except for the year 1977 when the percent 1-133 was 1.77. The calculations indicate that I-133 is a negligible dose contributor and its inclusion in a sampling and analysis program and dose calculation is unnecessary.
VIRGINIA -
VPAP 2103 POWER -
REVISION 2 l
PAGE 112 OF 119 ATTACilh1ENT 29 (Page 1 of 8)-
i NORTil ANNA h1ETEOROI.OGICAI.,1.lQUID AND GASEOUS PATilWAY AN Al,YSIS l.0 hlETEOROI.OGICAl, ANAL,YSIS 1.1 Purpose The purpose of the meteorological analysis was to detennine 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 to perfonn a dose pathway analysis to determine both the maximum exposed individual at site boundary and 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
-hieteorological Data, Parameters, and hiethodology Onsite meteorological data for the period January 1,1981, through December 31,1981, were used in calculations. This data included wind speed, wind direction, and differential temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (e.g., ventilation vent), and those characterized as mixed mode (i.e., process vent). The portions of release characterized as ground level were based on AT158.9ft-28.2rt and 28.2 foot wind data, and the portions characterized as mixed mode were based on AT13xSrt.28.2rt and 158.9 ft wind data.
X/Q's and D/Q's were calculated using the NRC computer code "XOQDOQ - Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations",'
- Septentber,1977. The code is based uporj 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 tecrain adjustment factors were applied to the X/Q values as recommended in Regulatory Guide 1.111. The site region is characterized by gently rolling terrain so open terrain correction factors were considered appropriate. The ground level ventilation vent 2
release calculations included a building wake correction based on a 1516 m containment minimum cross-sectional area.
VIRGINIA VPAP-2103 POWER REVISION 2 PAGE 113 OF 119 ATTACllMENT D (Page 2 of 8)
NORTil ANNA METEOROI OGICAl.,1,1 QUID AND G ASEOUS PATilWAY A N Al,YSIS 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.
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 1.11 i 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 Analysis Report Table 1IC.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.
According to the definition 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 teleases 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 average concentrations is appropriate according to NUREGJ)l33.
~
The X/Q and D/Q values calculated from 19S1 meteorological data are comparable to the values presented in the North Anna Power Station UFSAR.
1.3 Results The X/Q value that resulted in the maximum total body, skin and inhalation exposure for 3
ventilation vent teleases was 9.3E-06 sec/m at a site boundary location 1416 meters SE sector.
3 For process vent teleases, the site boundary X/Q value was 1.2E-06 sec/m at a location 1513 meters S sector. The shoreline X/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 1.0E-04 sec/m3 at a location 241 meters NNE sector. The 3
shoreline X/Q value for process vent was 3.7E-06 sec/m at a location 241 meters NNE sector.
VIRGINIA VPAP 2103 POWER Rl! VISION 2 PAGli 114 OF 119 NITACllMENT 29 (Page 3 of 8)
NORTil ANN A METEOROI,0GICAl., I.lQlllD ANI) G ASEOt1S PAYllWAY AN Al,YSIS Pathway analysis indicated that the maximum exposure from l 131, and from all radionuclhics in particulate fonn with half lives greater than 8 days was tiuough the prawcow inilk pathway. The D/Q value from sentilation vent icleases resulting in the maximum exposure was 2
2.41!-09 per m at a location 3250 meters N sector. Fc process vent releases, the D/Q value was 1.11109 per m2 at a location 3250 :neters N sector. For tritium, the X/Q value from ventilation vent teleases resulting in the maximum exposure for the milk pathway was 7.21!-07 i
3 see/m, and 3.9E-07 sec/m for process vent releases at a location 3250 meters N sector.
2.0 1,1Q111D PATilWAY ANAL,YSIS 2.1 Purpose The purpose of the liquid pathway analysis was to determine the maximum exposed member of the public in umesuicted areas as a result of radioactive liquid elfluent releases. The analysis includes a determination of most restrictive liquid pathway, most restrictive age group, and critical organ. This analysis is required fcr 6.2, 2.2 Datn, Parameters, and Metandology Radioactive liquid effluent release data for the years 1979,1980, and 1981 was compiled from the North Anna Power Station semi annual effluent ielease reports. The data for each year, along with appropriate site specific parametcts and default selected parameters, was entered into the NRC computer code LAD'l AP as described in NURl!G 0133.
