ML20138B542
| ML20138B542 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/16/1996 |
| From: | Tarantino C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20138B489 | List: |
| References | |
| VPAP-2103, NUDOCS 9704290195 | |
| Download: ML20138B542 (176) | |
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VPAP-0502 T'RGIN A POWER PROPERTY REMOM This document is the 'p roperty of' "D, MM I 31996 NM & P PAGE 109 OF 159 VIRGINIA POUR and is to be returned 9 m, upon request. No permission is granted to publich. reproduce. transmit, or , PTOC6dUTO ACf/OU OBQuest (PAR) inclose to another any information ! entained in this document. i l Instructions for completing this form are included in VPAP-0502.
- 1. ;'s_ _-dure Number ..a 2. R I 4.Page 7.5wt 5. Effective VpAp_x03- not approval 9 2. Number 3.Chadng 1
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Notet if ** PAR le to request a REVISION ONLY, aldp items 10 W@ 20, fill sad hems 21122, and submit 10, es this request for a new procedure? Yes No l 11. Does this change result in a "Yes" answer to any questions on the j
- 12. *Does the coverorsheet al Test.' of othis procedure indcate "Intreguently Conducsoa or Complex Test or Evoluton' or is Epip recedure or EOP or Fire Protection P ? y, g [
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- 13. A change to the stated Purpose of the procedure.
]Yes $5 No l 14. A change in the stated initial Conditons that must be satisfod prior to performing the procedure.
Yes
@Nol l 15. A change in the stated Acceptance Criteria that must be eatisted for satisfactory completio l 16. A modification or deletion of setpoints, independent. or simultaneous verification. hYes Owol ;
l Yes XNol I I 17. A change completion of the task. that attects This includes changes specific acons that affect personnel that safety, arefireregurred decrease protection to be accom { { effectiveness, affect equipment qualtlication. or involve a less conservative method of performing the task. hYes ON. . l
- 18. procedure A changewhich tnat includes relocates or deletes a required hold point. Thts ooes not include de'sterg a secten of a a hold point.
Y'8 0
- 10. A change to CAUTION or WARNING statements. This doec not include adding CAUTION or WARNING statements or deleting a sodion of a procedure which includes CAUTION or WARNING statements. Yes l 20. A change that modifies or deletes the method for meeting a commitment identified @No in thelIpr Yes 21.Re esteABy NameiPieabPnnt)
[No l e na 22.Oa% 3 9(o 11 SFN spproval to reqused for a procedure change. t supon-,t.- .a not neccesary tarthe i . . . . . .
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@23. SNSOC ( -
- @24. Cognizant Management B
. . . . . O 25 cocaiz=at uenseemoai^
- 26. Required Approval Authortty (59Sw]d 27, Date
- 28. Shltt Supervisor Approval For Changes (S@luture) V s -/6-%
- 29. Date
- 30. Station Manager Approval 11 Required (Sgnature)
, l 31. Date K:.y: W^' 1 l SNSOC-Station Nuc6eer Safety and Weiing C= .N; r.; l
- .mgency 7" r. .t. . i.;ing k*%r==sm raneaep pesi Procedures; EOP-Emepr.g Operating Procedure, PAR-Procedure Action Request 9704290195 970421 PDR ADOCK 05000338 p PDR ,
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VPAP-050 VIRGIR A 20WER PROPERTY j . This document is the 'p roperty of" asesiod' { , j'D, MAY 131996 H M &P PAGE 109 0F 159 VIRGINIA PC#ER and in to be returned i n nr m estaaper=Lutontsernnt*d to publish reproduce, transmit. or ' Procedure Action Request (PAR) wasassammgiac1ces to another any information j . contained in this tiocument. ,,,,c n,n,n, 2 ' instructions for completing this form are included in VPAP-0502. I t ..y 2. R 4.Page ! l . Proceouro NumberV 7 devis P AP-N 9 03'2 Number 3.Chadng I i of l'f f"/A
- 5. Effectsve/D te (linot aprov I
I l T*s$ b dnicM% haaval (Aerth Anm OM I//d
- 8. Type of Request l
0"e Proe oureE Proe ours en=as. m---*e l t Proc ourea vi ionDeroe dur o i tiaaOv ador ! 9. Reason U g mand deDescriptonhf ChanE b Ge j Co r rec % ' to erdor Q Capo . pue,ww ggte .
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fe r Yo hadd fMM p is b C N % hCap/t h N:te: if PAR ** La to requeet e REVISION ONLY, =*_la items to O. M/ . agh 20,ful out home 21 & 22, and submit to Procedures grou { 10. is this request for a new procedure? ji '}Yes [>d No] l 11. Does this change result in a "Yes' answer to any questions on the Acuvity S 1
- 12. "Soocial Does the cover sheet of this procedure indicate *Introquerftty Conducted or Comp 6ex Test or Evoluten or Yes yNol Test.* or is EPIP or S orocedure or EOP or Fire Protection P m? y, g l !
- 13. A change to the stated Purpose of the procedure. I l 14. A change in the stated initial Conditions that must be satisfied prior to performing ]Yes Gthe Noproce I
l 15. A change in the stated Acceptance Criteria that must be satistedhfor Yes @Nol satisfactory l 16. A modification or deletron of setpoints, independent, or simultaneous verffcation. hYes Nol ) Yes l 17. A change that affects spectic actions that are required to be accompinhed to ensure l XNol to the satisfar: completion ut the task. This includes changes that affect personnel safety. decrease fire protection .f ettectiveness affect equipment qualification, or involve a less conservative method of >3 Yes performing the task No 1 l 18.procedure l A change that relocates or oeletes a required hold point. This does not enclude deleting a secten of which includes a hold point. i y, g
- 19. A change to CAUTION or WARNING statements. This does not include adding CAUTION or WARNING statements or deleting a secten of a procedure which includes CAUTION or WARNING statements.
l 20. A change that modifies or deletes the method for meeting a commitment identified in
- 21. he este By Name iPisa Print) Yes
- 22. C at f hNo l l;
DTM N6 $ 3, 11 SfM approval es requred tot a procedure criange. A es not neces Shift S+ervssor to approve the procedure change, piace N/A in block 28. l
@23. SNSOC ( -
- 24. Cognizant Management B O 25 cooniz=at u=a a m at ^
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- 26. Required Approval Authorrty(SgSay. Tw 27. Date 1
l 28. Shltt Supervisor Approval For VChanges (Sqpedature) MA s -a-&
- 29. Date
)
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- 30. Staten Manager Approvalif Required (Sgnature) .
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- 31. Date
' ', Kcy: SNSOC Staten Nuc6 ear Safety and Cesng Cwes.r. e; EPIP E.T.ww
, hu_e Q.O(o n y P6an tr.gA.T aiing m Procedures; EOP. Emergency Operating Procedure, PAR-Procedure Action Request -ess 9704290195 970421 j
PDR ADOCK 05000338 R PDR 1 1
v4f-tio3 M PNq P.3M O G Activity Screening Checidist
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- GOV 02 VPAP-3001
- 1. Identification of Governing Document 2. Apphcable Station
- 3. Apphcable Unit E North Anna Power Station C Surry Power Ste. tion
\/9 AP - A/ 03.fN'A @ Unit 1 Q Unit 2
- 4. Onet Descrip ton of the Activity .
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- 5. General Screenin0 (Definitions are provided in VPAP 3001.)
A. Does this activity require a change to the Operating License or Technicaf Spechcations? Yes @ No B. Does this activity alter ( temporarily or permanently) the information, design, function, ability to function, or method of performing the f unction of a structure, system, or component as described in the SAR? Yes @ No C. Does this activity modify a procedure or method of operation as described, outlined, or summarized in the SAR? Yes @ No D. Does this activity periorm a test or experiment that is not described in the SAR? O Yes @ No E. Does this activity involve a change to the Environmental P otection Plan, or a change, test, or experiment that may affect the environment? O ves E No F. Does this activity involve a temporary modification? Yes @ No
- 6. Discussion and References 1)cP 9 4-oo Y l-off Note it Any Response is "yes.~ a Safety Evaluation Must be Perio ed in Accordance With VPAP 3001. Safety Evaluations
- 7. Preparer Name (Please Print) 8. Istle Gort A. 1 aran % D %dc St H Matt % Mu siw, &
- 9. Preparer Synatur 10. Date V f
- 11. Reviewer Na k ^^-<
Only t Non-Aut onze 6Y/3/ 9br reparer-Please Pnnt) 12. Title { fff ar a 1'N f6r !)MfC O'( Y l'
- 13. Reviewer Signatu L
- 14. Date Key: SAR-Safety Analysis Report F *'*
- 7 "' 0"' )
-North Anna Only- PN2 Page 3 of 14 VIRGINIA VPAP-2103
- POWER -
REVISION 7
- PAGE 17 OF 156 i .
- b. Radioactive Liquid Emuent Monitoring Instrumentation Operability I
, Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operabib by performing a Channel Check, Source Check, Channel l
- m.
Calibration, and Channel Functional Test at the frequencies shown in Attachments , 3 and 4, Radioactive Liquid Effluent Monito-ing Instrumentation Surveillance l
- Requirements.- )
\
- 1. If the number of operable channels is less than the mmimum required by the tables in Attachment 1 or 2, perform the action shown in those tables.
, 2. Attempt to return the instruments to operable stams within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report $[ why the inoperability was not corrected in a timely manner. - i l c. Applicable Monitors i i j Liquid effluent monitors for which alarm / trip setpoints shall be determined are: ' ~ Release Point Instrument Number l
\
North Anna Surry ) j Liquid Radwaste Effluent Line 1-LW-RM-111 N/A ] Service Water System Effluent Line 1-SW-RM-108 l-SW-RM-107 A, i B,C,D ' 3 Condenser Circulating Water Line 1-SW-RM-130 1-SW-RM-120 2-SW-RM-230 2-SW-RM-220 Radwaste Facility Effluent Line N/A 1-RRM-RITS-131 i {PN2} Steam Generator High 1-RM-SS-125 Capacity Blowdown Line N/A 2-RM-SS-225 a-O
-North Anns Only- PN2 Page 4 of 14 . VIRGINIA VPAP-2103 M. POWER ~~
REVISION 7 - PAGE 18 OF 156 6.2.2 Liquid Monitoring Instrumentation (continued) )
,d. Setpoint Calculation ol ~
NOTE: 'Ihis methodology does not preclude use of more conservative setpoints.
- 1. Maximum setpoint values shall be calculated by: _;
l CF S= U (2) F E ~ where: S = the setpoint, in pCi/ml, 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 pCi/ml FE= maximum design pathway effluent flow rate Fo = dilution water flow rate calculated as: (Surry) D = F E+ (200,000 gpm x number of cire. pumps in service) ,
, (N. Anna) D = FE+ (218,000 gpm x number of circ. pumps in service) .
- 2. Each of the condenser circulating water channels (Surry: SW-120, SW 220)
(North Anna: SW-130, SW-230) monitors the effluent (service water, including component cooling service water, circulating water, and liquid radwaste) in the circulating water discharge tunnel beyond the last point of possible radioactive , material addition. No dilution is assumed for this pathway. Therefore, Equation ! (2) becomes: S=C (3) The setpoint for Station monitors used to implement 10 CFR 20 for the site becomes the effluent concentration limit.
- 3. .in. addition, for added conservatism, serpoints shall be. calculated for the liquid radwaste effluent line (Nonh Anna: LW-111), the service water system effluent line (Surry: SW-107 A, B, C, and D, North Anna: SW-108), and the Radwaste Facility effluent line (Surry: RRM-131).
-North Anna Only- PN2 Page 5 of 14
-i "- VIRGINIA VPAP-2103 4 POWER -' REVISION 7 PAGE 45 OF 156 6.6.2 Land Use Census i
- , a. Requirement
- A land use census shill be conducted and shall identify within a distance of 8 km ., ,
-(5 miles) the location in each of the46 meteorological sectors of the following. ;
)
! . Nearest milk animal
. Nearest residence ~
. Nearest garden greater than 50 m2 (500 ft2) that produces broad leaf vegetation l
! 1. The land use census shall be conducted during the growing season, at least once ._ l per 12 months, using methods that will provide theibest results (e.g., door-to-j door survey, aerial survey, local agriculture authorities). Land use census results shall be included in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.
- 2. In lieu of the garden census, road leaf vegetation sampling of at least three
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different kinds of vegetation may be performed at the site boundary in each of j two different direction sectors with the highest predicted ground deposition (D/Qs). Specifications for broad leaf vegetation sampling in Attachment 20 or , i - 21 shall be followed, including analysis of control samples. ' b. Action
- l. If a land use census identifies locations that yield a calculated dose or dose commitment greater than the values currently being calculated in 6.3.4.a.2, identify the new locations in the next Annual Radioactive Effluent Release !
- Report in accordance with VPAP-2802, Notifications and Reports.
- 2. If a land use census identifies locations that yield a calculated dose or dose commitment (via the same exposure pathway) 20 percent (Surry) or 25 percent
) (North Anna) greater than at a location from which samples are currently being f obtained, add the new locations to the Radiological Environmental Monitoring l Program within 30 days. Sampling locations, excluding the control stadon location, that have the lowest calculated dose or dose commitments (via the I same exposure pathway) may be deleted from the monitoring program. Identify new locations in the next Annual Radioactive Effluent Release Report and [ include in the report revised figures and tables reflecting the new locations in
; accordance with VPAP-2802, Notifications and Reports. [ Commitment 3.2.4]
- - . , . , - - . - .~. -
-North Anna Only- PN2 Page 6 of 14 g VIRGINIA VPAP-2103 i POWER -
REVISION 7 - i PAGE 46 OF 156 i 6.6.3 Interlaboratory Comparison Program [ , a. Requirement {PNi} Radioactive matedals (which ccntain nuclides produced at the Stations),
.._ supplied as part of an Interlaboratory Comparison Program $2: h= Ex.. pp:c.wl-by :!.: ."C, shall be analyzed. ,
- b. Action
- 1. {PNI} Analyses shall be performed as follows pr: cf $c Endenm:nd Prc::::icn A;;cacy's Envi enmend Radic=:iy!:y Lab =:try In::rccmpri=n
^~
S:ad!= (Crcz Ch=k) Rc;;m . nd iq ! de: _ , Program Cross-Check of Milk 1131, Gamma, K, Sr89 and Sr90 Water Gross Beta, Gamma,1 131,11 3 (Tritium),Sr89 and Sr90(blind-any combinations of above radionuclides) f Air Filter Gross Beta, Gamma, Sr*
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- 2. If analyses are not performed as required by 6.6.3.b., report in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports, the corrective actions taken to prevent recurrence.
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i . I -N::rth Anna Only- PN2 Page 7 of 14 L VIRGINIA VPAP-2103
. POWER -
REVISION 7 PAGE 47 OF 156 l . 6.6.3 Interlaboratory Comparison Program (continued)
- c. Methodology and Results
- 1. {PNI}Methodolohy and results of the cross-check program shall be maintained _
in the contractor-supplied N=b;- Re=:cr Envired=nt:1 Rad!::!cn I Meni:=ing Quality Control Manual, I L "J32 351.
, 2. Results shall be reported in the Annual Radiological Environmental Monitoring i Repon in accordance with VPAP-2802, Notifications and Reports.