Reconcentration of efnuents using the small lake connected to larger wates body model was selected with the appropriate parameters determined from Table 3.5.3.5, Design Data for Reservoir and Waste lleat 'I rcatment Facility fiom Virginia lilectrie and Power Company, Applicant's linvironmenta! 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 aserage Dow rates. All other parameters were defaults se'ected by the LADTAP coinputer code.
VlltGINIA Vl'AP 2103 POWER Ri? VISION 2 PAOli 115 OF i19 ATTACllMENT 29 (Page 4 of 8)
NORTil ANNA METEOROl.OGICAl.,1,1 QUID AND GASEOUS l'ATilWAY ANAIJSIS 2.3 Results t
I;or 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. Ilowever, since d.l ddult total IXDdy dose was greater than the teen total tuly dose for each year, the adult was selected as the most testrictive 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.
3.0 GASEOUS l'ATilW W ANAL,YSIS 3.1 l'urpose A paseous effluent pathway analysis was perfonned to determine the location that would result in the maximum doses due to noble pases for use in demonstrating compliance with 6.3.1.a and 6.3.3.a. The analysis also included a detennination of the critical pathway, location of maximum exposed member of the public, and the critical organ for the maximum dose due to 1 131, tritium, and for all radionuclides in particulate fonn with half lives greater than 8 days for use in demonstrating compliance with reouirements in 6.3.1.a.1 and 6.3.3.a. The Analysis also included a deteimination of the critical pathway, location of maximum exposed memler of the public, and the critical organ for the maximum dose due to 1 131, tritium, and for all radionuclides in paniculate form with half lives greater than 8 days for use in demonstrating compliance with 6.3.1.a.2 and 6.3.4.a.
3,2 Data, l'arameters, 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 site l
boundary, The largest X/Q value was detennined to be 9.3E 06 sec/m at site boundary for 3
ventilation vent releases at a location 1416 meters SE direction, and 1.2E@ sec/m at site 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 trta 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.
VlltGINIA VPAP-2103 POWElt IlliVISION 2 PAGl! 116 Ol; 119 ATTACllh1ENT 29 (Page $ of 8)
NOltTil ANNA $1ETEOl(OI.OGICAl., 1.10111D AND G ASEOt!S PATilWAY AN Al YSIS 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Theiefore, the locations and 7./Q values determined for maximum noble gas doses can le used to determine the maximum dose form 1 131, tritium, and for all radionutlides in particulate fonn with half lives greater than 8 days for the inhalation pathway.
The NitC computer code GASPAlt," Evaluation of Atmospheric iteleases,"itevised 8/1997, was run using 1979,19X0 and 1981 North Anna Power Station Gaseous E' fluent Release lleport data. Doses from I 131, tritium, and particulates for the inhalation pathway were i
calculated using the 9.3E-06 sec/m site boundary 7JQ. Except f or the source tenn data and the 7JQ value, computer code default parameters were used itesults for each year indicated that the critical age p.roup was the child and the critical organ was the thyroid for the inhalation pathway.
The gamma and beta dose factors Kivy, L n, M vy, and N vv in Attachment 12 w cre obtained i
i i
by performing a units conversion of the appropiiate dose factois from Table 11 s, Regulatory l
l Guide 1.109, Rev.1, to nuem/yr per Ci/m or mrad /yr irr Ci/m, and multiplying by the ventilation vent site boundary 7JQ value of 9.3E-06 sec/m' The same approach was used in calculating the ganuna and beta dose factors Kipv, Lipy, Mipv, and Nipv in Attachment 13 using l
the process vent site boundary 7JQ value of 1.2E-06 sec/m.
The inhalation pathway dose fa ns P vv and P v in Attachment 13 were calculated using the i
ip following equation:
P = K'(llR) DFA (7JQ)(mreni/yr per Curic/sec) i i
where:
K' = a constant of unit conversion,1E+12 pCi/Ci 3
DR = the breathing rate of the chihl 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 nuem/pCi, from Table E-9, Regulatory Guide 1.109 Rev. I l
7/Q = the ventilation vent site loundary 7JQ,9.3E-06 sec/m, or the process vent site i
boundary 7JQ,1.2E-06 sec/m as appropriate, l
_.-.__.-..-._m.