6.7 Reporting Requirements - 6.7.1 Annual Radiological Environmental Operating Report Routine Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year. A single submittal may be made for the Station. Radiological Environmental Operating Reports shallinclude:
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- a. Summaries, interpretations, and analysis of trends of results of radiological environmental surveillance activities for the repon period, including:
. A comparison (as appropriate) with preoperational studies, operational controls, ,
~;
and previous environmental surveillance repons
. An assessment of the observed impacts of the plant operation on the environment
. Results ofland use census per 6.6.2 I
- b. Results of analysis of radiological environmental samples and of environmental radiation measurements taken per 6.6.1, Monitoring Program. Results shall be summarized and tabulated in the format of the table in the Radiological Assessment Branch Technical Position on Environmental Monitoring.
- 1. If some individual results are not available for inclusion with the repon, the repon shall be submitted, noting and explaining reasons for missing results.
- 2. Missing data shall be submitted in a supplementary repon as soon as possible.
)
i
- c. A summary description of the radiological environmental monitoring program. I l
- 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.
i w
-North Anna Only- PN2 Page 8 of 14 VIRGINIA VPAP-2103 r ' POWER --
REVISION 7 - PAGE 48 OF 156
- e. Results of Station panicipation in the Interlaboratory Comparison Program,
, per 6.6.3.
,i
- f. Discussion of deviations'from the Station's environmental sampling schedule per -
' '~
' Attachment 20 or 21.
- g. Discussion of analyses in which the lower limit of detection (LLD) required by
. Attachment 24 or.25_was notachievable.
6.7.2 Annual Radioactive Effluent Release Report
- a. Requirement -
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Radioactive Effluent Release Repons covering ~operati~on~6f th'e units during the previous 12 months of operation shall be submitted before May 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 Effluent Release Reports shall include:
- 1. A summary of quantities of radioactive liquid and gaseous effluents and solid waste released. Data shall be summarized on a quarterly basis following the format of Regulatory Guide 1.21, Appendix B.
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- 2. An assessment of radiation doses to the maximum exposed members of the public due to the radioactive liquid and gaseous effluents released from the Station during the previous calendar year. This assessment shall be in accordance with 6.7.2.b.
- 3. A list and description of unplanned releases from the site to unrestricted areas, during the reporting period, which meet the following criteria:
. Unplanned releases that exceeded the limits in 6.2.1 and 6.3.1
. Unplanned releases which require a Deviation Report and involve the l discharge of contents of the wrong Waste Gas Decay Tank or the wrong liquid radwaste release tank Unplanned releases from large leaks due to unexpected valve or pipe failures l that result in a quantity of release such that a 10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors or 10 CFR 50.73, Licensee Event Repon System, report is required
. Unplanned releases as determined by Radiation Protection Supervision, l which may or may not require a Deviation Report w
-North Anns Only- PN2 Page 9 of 14 l
VIRGINIA . VPAP-2103
- POWER -
REVISION 7 PAGE 55 OF 156 ATTACHMENT 2 (Page 1 of 2) North Anna Radioactive Liquid Emuent Monitoring Instrumentation Instrument Minimma Operable Action Channels
. 1. Liquid Radwaste Emment I (a) 1 RM-LW-111, Liquid Radwaste Effluent Monitor 1 1 l
[, (b) 1-LW-FT-104, Liquid Radwaste Effluent Total Flow Measuring Device 1 2 < l (c) 1-LW-SOV-121, Clarifier Effluent Line Continuous Composite Sampler i 1 l and Sampler Flow Monitor l (d) 1-LW-TK-20, Liquid Waste Efiluent Sample Vessel 1- 1 (e) 1-LW 1130, Liquid Waste Effluent Proportional Sample Valve 1 1 , (f) 1-RM-SW-108, Service Water Effluent Monitor 1 1 ! (g) 1-RM SW 130, Unit 1 Circulating Water System Effluent Line Monitor 1 4 (h) 2-RM-SW 230, Unit 2 Circulating Water System Effluent Line Monitor 1 4
- 2. Tank Level Indicating Devices (Note 1) l (a) Refueling Water Storage Tanks Unit 1 1-QS-LT 100A 1-QS-LT-100B 1 3 ~!
1-QS-LT 100C 1-QS-LT-100D Unit 2 2-QS-LT-200A 1 3 >
. 2-QS-LT-200B 2-QS-LT-200C ',
2-QS-LT 200D l (b) Casing Cooling Storage Tanks i' i Unit I l-RS-LT-103A 1 3 1-RS-LT 103B I Unit 2 2-RS-LT-203A 1 3 , 2-RS-LT-203B ' ' (c) PG Water Storage Tanks (Note 2) 1 BR-LT-116A (1 PG TK-1 A) 1 3 1-BR-LT-116B (1-PG-T <-1B) 1 3 (d) Boron Recovery Test Tanb(Note 2) ! 1-BR-LT 112A (1-BR-1K 2A) 1 3 1-BR-LT-112B (1-BR-TK 2B) 1 3
- 3. (PN2) Steam Generator High Capacity Blowdown l
(a) Steam Generator High Capacity Blowdown Radiation Monitor ! Unit 1 1 RM SS 125 1 1 Unit 2 2 RM.SS-225 1 1 (b) Steam Generator High Capacity Blowdown Flash Tank Outlet Howrate Unit 1 1 BD FT-105 1 2 Unit 2 2 BD-FT 205 1 2 i (c) Steam Generator High Capacity Blowdown Pmportional Sampling l System Collection Tank i Unit 1 1 BD TK-4 1 1 j Unit 2 2 BD-TK 4 1 1 i
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-North Anna Only- PN2 Page 10 of 14
_. VIRGINIA VPAP-2103
- POWER -
REVISION 7 - PAGE 56 OF 156 ATI'ACHMENT 2 (Page 2 of 2) North Anna Radioactive Liquid Emuent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases via this pathway may continue if, at least once within 12 hours, grab samples are collected and - analyzed for gross radioactivity (beta and gamma) at an LLD of at least lx10-7 pCi/g or an isotopic radioactivity at an LLD of at least 5x10-7 pCi/g. ACTION 2: If the number of opee $le channels is less than required, effluent releases via this pathway may continue if the flow rateis estimated at least once per 4 hours during actual releases. Design capacity performance curves generated in situ may be used to estimate flow. ACTION 3: If the number of operable channels is less than required, liquid additions to this tank may continue if the tank liquid level is estimated during all liquid additions to the tank.
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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. l NOTE 1: Tanks included in this requirement are those outdoor tanks that are not surrounded by ,; liners, dikes, or walls capable of holding the tank contents, and do not have overflows and surrounding area drains connected to the liquid radwaste treatment system. NOTE 2: This is a shared system between Unit I and Unit 2.
- l
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- L -North Anna Only- PN2 Page 11 of 14 !
h' , VIRGINIA VPAP-2103
~
POWER ~ REVISION 7
- i. PAGE 59 OF 156 ;
j . l. ATTACHMENT 4 (Page 1 of 2) Norih Anna Radioactive Liquid Emuent Monitoring Instrumentation SurveiHance Requirements Channel Description .. Channel Source Channel Channel l Check Check' Calibration Functional Test .
- 1. Liquid Radwaste Emuent '
(a) 1-RM LW lll, Liquid Radwaste Effluent Monitor D D R Q(NOE l) l l (b) 1-LW-FT 104,, Liquid Radwaste Effluent Total Flow l Measuring Device D(NOTE 3) N/A R Q - - < l (c) 1-LW-SOV 121, Clarifier Effluent Line Continuous - i Composite Sampler and Sampler Flow Monitor N/A N/A R N/A l (d) 1 LW-TK-20, Liquid Waste Effluent Sample Vessel D(NOTE 9) N/A N/A N/A (e) 1- -1130, Liquid Waste Effluent Proportional Sample D(NOTE 9) N/A N/A N/A (f) 1 RM SW-108, Service Water System Effluent Monitor D M R Q(NOTE 2) (g) 1 RM-SW 130, Unit 1 Circulating Water System Effluent Line Monitor D M R Q(NOTE 2) i ' (h) 2-RM-SW-230 Unit 2 Circulating Water System Effluent l Line Monitor D M R Q(NOTE 2) ;
- 2. Tank Level Indicating Device (NOTE 6) '
(a) Refueling Water Storage Tanks
. Unit I l-QS-LT 100A,1-QS-LT-1008 -
1-QS LT-100C,1-QS-LT 100D D(NOTE 4) N/A R Q(NOTE 7) Unit 2 2-OS-LT-200A,2-QS-LT 200B 2 OS-LT-200C 2-QS-LT-200D D(NOTE 4) N/A R Q(NOTE 7) (b) Casing Cooling Storage Tanks Unit I l RS-LT 103A,1 RS-LT-103B D(NOTE 4) N/A R Q(NOTE 7) I Unit 2 2-RS-LT 203 A,2-RS-LT 203B D (NOTE 4) N/A R Q(NOTE 7) ; (c) PO Water Storage Tanks (NOTE 5) 1 BR LT Il6A (1-PG-TK 1 A) D(NOTE 4) N/A R Q(NOTE 8) 1-BR LT-116B (1-PG-TK-1B) D (NOTE 4) N/A R Q(NOTE 8) (d) Boron Recovery Test Tanks (NOTE 5) 1-BR-LT-112A (1-BR-TK-2A) D (NOTE 4) N/A R Q(NOTE 8) 1-BR-LT 112B (l-BR-TK-2B) D (NOTE 4) N/A R Q (NOTE 8)
- 3. (PN2) Steam Generator (SG) High Capacity Blowdown (a) SG High Capacity Blowdown Radiation Monitor Unit I l RM SS'125 D (NOTE 12) D (NOTE 12) Q(NOTE 11)
Unit 2 2 RM SS 225 R R (NOTE 10) (b) SG High Capacity likewdown Flash Tank Outlet Flowrate l Unit I l BD FT 105 Unit 2 2-BD-FT 205 D (NOTE 13) N/A R N/A (c) SG High Capacity filowdown Proportional Sampling System Collection Tank ' Unit I l BD TK 4 i Unit 2 2 BD-TK-4 D (NOTE 9) N/A N/A N/A l l
-North Anno Only- PN2 Page 12 of 14 VIRGINIA VPAP-2103 . l POWER REVISION 7 l PAGE 60 OF 156 ATTACIIMENT 4 l
, (Page 2 of 2)
North Anna Radioactive Liquid Eftluent Monitoring Instrumentation Surveillance -
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- Requirements NOTE 1
- The Channel Functional Test shall demonstrate:
- a. Automalic isolation of this pathway and Control Room alarm annunciation occur if the instrument l indicates measured levels above alarm / trip setpoint.
b.Alami annunciation occurs if the instrument controls am not set in " operate" mode. NOTE 2: The Channel Functional Test shall demonstrate that Control Room alarm annunciation occurs if any
^
of the following conditions exists: a.Instmment indicates measured levels above the alarm / trip setpoint.
- b. Instrument controls not set in " operate" mode.
NOTE 3: Channel Check shall consist of verifying indication of flow during periods of release. Channel Check shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. NOTE 4: During liquid additions to the tank, verify indication of level change. NOTE 5: This is a shared system between Unit I and Unit 2. NOTE 6: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have overflows and surrounding area drains - connected to the liquid radwaste treatment system. NOTE 7: The Channel Functional Test shJI demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur ifinstrument indicates measured levels outside the alarm / trip serpoint. Demonstration of automade isolation may consist of verifying the appropriate signal is generated. Valves need not be operated for this test. NOTE 8: The Channel Functional Test shall demonstrate that Control Room alarm annunciation occurs if the instrument indicates measured levels are outside alarm setpoint. NOTE 9: Channel Check shall consist of verifying that proportional flow exceeds 0.5 mis / gallon. NOTE 10: (PN2} Channel Functional Test shall demonstrate that system isolation occurs on a radiation monitorliigh High Alarm. NOTE 11: {PN2} Channel Functional Test shall demonstrate:
- a. Trip signals are generated at the required setpoints. Isolation is not required.
- b. Local radiation monitor indication occurs ifinstrument controls are not set in " Operate"
, mode or if the instrument indicates measured levels are above the alarm / trip setpoint. NOTE 12: {PN2} The radiation monitor automatically performs periodic source checks. The Source Check and Channel Check are satisfied as long as the green light is lit. NOTE 13: {PN2} This is verified by indicated elliuent flow less than or equal to 190 gpm. l l l l l
-North Anne. Only - PN2 Page 13 of 14 VIRGINIA VPAP-2103 POWER -
REVISION 7 PAGE 131 OF 156 ATTACHMENT 23 (Page 3 of 4) North Anna Environmental Sampling Locations .
' ' ~
Distance and Direction F'rbiriIinit No."1 Sample Location Station Distance Direction Collection REMARKS Media No. (Mims) Frequency Airbome NAPS SewageTreatment 01 0.20 NE Weekly On-Site Plant Particulate Frederick's Hall 02 5.30 SSW Weekly and Mineral. VA 03 7.10 WSW Weekly Radiolodine Wares Crossroads 04 5.10 WNW Weekly Route 752 05 4.20 NNE Weekly Sturgeon's Creek Marina 05A 3.20 N Weekly Levy.VA 06 4.70 ESE Weekly Bumpass. VA 07 7.30 SSE Weekly End of Route 685 21 1.00 WNW Weekly Site Boundary Route 700 22 1.00 WSW Weekly Site Boundary
" Aspen Hills" 23 0.93 SSE Weekly Site Boundary Orange. VA 24 22.00 NW Weekly Control Surface Water Waste Heat Treatment
. [ Commitment Facility (Second Cooling 08 1.10 SSE Monthly 3.2.2] Lagoon)
North Anna River (upstream)Rt 669 Bridge 09A 12.9 WNW Monthly Control (Brook's Bridge) North Anna River 11 5.80 SE Monthly (downstream) Ground Water Biology Lab 01A 0.75 SE Quarterly (well water) Aquatic Waste Heat Treatment Sediment Facility (Second Cooling 08 1.10 SSE Semi-Annually Lagoon) North Anna River (upstream)Rt 669 Bridge 09A 12.9 WNW Semi-Annually Control (Brook's Bridge) North Anna River 5.80 SE 11 Semi-Annually (downstream) {PN2} Shoreline Soil Lake Anna (up=:) 08 09 1.10 M9 SSE NW Semi-Annually Soil NAPS SewageTreatment Plat 01 0.20 NE Once per 3 yrs On-Site l ( t 1
o
-North Ann 3 Only- PN2 Page 14 of 14 VIRGINIA l- POWER VPAP-2103 REVISION 7 - '
l PAGE 132 OF 156 ATTACHNENT 23 ? (Page 4 of 4)
, North Anna Environmental Sampling Locations m . . . .
Distance and Direction From Unit No.1 Sample Location Station Distance Direction Collection REMARKS Media No. (Miles) Frequency Soil Fredericks Hall 02 5.30 1 SSW Once per 3 yrs ; (continued) Mineral VA 03 7.10 WSW, Once per 3 yrs i Wares Crossroads 04 5.10 WNW. Once per 3 yrs .~ Route 752 05 - 4.20 -NNE Once per 3 yrs Stu geon's Creek Marina OSA 3.20 N Once per 3 yrs Levy, VA 06 4.70- ESE Once per 3 yrs Bumpass, VA 07 7.30 SSE 'Once per 3 yrs End of Route 685 21 1.00 WNW Once per 3 yrs Site Boundary Route 700 22 1.00 WSW Once per 3 yrs Site Boundary
" Aspen Hills" 23 0.93 SSE Once per 3 yrs Site Boundary Orange, VA 24 22.00 NW Once per 3 yrs Contml Milk Holladay Dairy 12 8.30 NW Monthly (R.C. Goodwin)
Terrell's Dairy
- 13 5.60 SSE ' Monthly - l (Frederick's Hall)
Fish Waste Heat Treatment Semi-Facility (Second Cooling 08 1.10 SSE Annually i Lagoon) Lake Orange 25 16.50 NW S*"I' ' Contsul Annually Food Products Route 713 14 vanes NE (PN2) Edible Route 614 15 varies SE Monthly broadleaf if available, vegetation") Route 629/522 16 varies NW or at harvest control Route 685 21 varies WNW
" Aspen Hills" Area 23 varies SSE
- a. (PN2} If edible broadleaf vegetation is unavailable, non-nlible vegetation of similar leaf characteristics may be substituted.
4 i l .
1 i ' VPAP-0502 o REVISION 7 ) . PAGE 109 OF 159 I Procedure Action Request (PAR) J -- Attachrnent 2 instructions for completing this form are included in VPAP-0502.
.* 2. Revison yumoer 4.Page
! l 1.\7R- h"ure NumberP-alo3 7 3.C[S9e i ,iie 1 i oi 6 hva,
- 5. hftectlYo m Date (11 n l ls.er0o,4esitz l
+
- 8. Type of Request h sw Calesi&a 1%/ 7. Exo rati6n osi.
{ l l ONew ProcedurehProcedure Change Procedure Revision I Procedure De'etion
- 9. Reason and Desenpton of Change
-- North /%*e ()<h %
Vendor Pr- -M \ rAe EPA a 4 Arn L 4 sqpat of & gar pafemagrW MJcd-( &ndron~nt</% M Infna Q W r t % p s L. L. 3. q ., L..( 3b a.n d (,. c,. 3 . c . I
/%%y pag ran .
l 6 J i+a,-,- ( cha r +0 s +e p i . '7.1 l Po L 'h dac{od eLS pasos i i h Note: If " PAR" le to request a REVISION ONLY, .;Gy items 10 through 20, fi
] 10. Is this request for a new procedure?
4 8 " \ Yes MNoj l 11. Does this change result in a "Yes' answer to any questions Yes on the
]Nol
- 12. 'Soecial Does the cover sheet of this procedure indcate *Intreguently Conducted or Cornpnex Test or Evoluten or Test.* or is EPIP or See Yu ure or EOP or Fire Protection P m? No 4
- 13. A change to the stated Purpose of the procedure.
[~~) Yes gNo l 14. A change in the stated initial Conditions that must be satisted prior to performing the proce l(,,,,) Yes '[ Nol l 15. A change in the stated Acceptance Crfteria that must be satisfed for satisfactory co l 16. A moditcaten or deletion of setpoints, independent, or simultaneous verifcation. Cyes ] Nol l IYes YNol
- 17. A change that attacts specite actons that are required to be accompitshed to ensure the satsstamor completon of the task. This includes changes that affect persotined safety, decrease fire protection l Yes hNo the tas 4 effectiveness, aff ect equipment qualification. or involve a less conservative method lof performing l 18.procedure A change that which relocates includes a holdor deletes a reqJtred hold pomt. This does not include deleting al secton of a point.
y,, gl l 19. A change to CAUTION of WARNLNG statements. This does not include adding CAUTION or WARNING l statements or deleting a section of a procedure which includes CAUTION or WARNING statements. l 20. A change that modthes or deletes the method for meeting a commitment identified i l l yes h2l
- 21. Ryuesteo idy Name (Psease Pnrit) Yes
- 22. Date No l
(, A lQ(OhfIAO }9 i5. G it SNSOC approval is regured lor a procedure change, it et not noosem l Shift Supervisor to approve the procedure chanoe, pisos N/A h blodt 28. I { @23. SNSOC i 024.casatzatuaameatB 25. coontz at u a e - at ^ i
- 26. Required Approval Authority (Sgnature) I l
b 27. Date i
- 28. Shift Supervisor Approval For Changes (Sgnature) h.-2.0 9 c-3 b 29. Date
- 30. Staten Manager Approvalit Required (Sgnature) -
$ .31.pate l
{ Kr.y: SNSOC Staten Nuc6 ear Setety and W ting Committee; L":"imergency ~.^ . M h '=m@rassenveg.esi I. Procedures; EOP-Emer;H.r.cy Opsreting Procedure, PAR "rw-dure Action Pm C. t aing A i
VPAP4103 RJ FA'l Py2M ; O Activity Screening Checklist V GOV 02 VPAP-3001'
- 1. Identification of Governing Document 2. Applicable Station
- 3. Apphcable Una
\/() $ - a 10,3 8 North Anna Power Station @ Surry Power Station QUnrt1 @ Unit 2
- 4. Bnet Desenption of the Activity
&Je' f;f>., d re -[ern nes ' h $ f/*/1 bnuiranmetilR/' 0 t/td o eIt rs Jabtraf)ry
%-for e,4 m p ee ESrn LO rog rerrn . Ce r ru & re lero n c<- sh W e.ic, 4 />r>Y M lify Co,,T,s7 m ei, val cf h w /L//ft,#
,a A & nyno <nc,4 & tp nyamUQnn'drm D,'pgl[A&
- 5. Gefieth Screening (Defi%)tions are provided in VPAP.3001.)
A. Does this activity require a change to the Operating License or Technical Specifications? Yes @ No B. Does this activny alter ( temporarily or permanently) the information, design, function, ability to function, or method of performing the f unction of a structure, system, or component as described in the SAR? C Yes @No C. Does this activity modify a procedure or method of operation as described, outlined, or summanzed in the SAR? Yes No D. Does this activity perform a test or expenment that is not described in the SAR? O ves E No E. Does this activity involve a change to the Environmental Protection Plan, or a change, test, or experiment that may affect the environment? Yes @ No F. Does this activity involve a temporary moddication? Yes QNo
- 6. Discussion and References
.b N 11 b b)* l lbe lY U /E /t-llkr W4 YJW NG}' l ?)/ff [ ch Yke$/~ /h2kryh Y y m/4q'{c fb a Tn 8'r /G der a 7'? oy Of"/2 0 t /J 'O j';)rog rem s s' S fjo/rY 6 f g g g/g /cg t ,lrf) bn p*rlch />rCn *bil Niv fYOl'!N J0f![ N % ,
/ /s)rfit. w e t--
p ,, ,-6 Je&e .t /. a.sje esmm mo 7'r p<ir bey 6r + M ar, f p () anc//tr .4'fC C/iPrr,p/ T,&r4derbr,y &m,,o a , ,3 gi,, o fC P Cc19 Nff N ' IN [fjc v //"Of l l l l Note if Any Response is "Yes." a Safety Evaluation Must be Perto ed in Accordance With VPAP 3001, Safety Evaluation's.
- 7. Pre arer Name (Please Pnnt) B. Title O J7 / /2 O D/$f" flY fsbQ T)C)
- 9. Pre r Segna
~
- 10. Dat er Name (Only if No
- 11. ReSv k/fei t L . kn Authonzed 'o n Preparer-P6 ease Pnnt) 12. Tibt eed A/udcn krovdva' \Wo.Tp-
"~ "*"'*f D M Key: SAR-Satcy Analysis Report
- o. t' h
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1 l O MGMIA MER Station Administrative Procedure .
, ,, 4 y,,,,,, ,,,,,, ay,,, m l
Title:
Offsite Dose Calculation Manual l Lead Department: Radiological Protection
~
Procedure Number Revision Nun;ber Effective Date VPAP-2103 =
'7 '
10-31-95 l Revisiou Summary
. Incorporates PS1: Changes ATTACIniENT 22, Surry Environmental Sa ling Locations to replace Walnut Point oyster sampling location with Kingsmill oyster sampimg location on page 128 Incorporates PN1: Changes ATTACHMENT 23, North Anna Environmental Sampling j Locations to correct Emergency TLD locations on pages 129 and 130, adds reference 3.1.22, Deviation Report N94-1137, Improper Placement of Emergency TLDs to page 9
. Corrects units ofII33 concentration to pCi/cc at 4.5, Dose Equivalent I-131 on page 10
, . Reflects Surry Core Uprate to 2546 MWt at 4.13, Rated Thermal Power on page 12 ,
l Surry Power Station North Anna Power Station l Approved by: Approved by: h OtSW 9/2the bAb) io.s4r SNSODChairman Date SNSOC Chairman Date Appro ed by: Approved by: Station Manager M7 Pif Date tONM Station Manager Dat'e Approved by: / Vice President-Nuclear Operations Date
I VIRGINIA VPAP-2103 POWER REVISION 7 -
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VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 3 OF 156 TABLE OF CONTENTS Section l Pagg
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I.0 PURPOSE 7 2.0 SCOPE' 7 3.0 REi1RENCES/ COMMITMENT DOCUMENTS 8 4.0 DEFINITIONS 9 5.0 RESPONSIBILITIES 13 6.0 INSTRUCTIONS 15 6.1 Sampling and Monitoring Criteria 15 6.2 Liquid Radioactive Waste Emuents 15 6.2.1 Liquid Effluent Concentration Limitations 15 6.2.2 Liquid Monitoring Instrumentation 16 6.2.3 Liquid Effluent Dose Limit 20 6.2.4 Liquid Radwaste Treatment 23 , 6.2.5 Liquid' Sampling 24 , 6.3 Gaseous Radioactive Waste Emuents 24 6.3.1 Gaseous Effluent Dose Rate Limitation 24
- 6.3.2 Gaseous Monitoring Instrumentation 27
- 6.3.3 Noble Gas Effluent Air Dose Limit 30 i .
6.3.4 1-131,133, H-3 & Radionuclides in Particulate Form Effluent Dose Limit 33 6.3.5 Gaseous Radwaste Treatment - 36 6.4 Radioactive Liquid and Gaseous Release Permits 38 6.4.1 Liquid. Waste Batch Release Permits 38 6.4.2 Continuous Release Permit 39 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit 39 6.4.4 Reactor Containment Release Permits 40 6.4.5 Miscellaneous Gaseous Release Permit 40 1 4
. VIRGINIA VPAP-2103 d'".
- POWER REVISION 7 -
PAGE 4 OF 156 TABLE OF CONTENTS (continued) C Section Page , 6.4 Radioactive Liquid and GM Release Permits (continued) 6.4.6 Radioactive Liqpid , and Gaseous Release Controls 40 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 41 6.6 IEa'diological Environmental Monitoring _ 43 6.6.1 Monitoring Program ~ V" 43 6.6.2 Land Use Census 45 6.6.3 Interlaboratory Comparison Program 46 j 6.7 Reporting Requirements ;. 47 6.7.1 Annual Radiological Environmental Operating Report 47 l 6.7.2 Annual Radioactive Effluent Release Report . ' 48 6.7.3 Annual Meteorological Data 49 6.7.4 Changes to the ODCM 50 7.0 RECORDS 51 A'ITACHMENTS - 1 Surry Radioactive. Liquid Emuent Monitoring Instrumentation 53 2 North Anna Radioactive Liquid Emuent Monitoring Instrumentation 55 3 Surry Radioactive Liquid Effluent Monitoring Instrumentation 57 Surveillance Requirements 4 North Anna Radioactive Liquid Effluent Monitoring Instrunentation 59 Surveillance Requirements 5 Liquid Ingestion Pathway Dose Factors for Surry Station Units I and 2 61 6 North Anna Liquid Ingestion Pathway Dose F. actor Calculation Units I and 2 63 7 North Anna Liquid Pathway Dose Commitment Factors for Adults 69 8 Surry Radioactive Liquid Waste Sampling and Analysis Program 71 9 North Anna Radioactive Liquid Waste Sampling and Analysis Program 75 10 Surry Radioactive Gaseous Waste Sampling and Analysis Program 79 11 North Anna Radioactive Gaseous Waste Sampling and Analysis Program 85 12 Gaseous Emuent Dose Factors for Surry 89 13 Gaseous Emuent Dose Factors for North Anna 93
n VIRGINIA VPAP-2103 W - POWER REVISION 7 PAGE 5 OF 156 TABLE OF CONTENTS (continued) - Section Page A'ITACHMENTS (continued)l 14 Surry Radioactive GaseousEmuent Monitoring Instrumentation 97 , 15 Surry Radioactive Gaseous Emuent Monitoring Instrumentation 99 16 $urrf Radioactive Gaseous Effluent Monitoring Instrumentation 105 Surveillance Requirements 17 North Anna Radioactive Gaseous Effluent Monitoring Instrumentation 107 Surveillance Requirements 18 Critical Organ and Inhalation Dose Factors for Surry 111 19 Critical Organ Dose Factors for North Anna 113 j 20 Surry Radiological Environmental Monitoring Program 115 21 North Anna Radiological Environmental Monitoring Program 119 22 Surry Environmental Sampling Locations 125 23 North Anna Environmental Sampling Locations 129 24 Detection Capabilities for Surry Environmental Sample Analysis 133 25 Detection Capabilities for North Anna Environmental Sample Analysis 135 26 Reporting Levels for Radioactivity Concentrations in Environmental 137 Samples at Surry 27 Reporting Levels for Radioactivity Concentrations in Envimnmental 139 Samples at North Anna 28 Surry Meteorological, Liquid, and Gaseous Pathway Analysis 141 29 North Anna Meteorological, Liquid, and Gaseous Pathway Analysis 149 l l
E r VIRGINIA VPAP-2103 , POWER REVISION 7 PAGE 6 OF 156
, 7, ;
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- VIRGINIA VPAP-2103 I: POWER
. REVISION 7 PAGE 7 OF 156 1.0 PURPOSE The Offsite Dose Calculation Manual (ODCM) establishes equirements for the Radioactive Emuent and Radiological Envirdnmental Monitoring Programs. Methodology and parameters ~'
are provided to calculate offsite doses resulting from radioactive gaseous and liquid effluents, to calculate gaseous and liquid effluent monitoring alarm / trip setpoints, and to conduct the . Environmental Monitoring Program. Requirements are established for the Annual . Radiological Environmental Operating Report and the Annual Radioactive Emuent Release ! Report required by Station Technical Specifications. Calculation of offsite doses due to radioactive liquid and gaseous emuents are performed to assure that: l- ~' '
. Concentration of radioactive liquid emuents to the unrestricted area will be limited to ten times the effluent concentration values of 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases and 2E-4 pCi/ml for dissolved or entrained noble gases. .
. Exposure to the maximum exposed member of the public in the unrestricted area from radioactive liquid effluents will not result in doses greater than the liquid dose limits of 10 CFR 50, Appendix I
. Dose rate at and beyond the site boundary from radioactive gaseous emuents will be limited 1 to:
.. Noble gases -less than or equal to a dose rate of 500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin
.1333, 1 133, and H3 , and all radionuclides in particulate form with h'alf lives greater than 8 i
days - less than or equal to a dose rate of 1500 mrem /yr to any organ l
. Exposure from radioactive gaseous effluents to the maximum exposed member of the public in the unrestricted area will not result in doses greater than the gaseous dose limits of 10 CFR 50, Appendix 1.and
. Exposure to a real individual will not exceed 40 CFR 190 dose limits 2.0 SCOPE This procedure applies to the Radioactive Effluent and Environmental Monitoring Programs at Surry and North Anna Stations.
i
b VIRGINIA VPAP-2103 ' POWER REVISION 7 - PAGE 8 OF 156
3.0 REFERENCES
/ COMMITMENT DOCUMENTS 3.1 References 3.1.1 10 CFR 20, S'tandards for tectibr's Ng' a in$t 10dliAtion'
- 3.1.2 10 CFR 50, Domestic Licensing of Pbuction and kJtil'ization Facilities 3.1.3 40 CFR 190, Environmental Radiation Pro'tection Standards for Nuclear Power ;
Operations 3.1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites 3.1.5 Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents fron-Light-Water-Cooled Nuclear Power Plants, Rev.1, U.S. NRC, June 1974 3.1.6 Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR 50, Appendix I, Rev.1 U.S. NRC, October 1977 3.1.7 Regulatory Guide 1.111, Methods for Estimating Atmospheric' Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Rev.1 U.S. NRC, July 1977 3.1.8 Surry and North Anna Technical Specifications (Units 1 and 2) 3.1.9 NUREG-0324, XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, U.S. NRC, September 1977 3.1.10 NUREG/CR-1276, Users Manual for the LADTAP 11 Program, U.S. NRC, May,1980 3.1.11 NUREG-0597, User's Guide to GASPAR Code, U.S. NRC, June,1980 3.1.12 Radiological Assessment Branch Technical Position on Environmental Monitoring, November,1979 Rev.1 3.1.13 NUREG-0133. Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations, October,1978 3.1.14 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 3.1.15 NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, Rev. 3, March 1982 3.1.16 Environmental Measurements Laboratory, DOE HASL 300 Manual 3.1.17 NRC Generic Letter 89-01, implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS)in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program 3.1.18 UFSAR (SurTy and North Anna)
VIRGINIA VPAP-2103
- . POWER REVISION 7 !