VIRGINIA VPAP 2103 POWER REVISION 2 PAGE 117 OF 119 ATTACilh1ENT 29 (Page 6 of 8)
NORTil ANNA AIETEOROI.OGICAl., I,1 QUID AND GASEOUS PATilWAY A N Al,YSIS 6.3.4.a. sequires that the dose to the maximum exposed memler of the pub'ic from 1 131, tritium, and from all sadionuclides in particulate form with half lives greater than 8 days be less than or equal to the specified limits. Dose calculations were irrformed for an exposed snember 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 EnvironmentM Smvey Data for 1981.
It was detemiined that the member of the public witain site boundary would be using 1.,ake 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 memtwr 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 X/Q of 1.0E41 at a location 241 meters NNE acetor, The NRC computer code G ASPAR was run to calculate the inhalation dose to this individual. 'Ihe GASPAR results were corrected for the fractional year the member of the nublic wouki be using the lake.
Using the NRC computer code GASPAR and annual average X/Q and D/Q values obtained as described in Section 1 of this attachment the nemier 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 thjrold.
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 detemiined to be the infant, exposed through the grass-cow milk pathway, critical organ thyroid, at a location 3250 meters N sector.
_ _ _ ~ -
l VIRGINIA VPAP-2103 1
POWER Rl! VISION 2 J
PAGE 118 OF 119
\\
\\'ITACllMENT 29 (Page 7 of 8)
NORTil ANNA METEOHOI.OGICAI., LIQUll) AND G ASEOUS PATilWAY ANAL,YSIS The Rivy and Ripv dose factors, except for tritium,in Attachment 19 were calculated by multiplying the appropriate D/Q value with the following c luation:
+ (1-f f ) e A th H = K, _QF (Uap) l',en (r) (DFL )
fpfs i
e )iti p3 i
i
,I-i.
Ai + Aw
- P s
where:
K' = a constant of unit conversion, IE+ 12 pCi/Ci QF = cow's consumption rate,30,in Kp/ day (wet weight)
Unp = infant milk consumption rate,330, liters /yr Y = agricultural productivity by unit area of pasture feed grass. 0.7 Kg/m2 p
Ys = agricultural productivity by unit area of stored feed,2.0,in Kg/m2 F n = stable element transfer coefficients, from Table E 1, Regulatory Guide 1.109, Rev. I i
r = fraction of deposited activity retained on cow's feed grass,1.0 for radiciodine, and 0.2 for particulates DFLi = thyroid ingestion dose factor for the ith radionuclide for the infant, in mrem /pci, from Table E 14 Regulatory Guide 1.109, Rev.1 A = decay constant for the ith radionuclide,in see-1 i
Aw decay constant for removal of activity of leaf and plant sm faces by weathering,
=
5.73E-07 sec-1 (conesponding to a 14 day half life) i tr = transport time from pasture to cow, to milk, to receptor,1.73E+05, in seconds th = transport time from pasture, to harvest, to cow, to milk, to receptor,7.78E+06,in seconds fp = fraction of year that cow is on pasture 0.58 (dimensionless),7 months per year from NUREG-0597 f = fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensionless 3
Pa. aeters used in the above equation were obtained from NUREG-0133 and Regulatory Guide 1.109 Rev.l.
VIRGINIA VI'AP-2103 l'OWliR RiiVISION 2 PAGli 119 01; 119 ATTACilMI:NT 29 (l' ape 8 of 8)
NOl(Til ANNA MI:TI:Ol(OI.OGICAI., l.lQl!!!) ANI) G ASI:Ol!S l'ATilWAY AN Al YSIS Since the concentration of tritiutn in inilk is lused on the airlorne concentration rather than the deposition. the f ollowing equatioli is used:
Rii.3 - K' K"' 1% Q1: l.np (1)Fl ii.3) 10.75 (0.5/11)) x X/Q
.c y ti cerlV.Olt of U! lit corlVer %f t llWO3 pnt'Lg s
4 11 = absolute in.midity of the atmosphere,8.0, put'in 0.7f ' the fraction of total feed ti.at is water 0.5 e the ratio of the specific activity of the feed grass to the atmospheric water 4
X/Q = the annual as clage concentration at a location 3250 eneters N sector,7.21 07 sec/in I
for ventilation vent releases, and 3.915 07 sec/in for thc procew vent releases Other paraincters have been presiously defined.
W
(
__