PAGE 9 OF 156 3.1.19 Nuclear Reactor Environmental Rndiation Monitoring Quality Control Manual, IWL-0032-361 3.1.'2 0 VPAP-2802, Notifications and Reports 3.1.21 NAPS Circulating Water System Modifications . _
- a. DC-85-37-1 Unit 1
- b."DC-85-38-2 Unit 2 3.1.22 Deviation Report N94-1137, Improper Placement of Emergency TLDs l 3.2 Commitment Documents .
3.2.1 Quality Assurance Audit Report Number C 90-22, Management Safety Review Committee, Observation 03C, January 17,1991 i 3.2.2 Quality Assurance Audit Report Number 91-03, Observation 08N 3.2.3 Quality Assurance Audit Report Number 92-03, Observation 02N 3.2.4 Quality Assurance Audit Report Number 92-03, Observation 04NS (ltem 2) 4.0 DEFINITIONS > 4.1 Channel Calibration Adjustment, as necessary, of the channel output so it responds with the necessary range and accuracy to known values of the parameter the channel monitors. It encompasses the entire channel, including the sensor and alarm and/or trip functions and the Channel Functional Test. 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. This assessment includes, where possible, comparison of the channelindication 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 Channel injection of a simulated signal into a channel, as close to the sensor as practicable, to verify Operability, including alarm and/or trip functions.
U-VIRGINIA VPAP-2103
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POWER REVISION 7 - PAGE 10 OF 156 4.3 Channel Functional Test (continual) - + 4.3.2 Bistable Channel Injection of a simulated signal into a sensor to verify Operability, including alarm and/ or trip functions. ' . 4.4 Critical Organ - That or-jan, which has been determined to be the maximum exposed organ based on an effluent pathway analysis, thereby ensuring the~ dose and dose rate limitations to any organ will not be exceeded. 2 t 4.5 Dose Equivalent I-13I F That concentration of1131 (pCi/cc ) that alone would produce the same thyroid dose as the l quantity and isotopic mixture of1131, 1132,g133,y134,and1135 actually present. 'Ihyroid dose conversion factors for this calculation are listed in Table III of TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites. Thyroid dose conversion factors from NRC Regulatory Guide 1.109, Revision 1, may be used (Surry).' 4.6 Frequency Notations NOTE: Frequencies are allowed a maximum extension of 25 percent. ~' i NOTATION FREQUENCY D Daily At least once per 24 hours W - Weekly At least once per 7 days , M - Monthly At least once per 31 days Q - Quarterly At least once per 92 days S A - Semi-annually At least once per 184 days R - Refueling At least [nce per 18 months S/U - Start-up Prior to each reactor start-up P - Prior to release Completed prior to each release N. A. - Not applicable Not applicable DR - During the release At least once during each release I
o VIRGINIA VPAP-2103 i P*. POWER REVISION 7 l PAGE 11 OF 156 l l 4.7 Gaseous Radwaste Treatment System A system that reduces radioactive gaseous effluents by collecting primary coolant system offgases from the primary systeni and providing delay or holdup to reduce total radioactivity prior to release to the environment. The system comprises the waste gas decay tanks, - regenerative heat exchanger, waste gas charcoal filters, process vent blowers, waste gas surge tanks, and waste gas diaphragm compressor (North Anna); - 4.8 General Nomenclature x = Chi: concentration at a point at a given instant (curies per cubic meter) D = Deposition: quantity of depo' sited radioactive material per unit area (curies per square meter) Q = Source strength (instantaneous; grams, curies)
= Emission rate (continuous; grams per second, curies per second) ;
= Emission rate (continuous line source; grams per second per meter)
, 4.9 Lower Limit of Detection (LLD) )
The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that can be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal. t 4.10 Members of the Public Individuals who, by virtue of their occupational status, have no formal association with the Station. This category includes non-employees of Virginia Power who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with Station ! functions. This category does not include non employees such as vending machine servicemen or postal workers who, as part of their formal job function, occasionally enter an area that is controlled by Virginia Power to protect individuals from exposure to radiation and radioactive materials. .- t 4.11 Operable - Operability l l A system, subsystem, train, component, or device is operable or has operability when it is ' capable of performing its specified functions and all necessary, attendant instrumentation, l l controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or l device to perform its functions are also capable of performing their related support functions. l 1
i VIRGINIA VPAP-2103 .E- POWER REVISION 7 - PAGE 12 OF 156 4.12 Purge- Purging - Controlled discharge of air or gas from a confinement to maintain temperature, pressure, 5 I humidity, concentration, or other operating condition, so that seplacement air or gas is required to purify the confinement.- - " - - - m. "- - 4.13 Rated Thermal Power Total reactor core heat transfer rate to reactor coolant.
. Surry - 2546 Megawatts Thermal (MWt) l
. North Anna-2893 MWt ,
4.14 Site Boundary . The line beyond which Virginia Power does not own, lease, or otherwise control the land. 4.15 Source Check A qualitative assessment of channel response when a channel sensor is exposed to radiation. This applies to installed radiation monitoring systems. 4.16 Special Report A report to NRC to comply with Subsections 6.2,6.3, or 6.5 of this procedure. Also refer to . VPAP-2802, Notifications and Reports. 4.17 Thermal Power Total reactor core heat transfer rate to the reactor coolant. 4.18 Unrestricted Area 1 Any area at or beyond the site boundary, access to which is neither limited nor controlled by ! Virginia Power for purposes of protection of individuals from exposure to radiation and j radioactive materials, or any area within the site boundary used for residential quarters or for l industrial, commercial, institutional or recreational purposes.
VIRGINIA VPAP-2103
- POWER REVISION 7 PAGE 13 OF 156 4.19 Ventilation Exhaust Treatment System A system that reduces gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and High.
Efficiency Particulate Air (HEPA) filters to remove iodines and particulates.from a gaseous-exhaust stream prior to release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not Ventilation Exhaust Treatment System components. 5.0 RESPONSIBILITIES 5.1 Superintendent Radiological Protection _. The Superintendent Radiological Protection is responsible for: 5.1.1 Establishing and maintaining procedures for surveying, sampling, and monitoring . radioactive effluents and the environment. 5.1.2 S urveying, sampling, and analyzing plant effluents and environmental monitoring, and documenting these activities. 5.1.3 Analyzing plant effluent trends and recommending actions to correct adverse trends. 5.1.4 Preparing Effluent and Environmental Monitoring Program records. 5.2 Superintendent Operations The Superintendent Operations is responsible for requesting samples, analyses, and authorization to release effluents. I
, VIRGINIA VPAP-2103 POWER REVISION 7 -
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. j VIRGINIA VPAP-2103
. POWER _ REVISION 7 l PAGE 15 OF 156 l
l 6.0 INSTRUCTIONS NOTE: Meteorological, liquid, and gaseous pathway analyses are presented in Attachments 28 l and 29, Meteorological,' Liquid, and Gaseous Pathway Analysis. 6.1 Sampling and Monitoring Criteria 6.1 l' Surveys, sampling, and analyses shall use instruments calibrated for the type and range - of radiation monitored 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. -- i 6.1.3 A sufficient number of survey points shall be used or samples taken to adequately , assess the status of the discharge monitored. 6.1.4 Samples shall be representative of the volume and type of discharge monitored. 6.1.5 Surveys, sampling, analyses, and monitoring records shall be accurately and legibly documented, and sufficiently detailed that the meaning and intent of the records are clear. 6.1.6 Surveys, analyses, and monitoring records shall be reviewed for trends, completeness, and accuracy. 6.2 Liquid Radioactive Waste Emuents 6.2.1 Liquid Emuent Concentration Limitations
- a. Liquid waste concentrations discharged from the Station shall not exceed the following limits:
1
- 1. For radionuclides (other than dissolved or entrained noble gases), liquid effluent concentrations released to unrestricted areas shall not exceed ten times the effluent concentration values specified in 10 CFR 20, Appendix B, Table 2, Column 2.
- 2. For dissolved or entrained noble, gases, concentrations shall not exceed 2E-4 pCi/ml.
- b. If the concentration ofliquid effluent exceeds the limitsin 6.2.1.a., promptly reduce l concentrations to within limits.
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VIRGINIA VPAP-2103
? POWER REVISION 7 -
PAGE 16 OF 156 6.2.1 Liquid Emment Concentration Limitations (continued) ;
- c. Daily concentrations of radioactive materials in liquid waste released to unrestricted areas shallmIet the following: w r , e '
Volume of Waste Discharged + Volume of Dilution Water
- 2. m._. m .
3g g Ci/ml. Volume of Waste Discharged x T 2 M. L ACW.I p e .j where:
'**'.'..""""'"""d t _ .
pCi/ml; = the concentration of nuclide iin the liquid effluent discharge ACW; = ten ames the effluent concentration value in unrestricted areas of nuclide i, expressed as pCi/ml from 10 CFR 20, Appendix B, Table 2, ; Column 2 for radionuclides other than noble gases, and 2E-4 pCi/ml for dissolved or entrained noble gases 6.2.2 Liquid Monitoring Instrumentation -
- a. Radioactive Liquid Emuent Monitoring Instrumentation Radioactive liquid effluent monitoring instrumentation channels shown on -
Attachments 1 and 2, Radioactive Liquid Effluent Monitoring Instrumentation, l shall be operable with their alarm / trip setpoints set to ensure that 6.2.1.a. limits are not exceeded.
- 1. Alarm / trip setpoints of these channels shall be determined and adjusted in accordance with 6.2.2.d., Setpoint Calculation.
- 2. If a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint is less conservative than required by 6.2.2.a., perform one of the followmg:
. Promptly suspend release of radioactive liquid effluents monitored by the affected channel
. Declare the channelinoperable
. Change the setpoint to an acceptable, conservative value
~
VIRGINIA VPAP-2103 I'
. POWER REVISION 7 PAGE 17 OF 156 s
1 { b. Radioactive Liquid Emuent Monitoring Instrumentation Operability
, Each radioactive liquid effluent monitoring instrumentation channel shall be
- demonstrated operable by performing a Channel Check, Source Check, Channel Calibration, and Channel Functional Test at the frequencies shown in Attachments j 3 and 4, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance l ,
Requirements. i l j 1. If the number of operable channels is less than the muumum reqmred by the i tables in Attachment 1 or 2, perform the action shown in those tables. J I l 2. Attempt to retum the instruments to operable status within 30 days. If i
- unsuccessful, explain in the next Annual Radioactive Effluent Rel ,ase Report I why the inoperability was not corrected in a timely manner. l 1 c. Applicable Monitors ,
I Liquid effluent monitors for which alarm / trip setpoints shall be determined are: i
- Release Point Instrument Number North Anna Surry )
Liquid Radwaste Effluent Line 1-LW-RM-111 N/A j Service Water System Effluent Line 1-SW-RM-108 1-SW-RM-107 A, B,C,D Condenser Circulating Water Line 1-SW-RM-130 1-SW-RM-120 , 2-SW-RM-230 2-SW-RM-220 l Radwaste Facility Effluent Line N/A 1-RRM-RITS-131
.- l VIRGINIA VPAP-2103 POWER REVISION 7 -
PAGE 18 OF 156 6.2.2 Liquid Monitoring Instrumentation (continued)
- d. Setpoint Calculation ,
, f . y: .
NOTE: This methodology does not preclude use of more conservative setpoints. - l
!. , Maximum setpoint values shall be calculated by:
CFD~ l S=p
} .. . _ , , ,
(2) where- ' i i : S = the setpoint, in pCihnt, of the radioactivity monitor measuring the radioactivity concentration in the efDuent line prior to dilution 1 C= the effluent concentration limit for the monitor used to implement 10 CFR 20 for the Station,in pCi/ml Fg = maximum design pathway effluent flow rate ,, Fo = dilution water flow rate calculated as: (Surry) D = FE+ (200,000 gpm x number of cire. pumps in service)
. (N. Anna) D = Fs + (218,000 gpm x number of cire. pumps in service) ,
- 2. Each of the condenser circulating water channels (Surry: SW-120, SW-220) 7 (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 ratioactive material addition. No dilution is assumed for this pathway. 'Iherefore, Equation (2) becomes:
l S=C (3) ! i 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 (North Anna: LW-111), the service water system effluent line (Surry: SW-107 A,' B, C, and D, North Anna: SW-108), and the Radwaste Facility effluent line (Surry: RRM 131).
, - , , . . - ,,--cm-- -
VIRGINIA VPAP-2103 P., POWER REVISION 7 PAGE 19 OF 156
- 4. For the liquid radwaste effluent line, Equation (2) becomes:
e f
"I CFD gK ,
S= (4) - FE where: Kw t
= The fraction of the effluent concentration limit, used to implement 10 CFR 20 for the site, attributable to the liquid radwaste efnuent line pathway l
- 5. For the service water system effluent line, Equation (2) becomes:
D K,3 S= (5) FE ' where: Ksw = The fraction of the effluent concentration limit, used to implement f 10 CFR 20 for the Station, attributable to the service water effluent !
. line pathway .;
- 6. For the Radwaste Facility effluent line, Equation (2) becomes:
e CFDKRW S= (6) FE where: Kgw = The fraction of the effluent concentration limit, used to implement 10 CFR 20 attributable to the Radwaste Facility effluent line pathway
- 7. The sum K w t + Ksw + KRw shall not be greater than 1.0.
.- l A
~ VIRGINIA VPAP-2103
. POWER REVISION 7 .
PAGE 20 OF 156
, 6.2.3 Liquid Effluent Dose Limit l
- a. Requiresnent
> At least once per 31 days,' perform the dose calculations in 6.2.3.c. and 6.2.3.d. to F ensure the dose or dose commitment to the maximum exposed member of the public from radioactive materials in liquid releases (from each reactor unit) to unrestricted
. areas is limited to:
- 1. During any calendar quarter: = " ~
. Less than or equal to 1.5 mrem to the total body.
r
. Less than or equal to 5 mrem _ to the critical organ
- 2. During any calendar year: ,
. Less than or equal to 3 mrem to the total body
. Less than or equal to 10 mrem to the critical organ ,
- b. Action If the calculated dose from release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that identifies causes for exceeding limits and defines corrective actions taken to reduce releases of radioactive materials in liquid effluents to ensure that subsequent releases will be in compliance with the above limits.
- c. Surry Dose Contribution Calculations NOTE: Thyroid and GI-LLI organ doses must be calculated to deternune which is the critical organ for the period being considered.
1 Dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on the equation: I D = t FM [C;A; (7) , i I t where: l l Subscripts = i, refers to individual radionuclide i i l
- 1 VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 21 OF 156 D= the cumulative dose commitment to the total body or critical organ from the liquid effluents for the period t, in mrem t = the period for'which C; and F are averaged for all liquid releases, in hours M = the mixing ratio (rxipmcal of the dilution factor) at the point of exposure, dimensionless,0.2 from Appendix 11 A, Suny UFSAR l
'F = the near field average dilution factor for C; during any liquid effluent '
release; the ratio of the average undiluted liquid waste flow during release j to the average flow from the site discharge structure to unrestricted areas ; i C; = the average concentration of radionuclide,i,in undiluted liquid effluent l during the period t, from allliquid releases, in pCi/ml ' A; = the site-related ingestion dose commitment factor to the total body or critical ! organ of an adult for each identified principal gamma and beta emitter in mrem-ml per hr-pCi. Values for Ai are given in Attachment 5, Liquid Ingestion Pathway Dose Factors For Surry Power Station. A; = 1.14 E+05 (21BF; + 5BI;) DF; (8) where:
, 1.14 E+05 = 1 E+06 pCi/ Ci x 1 E+03 ml/kg/(8760 hr/yr), units conversion factor 21 = adult fish consumption, kg/yr, from NUREG-0133 5 = adult invertebrate consumption, kg/yr, from NUREG-0133 i BI; =
the bioaccumulation factor for nuclide i, in invertebrates, pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev. I l B F; = the bicaccumulation factor for nuclide i, in fish, pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev. I j DFi= the critical organ dose convefsion factor for nuclitle i, for adults, in I mrem /pCi, from Table E-11 of Regulatory Guide 1.109, Rev.1 I
)
i 1 I
i 14 VIRGINIA VPAP-2103 POWER REVISION 7 . PAGE 22 OF 156 6 6.2.3 Liquid Emment Dese Limit (continued)' ~
- d. North Anna Dese Contribution Calculations nl .
,e .
'+....u NOTE: Attachmer.t 6, North Anna Liquid Ingestion Pathway Dose Factor Calculation provides the derivadon for Equation (9).
~^ ^
Dose contribution shall be calculated for all radionuclides identified in liquid efGuents released to unrestricted areas based on: (9) D = {Q; x B; t< -Y l Where: . Subscripts = 1, refers to individual radionuclide D= the cumulative dose commitment to the total body or critical organ from the , liquid effluents for the period t, m mrem = B= i Dose Commitment Factors (mrem /Ci) for adults. Values for Bi are provided I in Attachment 7, North Anna Liquid Ingestion Pathway Dose Commitment , Factors for Adults . Q3 = Total released activity for the considered period and the ich nuclide Qi = t x C; x Waste Flow (10) Where: t = the period for which C iand F are averaged for all liquid releases, in , hours C=i the average concentration of radionuclide,i,in undiluied liquid effluent ' during the period, t, from any liquid releases, in pCi/ml l
- e. Quarterly Composite Analyses {
For radionuclides not determined in each batch or weekly composite, dose i contribution to current monthly or calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on previous monthly or quarterly composite analyses. However, for reporting purposes, calculated dose contribution shall be based on the actual composite analyses.
--_ _ _ _ , , - _- . __ _ . _ ..,3
._m-
VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 23 OF 156 6.2.4 Liquid Radwaste Treatment
- a. Requirement
- 1. The Liquid Radwa' ste Treatment System and/or the Surry Radwaste Facility ,
Liquid Waste System shall be used to reduce the radioactive materials in liquid l 1 waste prior to discharge when projected dose due to liquid effluent, from each ! reactor unit, to unrestricted areas would exceed 0.06 mrem to total body or 0.2
-{
mrem to the critical organ in a 31-day period. , l
- 2. Doses due to liquid releases shall be projected at least once per 31 days.
- b. Action ,_
If radioactive liquid waste is discharged without treatment and in excess of the above limits prepare and submit to the NRC, within 30 days, a special report in , accordance with VFAP-2802, Notifications and Reports, that includes the following: , 1. An explanation of why liquid radwaste was being discharged without treatment, , identification of any inoperable equipment or sub-system, and the reason for the inoperability.
~
- 2. Actions taken to restore inoperable equipment to operable status.
- 3. Summary description of actions taken to prevent recurrence.
l
- c. Projected Total Body Dose Calculation
- 1. Determine D.rs, the total body dose from liquid effluents in the previous 31-day i period, per Equation (7) or Equation (9) (Surry and North Anna, respectively). l
- 2. Estimate R 3, the ratio of the estimated volume ofliquid effluent releases in the present 31-day period to the volume released in the previous 31-day period. .
- 3. Estimate F 3, the ratio of the estimated liquid effluent radioactivity concentration 1 in the present 31-day period to liquid effluent concentration in the previous 31- i day period (pCihn!).
I
- 4. Determine PD.rs, the projected total body dose in a 31-day period.
PDTB = DTB(R3F3 ) (11) i
^
VIRGINIA VPAP-2103 POWER REVISION 7 .- PAGE 24 OF 156 6.2.4 Liquid Radwaste Treatment (continued) .a.
- d. Projected Critical Organ Dese Calculation Historical data pertaining b the volumes and radioactivity ofliquid effluents released in' connection with specific Station functions, such as maintenance or refueling outages, shall be used in projections as appropriate.
- 1. Determine D., the critical organ dose from liquid effluents in the previous 31-day period, per Equation (7) or Equation (9) (Suny and North Anna, respectively). - <- =s" '
- 2. Estimate R 3as in 6.2.4.c.2.
- 3. Estimate F ias in 6.2.4.c.3. t
- 4. Determine PD, = projected critical organ dose in a 31 day period.
PDg = DO @lF) i (12) 6.2.5 Liquid Sampling . Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis requirements in Attachments 8 and 9, Radioactive Liquid Waste . Sampling and Analysis Program (Surry and North Anna, respectively). 6.3 Gaseous Radioactive Waste Emuents 6.3.1 Gaseous Emuent Dose Rate Limitation
- a. Requirement l Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to:
- 1. The dose rate limit for noble gases shall be s 500 mrem / year to the total body and s 3000 mrem / year to the skin.
- 2. The dose rate limit for1133. 1133, for tritium, and for all radioactive materials in particulate form with tw'-lives greater :han 8 days shall be s 1500 mrem / year to the critical organ.
- b. Action
- 1. If dose rates exceed 6.3.1.a. limits, promptly decrease the release rate to within the above limits.
.g 9
_ ., , - _ , - . - +- -= +
~ .4 VIRGINIA VPAP-2103
+ -
. POWER REVISION 7 PAGE 25 OF 156
- 2. Dose rates due to noble gases in gaseous effluents shall be determined, l ,
. continuously, to be within 6.3.1.a. limits.
- 3. Dose rates dueio $131,1333, tritium, and all radionuclides in particulate form with half-lives gmater than 8 days, in gaseous effluents shall be determined to i be within the above limits by obtaining repmsentative samples and performing analyses in accordance with the sampling and analysis program specified on '
i Attachments 10 and 11, Radioactive Gaseous Waste Sampling and Analysis Program. se a ed 4 O , s' a W- - - __.
VIRGINIA VPAP-2103 k POWER REVISION 7 - PAGE 26 OF 156
,_ 6.3.1 Gaseous Emment Dose Rate Lindtation (continued) > - -
- c. Calculations of Gaseous Emuent Dose Rates ,
- 1. The dose rate limit for noble gases shall be determined to be within the limit by limiting the release rate to the lesser of: -
~
[K; djyy + K;pydj y)ps 500 mrem /yr to the total body .(13)
)
l OR l
.u..
M yy + 1.1M gy , ) d;yy + (Lp 1.1M p )d y]ip s 3000 mrem /yr to the skin (14) where: Subscripts = vv, refers to vent releases from the building ventilation vent, including Radwaste Facility Ventilation Vent; py, refers to the vent releases from the process vent; i, refers to individual radionuclide K;yy,K;py = The total body dose factor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide i, in mrem /yr per Curie /sec. Factors are listed in Attachments 12 and 13, Gaseous Effluent Dose Factors (Surry - i and North Anna, respectively) Livy, l.ipv = The 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 M iy y, M;py = The air dose factor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide, i, in mrad /yr per Curie /sec. Factors are listed in Attachments 12 and 13' d.d, = The release rate for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents in Curie /sec (per site) , 1.1 = The unit conversion factor that converts air dose to skin dose, in mrem / mrad
4 , l 1 VIRGINIA VPAP-2103 l
,. POWER REVISION 7 PAGE 27 OF 156 j 2. Thedoseratelimitfor1131, 1' 133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days, shall be determined to be within the limit by restricting the release rate to: l
((P;yy dyy+P;pyd;py] i s 1500 mrem /yr to the critical organ (15) i , .
- i 4 where:
Piyy, Pipy = ' The critical organ dose 3 factor for ventilation vents or process ventfor1131, I 3, H , and all radionuclides in particulate form with half-lives greater than 8 days, for the inhalation pathway, in mrern/yr per Curie /sec. Factors are listed in Attachments 12 i and 13 i dwd, = The release rate for ventilation vents or process vent of1133, 4 1133, H3 , and all radionuclides i, in particulate form with half- 1 i lives greater than 8 days,in gaseous effluents in Curie /sec (per site)
- 3. All gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of dw .
l . 6.3.2 Gaseous Monitoring Instrumentation ,j
- a. Requirement
- 1. The radioactive gaseous effluent monitoring instrumentation channels shown in Attachment 14 or 15, Radioactive Gaseous Effluent Monitoring
- Instrumentation, shall be operable with alamvirip setpoints set to ensure that 6.3.1.a. noble gas limits are not exceeded. Alarm / trip setpoints of these channels shall be determined and adjusted in accordance with 6.3.2.d.
?
- 2. Each radioactive gaseous effluent monitoring instrumentation channel shall be ,
demonstrated operable by Channel Checks, Source Checks, Channel ! Calibrations, and Channel Functio $al Tests at the frequencies shown in Attachment 16 or 17. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements. 1
VIRGINIA VPAP-2103
- POWER --
REVISION 7 PAGE 28 OF 156 g 6.3.2 Gaseons Monitoring Instrumentation (continued)
- b. Action -
I i l
- 1. If a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint is less conservative than required by 6.3.2.a.1, pmmptly:
- Suspend the release of radioactive gaseous effluents monitored by the affected
~ channel and declare the channelinoperable
- or
- Change the setpoint so it is a%i.bly conservative 1
- 2. If the number of operable channels is less than the minimum required by tables
{ in Attachment 14 and 15, take the action shown in those tables.
- 3. Return instruments to operable status within 30 days. If unsuccessful, explain 1
in the next Annual Radioactive Effluent Release Report why the inoperability I was not corrected in a timely manner. '
- c. Applicable Monitors Radioactive gaseous effluent monitors for which alarm / trip setpoints shall be !
determined are: 1 Release Point Instrument Number North Anna Surry Process Vent 1-GW-RM-102 1-GW-RM-102 l l-GW-RM-178-1 1-GW-RM-130-1 i Condenser Air Ejector 1-SV-RM-121 1-SV-RM-111 2-SV-RM-221 2-SV-RM-211 Ventilation Vent A 1-VG-RM-104 N/A 1-VG-RM-179-1 Ventilation Vent B l-VG-RM-ll3 N/A 1-VG-RM-180-1 Ventilation Vent No.1 N/A 1-VG-RM-104 l Ventilation Vent No. 2 N/A 1-VG-RM-110 1-VG-RM-131-1 Radwaste Facility Vent N/A RRM-101 l l
__ .- .-- -- - - - ' ~ ~ i !' VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 29 OF 156 4
- d. Setpoint Calculations
, 1. Setpoint calculations for each monitor listed in 6.3.2.c. shall maintain this relationship: 3.. l D2Dpy + D c ,;4 D, (161
~
i - where: D = Step 6.3.1.a. dose limits that implement 10 CFR 20 for the Station, i mrem /yr Dpy = The noble gas site boundary dose rate from process vent gaseous effluent releases, mrem /yr
- D. =
The noble gas site boundary dose rate from condenser air ejector gaseous effluent releases, mrem /yr D.n = The noble gas site boundary dose rate from: Suny: Summation of the Ventilation Vents 1,2, and the Radwaste Facility vent gaseous effluent releases, mrem /yr North Anna: Summation of Ventilation Vent A plus B gaseous effluent releases, mrem /yr 4 L
VIRGINIA VPAP-2103 ' r POWER REVISION 7 - PAGE 30 OF 156 g 2. Setpoint values shall be determined by:
, -. , . . , . 4,_-,.. ... , .
- . # . l. -
R" x 2.12 E 03
._ .. C, . = p ,. , (17) -
m where: ,, m = ne release pathway, process vent (py),' ventilation vent (vy) condenser air ejector (cae),'ar Radwaste Facility (rv)
~
C. = The effluent concentration 1iNiit implementing 63.1.a. for the Station, Ci/ml' - . R. ; ne release rate' limit for pathway m huJned from methodology in 6.3.1.c., using Xe l33 as nuclide to bereleased, Ci/sec 2.12E-0.i = CFM per ml/sec Fm = The maximum flow rate for pathway m, CFM NOTE: According to NUREG-0133, the radioactive effluent radiation monitor alarm / trip setpoints should be based on the radioactive noble gases. It is not practicable to apply instantaneous alarm / trip setpoints to integrating monitors sensitive to radiciodines, radioactive materials in paniculate form, and radionuclides other than noble gases. - 6.3.3 Noble Gas Emuent Air Dose Limit
- a. Requirement
- 1. The air dose in unrestricted areas due to noble gases released in gaseous effluents from each unit at or beyond the site boundary shall be limited to:
. During any calendar quarter: 55 mrads for gamma radiation and 510 mrads for beta radiation
. During any calendar year: s 10 mrads for gamma radiation and 520 mrads for beta radiation
- 2. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be aetermined in accordance with 6.3.3.c. at .
least once per 31 days.
~
j .
VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 31 OF 156
.b. Action If the calculated air dose from radioactive noble gases in gaseous effluents exceeds any of the above limi.fs, prepare and submit to the NRC, within 30 days, a special .
report in accordance with VPAP-2802, Notifications and Reports, that identifies the causes for exceeding the limits and defines corrective actions that have been taken
.to reduce releases and the proposed corrective actions to be taken to assure that ,
subsequent releases will be in compliance with the limits in 6.3.3.a.
- c. Noble Gas Emuent Air Dose Calculation . .,
Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qivv. The air dose to areas at or beyond the site boundary due to noble gases shall be determined by the following: For gamma radiation: D g = 3.17E-08((M;yyD;yy + M;py ;py] i (18) I 1
.. l
- i. 9 VIRGINIA VPAP-2103 POWER REVISION 7 .-
l PAGE 32 OF 156 For beta radiation: c l . D (19) b = {.17N-08 [Ng Qiyy + N;pyQ;py]
.wp iih i O n'. , _ ,
Where: , .
~'
Subscripts = vv, refers to vent relesec from the buildmg ventilation vents,
- including the Radwaste Facility Ventilation Vent and air
! ejectors - ' - " " - l pv, refers to the. vent relemmes from the process vent I i, refers to individual radionuclide , , Dg = the air dose for jamma radiation, in mrad Db = the air dose for beta radiation, in mrad Mivy, Mipv = the air dose factors for ventilation vents or' process vent release due to gamma emissions for each identified noble gas radionuclide i, in mrad /yr per Curie '/sec. Factors are listed in Attachments 12 and 13 '
%Nv =ipthe air dose factor for ventilation vents or process vent release due to beta emissions for each identified noble gas radionuclide i, in mrad /yr per Curie /sec. Factors are listed in
. Attachments 12 and 13 ,
Qvy,Qpy = the release for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents for 31 days, quarter, or year as appropriate in Curies (per site) S' l l 1
VIRGINIA VPAP-2103
. , POWER .
REVISION 7 PAGE 33 OF 156 , 6.3.4 I-131,133, H 3 & Radionuclides In Particulate Form Emuent Dose Limit
- a. Requirement
- 1. Methods shall beimplemented to ensure that the dose to any organ of a member of thepublicfrom1131, 1333, tritium, and all radionuclides in particulate form with half lives greater than 8 days,in gaseous effluents released from the site to i
1 unrestricted areas from each reactor unit shall be:
- . During any calendar quarter
- 57.5 mrem to the critical organ i
. During any calendar year: s 15 mrem to the critical organ 1
j 2. Cumulative dose contributions to a member of the public from 1131, Il33, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to unrestricted areas for the current calendar 4 quarter and current calendar year shall be determined at least once per 31 days in accordance with 6.3.4.c. or 6.3.4.d. / , j b. Action If the calculated dose from the release of1131, 1133, tritium, and radionuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that contains the:
- 1. Causes for exceeding limits.
- 2. Corrective actions taken to reduce releases.
- 3. Proposed corrective actions to be taken to assure that subsequent releases will be in compliance with limits stated in 6.3.4.a.
- c. Surry Dose Calculations L
Gascous releases, not through the procpss vent, are considered ground level and shall be included in the determination of 6 . Historical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection to specific Station functions, such as containment purges, shall be used in the estimates, as appropriate. e
VIRGINIA VPAP-2103 POWER REVISION 7 .- PAGE 34 OF 156 I. 'Ihe dose to the maximum exposed member of the public, attributable to
, gaseous effluents at and beyond the site boundary that contain 1131, 1133, tritium, and particulate-form r$dionuclides with half lives greater than 8 days, chall be i determined by: - -
. " r- "a- ,
l l D, = 3.17E 08 [(RM;yydgy, + RM dipy) + (RI gyy dy,+RI p 3py)] d (20) i
. . . . . .. m.u ... . - ..
Where: . Subscripts = vv, refers to vent releases from the building ventilation vents, c including the Radwaste Facility Ventilation Vent and air
, ejectors; ,. .
py, 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 RMivy, RMipv= the cow-milk pathway dose factor for ventilation vents or process vent release due to I131, 1133, tritium, and from all particulate-form radionuclides with half-lives greater than 8
~
days, in mrem /yr per Curie /sec. Factors are listed in
~
Attachment 18, Critical Organ and Inhalation Dose Factors For Surry RIvy,RI i ipv = the inhalation pathway dose factor for ventilation vents or process vent release due to 1131, I133, tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in traem/yr per Curie /sec. Factors are listed in Attachment 18 d.6, = the release for ventilation vents or process vent of 1131. I133, tritium, and from all particulate-form radionuclides with half-lives greater than 8 days in Curies 3.17, E-08 = the inverse of the number of seconds in a year
VIRGINIA VPAP-2103 e .. . POWER REVISION 7 PAGE 35 OF 156 6.3.4 I-131, I 133, H 3, and Radionuclides In Particulate Form Emuent Dose Limit (continued)
, i
- d. North Anna Dese, Calculations ,
Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of D Historical data pertaining to the
, volume's and radioactive concentrations of gaseous effluents released in connection . -
to specific Station functions, such as' containment purges, shall be used in the
~ ~~
estimates as appropriate. I. The dose to the maximum exposed member of the public, attributable to gaseous effluents at and bey}ond the site boundary, that contain 1131, 1133, tritium, and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by: 1 _ _ t
)
r = 3.17E-08((RM;yy Q iyy + RM;pyQipy. (21) i Where: Subscripts = vv, refers to vent releases from the building ventilation vents; py, 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 RM ivy, RMipv =the cow-milk dose factor for ventilation vents or process vent release due to I131, Il33, tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in mrem /yr i per Curie /sec. Factors are listed in Attachment 19, Critical Organ Dose Factors for North Anna 6.6, = the release for ventilation vents or process vent ofII31, 1133, i tritium, and from all particulate-form radionuclides with half-lives greater than 8 days,in Curies 3.17 E-08 = the inverse of the 6 umber of seconds in a year
VIRGINIA ' VPAP-2103 / POWER - REVISION 7 - PAGE 36 OF 156 i 6.3.5 Gaseous Radweste Treatment - - Historical data pertaining to the volumes and radioactive concentrations of gaseous . effluents released in connectibn with specific Station functions, such as containment purges, shall be used to calculate projected doses, as. appropriate. 1
- a. Requirement , , _ , , ,_
~
' l. The Gaseous Radwaste Treatment System and the Ventilation Exhaust ,
1 Treatment System shall be used to reduce radioactive material in gaseous waste
- before its discharge, when projected gaseous effluent air doses due to gaseous
- effluent releases, from each unit to areas at and beyond the site boundary, would _
exceed 0.2 mrad for gamma radNtion'and 0.4Nfor beia radiation, averaged
- l. ~. u = .t .:p .
4 over 31 days. (North Anna) - i l 2. Appropriate portions of the Gaseous Radwaste Treatment System shall be used I to reduce radioactive materials in gaseous waste before its discharge, when the j projected gaseous effluent air doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceed 0.2 mrad for gamma
- radiation and 0.4 mrad for beta radiation, averaged over 31 days. (Surry)
. 3. The Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste before its discharge, when the projected doses due to j gaseous effluent releases, from each unit to areas at and beyond the site j boundary, would exceed 0.3 mrem to the critical organ, averaged over 31 days.
i
- 4. Doses due to gaseous releases from the site shall be projected at least once l
per 31 days, based on the calculations in 6.3.5.c., and 6.3.5.d. ) b. Action j If gaseous waste that exceeds the limits in 6.3.5.a. is discharged without treatment, l prepare and submit to the NRC within 30 days, a special report in accordance with j VPAP-2802, Notifications and Reports, that includes: ! I
- l. - An explanation why gaseous radwaste was being discharged without treatment, l
- identification of any inoperable equipment or subsystems, and the reason for the !
inoperability. ) 2. Actions taken to restore the inoperable equipment to operable status.
; 3. Summary description of actions taken to prevent recurrence.
< 1
l l l L VIRGINIA VPAP-2103
. . POWER REVISION 7 ;
PAGE 37 OF 156 l 6.3.5 Gaseous Radwaste Treatment (continued)
. c. Pmjected Gamma Dose
- 1. Determine D ,g the.'31-day gamma air dose for the previous 31-day period, -
per Equation (18). ., .
- 2. Estimate R ,g the ratio of the estimated volume of gaseous effluent in the current 31-day period to the volume released during the previous 31-day period.
- 3. Estimate F ,sthe ratio of the estimated noble gas effluent activity in the current 31-day period to the noble gas effluent activity during the previous 31-day period (pCi/ml).
- 4. Determine PD g, the projected 31-day gamma air dose.
PD = DE (Rg x FS.) (22) s !
- d. Projected Beta Dose
]
- 1. Determine D ,bthe 31-day beta air dose in the previous 31 days, l
per Equation (19). I i
. 2. Estimate R gand F as g in 6.3.5.c.2. and 6.3.5.c.3. i
- 3. Determine PD ,b the projected 31-day beta air dose.
PD b = Db(R, x F8 ) (23) l
- e. Projected Maximum Exposed Member of the Public Dose 1
- 1. Determine Dmax, the 31-day maximum exposed member of the public dose in the previous 31-day period, per Equation (20) or Equation (21), where Dr =
Dman. \ l
- 2. Estimate F , i the ratio of the estimated activity from 1131, 1133, radioactive materials in particulate form with half-lives greater than 8 days, and tritium in the current 31-day period to the activity of 1131, 1133, radioactive materials in particulate form with half-lives greater than 8 days, and tritium in the previous 31-day period (pCi/ml).
I i i i
- ___ --_ i
VIRGINIA VPAP-2103 - POWER REVISION 7 - PAGE 38 OF 156
- 3. Determine PDmax, the projected 31-day maximum exposed member of the
, public dose.
- >l PD,,, = D,(R, x F -) g (24) 6.4 Radioactive Liquid and Gaseous Release Permits _,,
. RP shall maintain procedures for Liquid and Gaseous Release Permits to ensure effluent dose limits are not exceeded when making releases.
6.4.I Liquid Waste Batch Release Permits' Operations shall obtain RP authorization before initiating batch releases of radioactive liquids. Examples of batch releases include:
- a. Surry Batch Releases -
Release of contents from the following tanks / sumps other than transfers to the Surry Radwaste Facility shall have a Liquid Waste Batch Release Permit before the discharge:
. Boron Recovery Test Tank (BR'IT)
. . Low 1.evel Waste Drain Tank (LLWDT) .
. High level Waste Drain Tank (HLWDT)
. Liquid Waste Test Tank (LWTT)
. Contaminated Drain Tank (CDT)
. Laundry Drain Surge Tank (LDST)
. Turbine Building Sumps when RP determines that source activity requires placing pumps in manual mode
. Condensate Polishing Building Sumps when RP determines the presence of contamination from primary-to-secondary. leakage '
VIRGINIA VPAP-2103 ' POWER
. REVISION 7 PAGE 39 OF 156 l
l i 6.4.1 Liquid Waste Batch Release Permits (continued)
, b. North Anna Batch Releases
+l .,., ,
NOTE: If the clarifier is in service, releases from tanks processed through the clarifier are l considered continuous releases. l 'A Batch Release Permit is required for a release from any tanks / sumps which ! contain (or potentially contain) radioactive liquid. Tanks / sumps-include: i -,
.BRTT l . LLWDT
.HLWDT
. Turbine Building Sumps when secondary coolant activity exceeds 1.0 E-5 pCi/ml
.CDT 6.4.2 Continuous Release Permit j Operations shall obtain RP authorization before initiating continuous releases of radioactiveliquids.
- a. Surry Continuous Releases -
A Continuous release permit is required at Surry for: i
. Steam generator blowdown
. Component Cooling Water (CCW) heat exchanger to service water leakage, if applicable
. Turbine Building sumps and/or subsurface drains if source activity concentrations are sufficiently low to allow continuous release .
- b. North Anna Continuous Releases ,.
A Continuous Release Permit is required at North Anna for:
. Clarifier, unless being bypassed
. Steam generator blowdown when clarifier is bypassed
. Containment mat sumps and service water reservoir when clarifier is bypassed 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit Operations shall obtain RP authorization before initiating WGDT releases.
- 1. .-
# VIRGIN 1A VPAP-2103 } POWER REVISION 7 -
PAGE 40 OF 156 6.4.4 Reactor Containment Release Permits ~ Operations shall obtain authorization fmm RP before initiating containment purges or containment hogging. Reactor Containment Release Permits shall be valid from start of purge / hog until: -
. Routine termination
. Terminated for cause by RP
. Receipt of Radiation Monitoring System (RMS) Containment Gas Monitor high alarm 6.4.5 Miscellaneous Gaseous Release Permit Operations shall obtain RP authorization before initiating releases of noble gases that I
may not be accounted for by routine sampling, or any planned release not being routed through the Process Vent or Ventilation Vents (e.g., steam driven auxiliary feedwater pump testing if primary to secondary leakage exists). 6.4.6 Radioactive Liquid and Gaseous Release Controls "'
- a. Operations shall notify RP of pending releases and request RP to initiate the appropriate release pennit. Operations shall provide the necessary information to .!
complete the required release permit.
- b. A representative sample shall be obtained of the source to be released. ;
- 1. Operations shall provide RP with liquid samples and sample information (e.g.,
time of sample) for samples obtained outside the Primary Sample Room, except Clarifier Proportional Tank and Clarifier Grab Samples at North Anna.
- 2. Chemistry shall provide RP with liquid samples and sample information for samples obtained from inside the Primary Sample Room.
- 3. RP shall obtain gaseous samples.
- c. RP shall perform required sample analyses.
- d. RP shall calculate and record the following information on a release permit:
. Maximum authorized release rate
. Maximum authorized release rate in percentage of limits specified by the ODCM Applicable conditions or controls pertaining to the release
- i
. - _ _ _ __ _~ _ _ . _ _ _ _ _ __._ _ . _
~.
VIRGINIA I
' VPAP-2103 1 .. POWER REVISION 7 PAGE 41 OF 156 )
l 6.4.6 Radioactive Liquid and Gaseous Release Controls (continued) l
- e. RP shall notify the Shift Supervisor ifit is detennined that a release may not be
' ~
within the effluent do'se limits. l
- f. Upon receipt of a release permit from RP, Operations shall: .
I
,1. Verify the correct source is authorized for release.
- 2. Note maximum authorized release rate. .
- 3. Note percent of Technical Specification limits the release represents.
- 4. Note and ensure compliance with any indicated controls or conditions applicable to the release.
- g. When commencing release, Operations shall provide RP with required information. l As appropriate, required information shall include:
. Date and time release was started
. Starting tank / sump level l Beginning pressure Release flow rate
~
. Dilution water flow rate
- h. Upon terminating the release, Operations shall return the permit to RP and provide information necessary for completion of permit. As appropriate, required information shallinclude:
. Date and time release was stopped
. Tank / sump ending level
- Release flow rate just prior to termination
. Ending pressure ,
. Volume released 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 6.5.1 Requirement The annual (calendar year) dose or dose commitment to a real individual due to releases of radioactivity and radiation from uranium fuel cycle sources shall not exceed 25 mrem to the total body or the critical organ (except the thyroid, which shall not exceed 75 mrem).
. - . .._. .. .- =. - - - . - - . - - . . - - . . . . . - - . _ . - - - - . - . . .
VIRGINIA VPAP-2103 ,,' POWER REVISION 7 - PAGE 42 OF 156 a 6.5.2 Action
- a. If the calculated doses from release of radioactive materials in liquid or gaseous ,
effluents exceed twice theilimits in 6.2.3.a.,6.3.3.a., or 6.3.4.a., calculate - (including direct rariintion contribution from the units and from outside storage - tanks) whether limits in 6.5.1 have been exceeded.
- b. If tiie limits in 6.5.1 have been exceeded, prepare and submit to the NRC within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that defines the corrective action to be taken to reduce subsequent releases and to prevent recurrence, and includes a schedule for achieving conformance with the limits. Special reports, as defined in 10 CFR 20.2203(a)(4), shall include:
- 1. An analysis that estimates the radiation exposure (dose) to a real individual from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases covered by the report.
1
- 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 6.5.1, and if the release condition that violates 40 CFR 190 has not already been corrected, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report in c~isidered a timely request, and a variance is granted until staff action u; tWequest is complete.
e e
VIRGINIA VPAP-2103
, POWER REVISION 7 PAGE 43 OF 156 6.6 Radiological Environmental Monitoring 6.6L1 Monitoring Program
- a. Requirement <
. 1. 'Ihe Radiological Environmental Monitoring Program shall be conducted as - - specified in Attachments 20 or 21, Radiological Environmental Monitoring , Program. .
- 2. Samples shall be collected from specific locations specified in Attachment 22 or 23, Environmental Sample Locations. [ Commitment 3.2.2]
- 3. Samples shall be analyzed in.accordance with:
- Attachment 20 or 21 requirements
. Detection capabilities required by Attachment 24 or 25, Detection Capabilities for Environmental Sample Analysis Guidance of the Radiological Assessment Branch' Technical Position on Environmental Monitoring dated November,1979, Revision No. I
- b. Action
- 1. If the Radiological Environmental Monitoring Program is not being conducted as required in 6.6.1.a., repon the situation in accordance with VPAP-2802, -
Notifications and Repons, by preparing and submitting to the NRC, in the Annual Radiological Environmental Operating Repon required by Technical Specification (Surry Technical Specification 6.6.B.2 and North Anna Tech!dcal Specification 6.9.1.8), a description of the reasons for not conducting the program as required, and the plan for precluding recurrence.
- 2. If, when averaged over any calendar quarter, radioactivity exceeds the 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 in accordance with VPAP-2802, Notifications and Repons, that:
. Identifies the causes for exceeding the limits, and
. Defines the corrective actions to be taken to reduce radioactive effluents 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 POWER REVISION 7 . PAGE 44 OF 156 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:
,j . ... .. ......... . ,
concentration (1) concentration (2) repotting level (1) + reporting level (2) + .. 2: 1.0 (25)
- 3. When radionuclides other than th5se listed in Anachments 26 and 27 are detected and are the result of plant effluents, the reh shall be submitted if the
^
potential annual dose to a member of the public is echual to or greater than the calendar year limits of 6.2.3,6.3.3,~and 6.3.4lThe ieport is not' required if the measured level of radioactivity M not the result of plant effluents; however, in such an event, report and describe the condition in the Annual Radiological
^
Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.
- 4. If milk or fresh leafy vegetable samples are unavailable from one or more of the sample locations required by Attachment 20 or 21, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Identify - -
the cause of the unavailability of samples and identify the new locations for obtaining replacement samples in the next Annual Radioactive Effluent Release , Report in accordance with VPAP-2802, Notifications and Reports. Include in the repon a revised figure and table for the ODCM to reflect the new locations. p m --,e.
1 . VIRGINIA VPAP-2103 - ., POWER . REVISION 7 PAGE 45 OF 156 6.6.2 Land Use Census
- a. Requirement ;
A land use census shAll be conducted and shallidentify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the following:
. Nearest milk animal - - - - - --
l 1
. ~. Nearest residence '
. Nearest garden greater than 50 m2 (500 ft2) that produces broad leaf vegetation 1.- The land use census shalibe conducted during the growing season, at least once per 12 months, using methods that will provide the best results (e.g., door-to-door survey, aerial survey, local agriculture authorities). Land use census results shall be included in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.
- 2. In lieu of the gattien census, road leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of - I two different direction sectors with the highest predicted ground deposition (D/Qs). Specifications for broad leaf vegetation sampling in Attachment 20 or
. 21 shall be followed, including analysis of control samples.
- b. Action
- 1. If a land use census identifies locations that yield a calculated dose or dose commitment greater than the values currently being calculated in 6.3.4.a.2, identify the new locations in the next Annual Radioactive Effluent Release .
Report in accordance with VPAP-2802, Notifications and Reports.
- 2. If a land use census identifies locations that yield a calculated dose or dose commitment (via the same exposure pathway) 20 percent (Surry) or 25 percent (North Anna) greater than at a location from which samples are currently being obtained, add the new locations to the Radiological Environmental Monitoring Program within 30 days. Sampling locations, excluding the control station location, that have the lowest calculated dose or dose commitments (via the same exposure pathway) may be deleted from the monitoring program. Identify new locations in the next Annual Radioactive Effluent Release Report and include in the report revised figures and tables reflecting the new locations in accordance with VPAP-2802, Notifications and Reports. [ Commitment 3.2.4]
. . VIRGINIA VPAP-2103 d - POWER REVISION 7 - PAGE 46 OF 156 6.63 Interlaboratory Comparison Program
- a. Requirement Radioactive materials (which contain nuclides produced at the Stations), supplied as part of an Interlaboratory Comparison Program that has been approved by the ,
. NRC, shall be analyzed.
b; Act' ion
- 1. Analyses shall be performed as part of the Environmental Protection Agency's Environmental Radioactivity laboratory Intercomparison Studies (Cross Check) Program and include: ,
Program Cross-Check of Milk 1131, Gamma, K, Srs9 and SrN Water Gross Beta, Gamma,1 133,H3 (Tritium),Sr89 and Sr# (blind-any combinations of above
.... . yadionuclides} _
Air Filter Gross Beta, Gamma, Sr#
~
- 2. If analyses are not performed as required by 6.63.b., report in the Annual Radiological Environmental Operating Report in accordaace with VPAP-2802, Notifications and Reports, the corrective actions taken to prevent recurrence.
w
- 1 VIRGINIA VPAP-2103
. . POWER REVISION 7 PAGE 47 OF 156 6.6.3 Interlaboratory Comparison Program (continued)
, c. Methodology and Results
- 1. Methodology and'results of the cross-check program shall be maintained in the contractor-supplied Nuclear Reactor Environmental Radiation Monitoring )
Quality Control Manual, IWL-0032-361. l
~
~2. Results shall be reported in the Annual Radiological Environmental Monitoring Repon in accordance with VFAP-2802, Notifications and Reports.
6.7 Reporting Requirements , ! i 6.7.1 Annual Radiological Environmental Operating Report ! Routine Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year. A single submittal may be made for the Station. Radiological Environmental Operating Reports shallinclude:
- a. Summaries, interpretations, and annlysis of trends of results of radiological environmental surveillance activities for the repon period, including:
. A comparison (as appropriate) with preoperational studies, operational controls.
and previous environmental surveillance reports - An assessment of the observed irapacts of the plant operation on the environment
. Results ofland use census per 6.6.2
- b. Results of analysis of radiological environmental samples and of environmental radiation measurements taken per 6.6.1, Monitoring Program. Results shall be summarized and tabulated in the format of the table in the Radiological Assessment Branch Technical Position on Environmental Monitoring.
- 1. If some individual results are not available for inclusion with the repon, the repon shall be submitted, noting and explaining reasons for missing results.
- 2. Missing data shall be submitted in a supplementary repon as soon as possible.
- c. A summary description of the radiological environmental monitoring 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; n second shall include more distant stations.
l J
1 - l N VIRGINIA VPAP-2103 T POWER REVISION 7 PAGE 48 OF 156 i
- e. Results of Station p ikij,. tion in theinterlaboratory Comparison Pmgram,
, per 6.6.3.
- f. DiscussioAof deviation ^s fro'rE.he Sta' tion's'elivir'orhntal sampling schedule per Attachment 20 or 21.
- g. Discussion of analyses in which the lower limit of detection (LLD) required by ,.
~ ' Attachment 24 or 25 was not achievable?'6 : "i H v 7 -
, ..~ . . . - - , . . . . .
6.7.2 Annual Radioactive Emment' Release Report
- a. Requirement c' '
Radioactive Effluent Release Reports covering operation of the units during the previous 12 months of operation shall be submitted before May 1 of each year. A
~
single submittal may be made for the Station and should combine those sections that are common to both units. Radioactive Emuent Release Reports shall include:
\
l
- 1. A summary of quantities of radioactive liquid and gaseous effluents and solid 1
+
waste released. Data shall be summarized on a quarterly basis following the f format of Regulatory Guide 1.21, Appaamw B. t l
- 2. An assessment of radiation doses to the maximum exposed members of the ,
public due to the radioactive liquid and gaseous emuents released from the j
. Station during the previous calendar year. This assessment shall be in 1 accordance with 6.7.2.b.
- 3. A lin and description of unplanned releases from the site to unrestricted areas, during the reporting period, which meet the following criteria:
. Unplanned releases that exceeded the limits in 6.2.1 and 6.3.1
. Unplanned releases which require a Deviation Report and involve the l discharge of contents of the wrong Waste Gas Decay Tank or the wrong liquid radwaste release tank
. Unplanned releases from large leaks due to unexpected valve or pipe failures l that result in a quantity of release such that a 10 CFR 50.72, immediate Notification Requirements for Operating Nuclear Power Reactors or 10 CFR 50.73, Licensee Event Report System, neport is required
. Unplanned releases as determined by Radiation Protection Supervision, l which may or may not require a Deviation Report 4
~.
. VIRGINIA VPAP-2103
. . POWER _ REVISION 7 PAGE 49 OF 156 i 6.7.2 Annual Radioactive Emuent Release Report (continued) l
, 4. Major changes to radioactive liquid, gaseous, and solid waste treatment systems during the reportihg period. .
- 5. Changes to VPAP-2103, Offsite Dose Calculation Manual (see 6.7.4).
- 6. A listing of new locations for dose calculations or environmental monitoring ,
identified by the land use census (see 6.6.2).
- b. Dose Amnemament
- 1. Radiation dose to individuals due to radioactive liquid and gaseous effluents from the Station during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109.
Population doses shall not be included in dose assessments.
- 2. The dose to the maximum exposed member of the public due to radioactive
~ ~
liquid and gaseous effluents from the Station si1all be incorporated with the dose assessment performed above. If the dose to the maximum exposed member of the public exceeds twice the limits of 6.2.3.a.1,6.2.3.a.2,6.3.3.a.1, or 6.3.4.a.1, the dose assessment shall include the contribution from direct radiation. NOTE: NUREG-0543 states: "There is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard,40 CFR Part 190."
- 3. Meteorological conditions dudng the previous calendar year or historical annual average atmospheric dispersion conditions shall be used to determine gaseous pathway doses.
6.7.3 Annual Meteorological Data
- a. Meteorological data collected during the previous year shall be in the form ofjoint frequency distributions of wind speed, wind direction, and atmospheric stability.
- b. Meteorological data shall be retained in a file on site and shall be made available to NRC upon request.
. __ . ~ . _..
L .- w VIRGINIA VPAP-2103 i- POWER REVISION 7 j ' PAGE 50 OF 156 1 4 6.7.4 Changes to the ODCM Changes to the ODCM shall be: , el , i a. Reviewed and approved by SNSOC and the Station Manager before > implementation.
- b. Documented. Records of reviews shall be retained'as Station records.
Documentation shallinclude:
- 1. Sufficient information to support changes, together with appropriate analyses or evaluationsjustifying changes. t x
- 2. A determination that a change will not adversely impact the accuracy or reliability of effluent doses or schint calculations, and will maintain the level .
of radioactive effluent control required by: - 10 CFR 20 Subpart D 40 CFR 190 10 CFR 50.36a _. 10 CFR 50, Appendix I
- c. Submitted to NRC in the form of a complete, legible copy of the entire ODCM as a pan of, or concurrent with the Annual Radioactive Effluent Release Repon for the period of the 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.
[ Commitment 3.2.1)
- e. Submitted to NRC in accordance with VPAP-2802, Notifications and Reports.
l
l VIRGINIA l VPAP-2103 1
. POWER REVISION 7 '
I PAGE 51 OF 156 7.0 RECORDS l 7.1 The following individual and packaged documents and copies of any related correspondence l completed as a result of the periodnance or implementation of this procedure are records. They I shall be submitted to Records Management in accordance with VPAP-1701, Records l 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, , 1 7.1.1 Individual Records !
. None i 7.1.2 Record Packages i
. Records of changes to the ODCM in accordance with 6.7.4
. Records of meteorological data in accordance with 6.7.3 I l . Records of sampling and analyses i
. Records of radioactive materials and other effluents released to the environment
. Records of preventive maintenance, surveillances, and calibrations 7.2 The following documents completed as a result of the implementation of this procedure are not records and are not required to be transmitted to Records Management.
l None l I l l : t I a f l i
- 1. _.
I
. VIRGINIA VPAP-2103 POWER REVISION 7 -
PAGE 52 OF 156 G: h,e
+- .
32[' _lu !, , 24;t *
- .a f
.i l l < +
' nate.: 3r Intentionally Blank 0
4*
VIRGINIA VPAP-2103 '. POWER REVISION 7 1 i PAGE 53 OF 156 l I ATTACHMENT 1 (Page1of1) Surry Radioactive Liquid Emuent Monitoring Instrumentation - Instrument Minimum. Action 4 Operable Channels
- 1. GROSS RADIOACTIVITi MONITORS PROVIDING ALARM AND AUTOMATIC TERMIN ATION OF RELEASE (a) Radwaste Facility Liquid EPluent Line RM-RRM-131
} }
- 2. GROSS BETA OR GAMMA RADIOACTIVITY MONilDRS PROVIDING ALARM BUT NOT PROVIDING AUTDMATIC TERMINATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1 SW RM 120 2 2 Unit 2: 2-SW RM-220 (b) Component Cooling Service Water Effluent Line 1-SW RM 107A 1-SW-RM-107B 4 2
~
1 SW-RM-107C 1 SW-RM-107D
- 3. FLOW RATE MEASUREMENT DEVICES Radwaste Facility Liquid Effluent Line Instrument Loop RLW-153 1 3 ACTION 1: If the number of operable channels is less than required, effluent releases shall be suspended.
ACTION 2: If the number of operable channels is less than required, effluent releases via this pathway may continue provided that, at least once per 12 hours, grab samples are collected and analyzed for principal gamma emitters, as defined in Attachment 8, Snrry Radioactive Liquid Waste Sampling and Analysis Program. ACTION 3: If the number of operable channels is less than required, effluent releases via this pathway shall be suspended.
VIRGINIA VPAP-2103
- POWER REVISION 7 -
PAGE 54 OF 156 I i l I
, i
- s. w ,u ,
r.o .c e
.uA:a v. au u.nuus cc=.:m . x ..u...
7 Intentionally Blank 9 0 4 4 to w
VIRGINIA VPAP-2103 POWER ._ REVISION 7 PAGE 55 OF 156 ATTACHMENT 2 (Page 1 of 2) j
' North Anna Radioactive Liquid Emment Monitoring Instrumentation ,
Minimum ,
^
. Instrument Operable Action '
Channels
- 1. Liquid Radwaste Emuent (a) 1-RM-LW 111 LiquidRadwasteEmuentMonitor 1 1 (b) 1 LW FT 104, Liquid Radwaste Emuent Total Flow Measuring 9,y;c, - i . . . 2 '-
(c) 1-LW-SOV 121 Clarifier Emuent Line Cortinuous Composite Sampler and SamplerFlow Monitor i g (d) 1-LW-TK-20, Liquid Waste Emuent Sample Vessel 1 1 (e) 1-LW-1130, Liquid Waste Emuent Proportional Sample Valve 1 1 (f) 1-RM-SW 108. Service Water Emuent Monitor 1 1 l (g) 1 RM-SW 130, Unit 1 Circulating Water System Emuent Linc Monitor } 4 (h) 2-RM SW-230, Unit 2 Circulating Water System Emuent Line Monitor 1 4 i
- 2. Tank Level Indicating Devices (Note 1)
(a) Refueling Water Storage Tanks Unit i 1-OS-LT 100A 1-QS LT-100B 1 3 1-OS-LT-100C l 1-OS-LT 100D Unit 2 2-QS-LT-200A 1 3 2-QS-LT-200B 2-OS-LT 200C 2-OS-LT 200D (b) CasingCoolingStorageTanks Unit I l-RS-LT 103A 1-RS-LT-103B - 1 3 Unit 2 2-RS-LT 203A - 2-RS-LT-203B 1 3 (c) PG Water Storage Tanks (Note 2) 1 BR LT-116A(1-PG-TK 1 A) 1 3 1-BR-LT-116B (1-PG-TK 1B) 1 3 (d) Boron Recovery Test Tanks (Note 2) 1 BR-LT 112A(1 BR-TK-2A) 1 3
' l-BR-LT-112B (1 BR-TK-2B) 1 3 1
i VIRGINIA VPAP-2103 POWER REVISION 7 -
- PAGE 56 OF 156 ATTACHMENT 2 (Page 2 of 2)
North Anna Radioactive Liquid Emuent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases via this - pathway may continue if, at least once within 12 hours, grab samples are collected and aiuilyzed for gross radioactivity (beta and gamma) at an LLD of at least lx10-7 pCi/g I or an isotopic radioactivity at an LLD of at least 5x10-7 Ci/g. ACTION 2: If the number of operable channels is less than required, effluent release's via this pathway may continue if the flow rate is estimated at least once per 4 hours during actual releases. Design capacity performance curves generated in situ may be used to estimate flow. I ACTION 3: If the number of operable channels is less than required, liquid additions to this tank may continue if the tank liquid levelis estimated during allliquid additions to the tank. ACTION 4: If the number of operable channels is less than required, make repairs as soon as possible. Grab samples cannot be obtained via this pathway. NOTE 1: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents, and do not have overflows and surrounding area drains connected to the liquid radwaste treatment system. NOTE 2: This is a shared system between Unit I and Unit 2. . t k
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VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 57 OF 156 ATTACHMENT 3 (Page 1 of 1) Surry Ra'dioactive Liquid Emuent Monitoring Instrumentation Surveillance Requirements Channel Description Channel Source Channel Channel Check Check . Calibration Functional
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Test
- 1. GROSS RADIOACTIVITY MONITORS ~- -
PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE -- (a) Radwaste Facility Liquid Effluent Line RM-RRM 131 D P R Q
- 2. GROSS BETA OR GAMMA RADIOACTIV-ITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUIDMATIC 'IERMI-NATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1 SW-RM-120 D M R Q Unit 2: 2-SW-RM-220 .
(b) Component Cooling Service Water Efau-ent Line , 1-SW-RM-107A D M R 1-SW-RM-107B Q l-SW-RM-107C 1-SW RM-107D , 3. FLOW RATE MEASUREMENT DEVICES l Radwaste Facility Liquid Effluent Line Instrument Loop RLW 153 DR N/A R N/A l l I l
4 VIRGMIA VPAP-2103
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- POWER VPAP-2103 REVISION 7 PAGE 59 OF 156 ATTACHMENT 4 (Page 1 of 2)
North Anna Radioactive LiquidEmuent Monitoring Instrumentation Surveillance 4 Requirements j Channel Description Channel Source Channel Channel Check Check Calibration Functional
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Test 1, Liquid Radwaste Emuent (a) 1-RM-LW-111,LiquidRadwasteEffluent D D. Monitor R Q(NOTE I) ] (b) 1-LW-FT-104. Liquid Radwaste Effluent TotalFlow Measuring Device D(NCTIE 3) N/A- R Q (c) 1-LW SOV 121, Clarifier Effluent Line N/A N/A R N/A Continuous Composite Sampler and SamplerFlow Monitor (d) 1-LW TK-20, Liquid Waste Effluent Sample Vessel D(NOTE 9) N/A N/A N/A (e) 1-LW-1130, Liquid Waste Effluent ProportionalSample Valve D(NOTE 9) N/A N/A N/A (f) 1 RM SW 108, Service Water System D M R Effluent Monitor Q(NOTE 2) (g) 1-RM-SW 130, Unit 1 Circulating Water D M System Effluent Line Monitor R Q(NOTE 2) (h) 2-RM-SW 230, Unit 2 Circulating Water D M System Effluent Line Monitor R Q (NO1E 2)
- 2. Tank Level Indicating Device (NOTE 6)
(a) Refueling Water Storage Tanks Unit I l-QS-LT-100A N/A R D (NOTE 4) Q (NOTE 7) 1-QS LT-100B l-QS-LT-100C 1-QS-LT 100D Unit 2 2-QS-LT-200A N/A R D(NOTE 4) O(NOTE 7) 2-QS-LT-200B ~ 2-QS-LT-200C 2-QS LT-200D (b) Casing Cooling Storage Tanks Unit I l RS-LT-103A D (NOTE 4) N/A R 1 RS-LT-103B Q(NO1E 7) Unit 2 2 RS-LT-203A R D(NOTE 4) N/A Q(NOTE 7) 2-RS-LT-203B (c) PO Water Storage Tanks (NOTE 5) 1 BR-LT-116A (1-PG-TK-1A) D(NOTE 4) N/A R Q(NOTE 8) 1-BR-LT 116B (1 PG TK 1B) D (NOTE 4) N/A R Q(NOTE 8) (d) Boron Recovery Test Tanks (NOTE 5) 1-BR-LT-112A (1 BR TK-2A) D(NOTE 4) N/A R Q(NOTE 8) 1-BR-LT 112B (1 BR-TK-2B) D(NOTE 4) N/A R Q(NOTE 8) l
1 U VIRGINIA VPAP-2103 1 M~ POWER REVISION 7 .- PAGE 60 OF 156 ; i A'ITACHMENT 4 -~ (Page 2 of 2) North Anna Radioactive Liquid Emuent Monitoring Instrumentation SurveiHance Requirements u :a ..:etc . - NOTE 1: The Channel Functional Test shall demonstrate:
- a. Atitomatic isolation of this pathway and Control Room alarm annunciation occur if the instrument indicates measured levels ab6v'e alaim/ trip setpoinE
- b. Alarm annunciation occurs if the instrument controls are not se:in " operate" mode.
NOTE 2: The Channel Functional Test shall demonstrate that Control Room alarm annunciation
- > ' ' ;o occurs if any of the following conditions exists: i*t
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Instrument controls not set in " operate" mode.
NOTE 3: Channel Check shall consist of verifying indication of flow during periods of release. Channel Check shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. , , _
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NOTE 4: During liquid additions to the tank, verify indication of level change. NOTE 5: This is a shared system between Unit I and Unit 2. NOTE 6: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have overflows and surroun' ding area drains connected to the liquid radwaste treatment system. NOTE 7: The Channel Functional Test shall demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur if instrument indicates measured levels outside the alarm / trip setpoint. Demonstration of automatic isolation may consist of verifying the appropriate signal is generated. Valves need not be operated for this test. NOTE 8: The Channel Functional Test shall demonstrate that Control Room alarm annunciation occurs if the instrument indicates measured levels are outside alarm setpoint. NOTE 9: Channel Check shall consist of verifying that proportional flow exceeds 0.5 mis / gallon.
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! VIRGINIA VPAP-2103 i '~, . . POWER REVISION 7 l PAGE 61 OF 156 ATTACHMENT 5 (Page1of1) l
' Liquid Ingestion PathwayDose Factors for Surry Station Units 1 and 2 i
Total Body Ai Thyroid Ag GI-LLI Radionuclide I mrem /hr mrem /hr mrem /hr l l ncumi ncumi ucune i H-3 2.82E-01 2.82E-01 2.82E-01 I Na-24 4.57E-01 4.57E-01 4.57E-01 Cr 51 5.58E+00 334E-01 1.40E+03 M v54 135E+03 - 2.16E404 Fe-55 8.23E+03 - 2.03E+04 Fe-59 7.27E404 - 6.32E+05 Co-58 135E+03 - 1.22E+04 Co-60 3.82E+03 - 3.25E+04 Zn-65 2.32E+05 - 3.23E+05 I Rb-86 2.91E+02 - 1.23E+02 Sr-89 1.43E+02 - 8.00E+02 Sr-90 3.01E+04 - 3.55E+03 Y-91 237E+00 - 4.89E+04 Zr-95 3.46E+00 - 1.62E+04 Zr-97 8.13E-02 - 5.51E+04 Nb-95 134E+02 - 1.51E+06
. Mo-99 2.43E+01 -
2.96E+02 . Ru-103 4.60E+01 - 1.25E+04 Ru-106 2.01E+02 - 1.03E+05 Ag 110m 8.60E+02 - 5.97E+05 Sb-124 1.09E+02 6.70E-01 7.84E+03 Sb-125 4.20E+01 1.79E-01 1.94E+03 Te-125m 2.91E+01 6.52E+01 8.66E+02 Te-127m 6.68E+01 1.40E+02 1.84E+03 Te-129m 1.47E+02 3.20E+02 4.69E+03 Te-131m 5.71E+01 1.08E+02 6.80E+03 l Te-132 1.24E+02 1.46E+02 6.24E+03 l-131 1.79E+02 1.02E+05 8.23E+01 1 132 9.%E+00 9.%E+02 5.35E+00 l-133 3.95E+01 1.90E+04 1.16E+02 l 134 5.40E+00 2.62E+02 132E-02 l l-135 2.24E+01 4.01E+03 6.87E+0! Cs-134 1.33E+04 - 2.85E+02 Cs-136 2.04E+03 - 3.21E+02 Cs-137 7.85E+03 -
?-3?E+02 Cs-138 5.94E+00 -
5.12E-05 Ba-140 1.08E+02 - 338E+03 1.a-140 2.10E-01 - 5.83E+04 Cc-141 2.63E-01 - RRAE+03 Cc-143 4.94E-02 - 1.67E+04 , Cc 144 9.59E+00 - 6.04E+04 Np-239 1.91E-03 - 7.1IE+02 l l
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VIRGINIA VPAP-2103
.. POWER REVISION 7 PAGE 63 OF 156 A'ITACHMENT 6 (Page 1 of 5)
North Anna Liquid Ingestion Pathway Dose Factor CalculationUnits 1 and 2 1.0 Equation (6) D = t F[f;C;A;~ (6-1) i where: D = cumulative dose commitment to the total body or critical organ, from the liquid effluents for the period t,in mrem t = period for which Ci and F are averaged for allliquid releases,in hours F = the near field average dilution factor for Ci during any liquid effluent release. Defined as ! the ratio of the average undiluted liquid waste flow 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 nuclides due to recirculation, listed on page 5 of this attachment. "fi"is the - ratio of the total dilution flow over the effective dilution flow Ci = average concentration of radionuclide i, in undiluted liquid effluent during the period t, 4 from any liquid releases,in pCi/ml , A; = the site-related ingestion dose commitment factor to the total body or critical organ of an adult for each identified principal gamma and beta emitter listed on page 5 of this attachment,in mrem /hr per pCi/ml A; = 1.14 EM)5 (730/Dw+ 21 BF;/D,) DF; (6-2) where: 1.14 E+05 = (1 E+06 pCi/ Ci x 1 E+03 ml/kg)/8760 hr/yr, units conversion factor 730 = adult water consumption, kg/yr, from NUREG-0133 l
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- VIRGINIA VPAP-2103 POWER REVISION 7 -
PAGE 64 OF 156 ATTACHMENT 6 (Page 2 of 5) North Anna Liquid Ingestion Pathway Dose Factor CalculationUnits 1 and 2 D, = 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.
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D, includes the dilution contributions from the IAte Anna Dam to Doswell (0.73), the WHTF(CijCc), and IAte Anna (Cg/Q). The potable water mixing ratiois caled=W as: 1/(Cg /CC )(CR /Cg ) 0.73 q Cc/(CR.x0.73 ) (6-3) where Cc, Q and Cn are the resgtive concentrations for the considered nuclide in the discharge channel, WHTF (Lagoon) and the Lake. Calculation is per expressions 11.2-5,11.2-6, and 11.2-8 of the North Anna UFSAR 21 = adult fish consumption rate, kg/yr, from NUREG 0133 BF = the bicaccumulation factor for nuclide i, in fish, pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev.1 Da = dilution factor for the fish pathway, calculated as 1/(Q /Cc) where Q and Ce are the concentrations for the considered nuclide in the discharge channel and the WHTF (Lagoon). Calculation is per Expressions 11.2-5, and 11.2-6 of North Anna's UFSAR DFi = the critical organ dose conversion factor for nuclide i, for adults, in mrem / pCi, from Table E-1I of Regulatory Guide 1.109, Rev.1
VIRGINIA VPAP-2103
. POWER _ REVISION 7 PAGE 65 OF 156 ATTACHMENT 6
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North Anna Liquid Ingestion Pathway Dose Factor Calcuh mUnits 1 and 2 - 2.0 Equation (9) . Equation (6)is simplified for actual dose calculations by introducing: WASTE FLOW WASTE FLOW
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F = CIRC. (WATER) FLOW + WASTE CIRC.FLOW (6-4) FLOW and
- f. = CIRC. FLOW (6-5) 2 EFFECTIVE DIL. FLOW. 1 Effective dilution flow rates for individual nuclides "i" are listed on Attachment 7, Noith Anna Liquid Pathway Dose Commitment Factors for Adults. Then the total released activity (Q) for the considered period and the ith nuclide is written as:
, Q; = t x C; x WASTE FLOW (6-6) ,
and Equation (6) reduces to: A'. D=[Q iEFF. DIL. FLOW. 1 I (6-7) For the long-lived, dose controlling nuclides, the effective dilution flow is essentially the over (dam) flow rate out of the Lake Anna system (i.e., the liquid pathway dose is practically independent from the circulating water flow rate. However, to accurately assess long range average effects of reduced circulating water flow rates during outages or periods oflow lake water temperatures, calculations are based on an average of 7 out of 8 circulating water pumps running at 218,000 gpm = 485.6 cft/sec per pump. l
c VIRGINIA VPAP-2103 d REVISION 7 -~ POWER - PAGE 66 OF 156 A'ITACHMENT 6 (Page 4 of 5) North Anna Liquid Ingestion Pathway Dose Factor CalculationUnits 1 and 2 . NOTE: ne 218,000 gpm flow rate per Circulating Water pump is based on Reference 3.1.21. De choice of seven Circulating Water pumps is considered realistic. Compared to Ods, the NAPS UFSAR, Chapter 11.2 (Reference 3.1.18), contains an extremely conservative consideration based on the minimum flow in accordance with Reference 3.1.21 with only two Orculating Water pumps operating. Even at such a low flow rate, which cannot be sustained during power generation, liquid pathway effluent dose factors increase only slightly for the dose controlling nuclides (i.e., Cs
- 19 percent, Cs l37 15 percent). .
By defining B i= At / EFF. DIL. FLOW 1, the dose calculation is reduced to a two factor formula: D =i [x B[ (6-8)
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Values for Bi (mrem /Ci) and EFF. DIL. FLOW iare listed in Attachment 7. w
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ATTACHMENT 6 (Page 5 of 5) N'orth Anna Liquid Ingestion Pathway Dese Factor CalculationUnits I and 2 . I 1 Individual Dilution Total Body Ag Liver Ag Radienuclide Multiplication Factor stalBag mretn/hr l (f)i pCi/nd pCi/ int i H-3 14.9 6.18E+00 6.18E+00 ! Na-24 1.0 3.71E+01 3.71E+01 l Cr 51 1.7 1.10B+00 - l Mn-54 7.0 8.62E+02 4.52E+03 Fe-55 113 130E+02 5.56E+02 Fe-59 2.2 9A7E+02 2.47E+03 j Co-58 2.8 2A9E+02 1.11E+02 ' Co-60 13 3 8.27E+02 3.75E+02 Zn-65 6.1 3.28E+04 7.25E+04 l Rb-86 1.5 3.53E+04 - 7.59E+04 Sr-89 23 8.70E+02 - Sr-90 15.8 239E405 - Y-91 2.5 3A2E-01 - Zr 95 2.7 2.98E-01 4.41E-01 Zr-97 1.0 1.50E-04 3.27E-04 Nb-95 1.9 1.13E+02 2.10E+02
. Mo-99 1.0 7ASE+00 3.93E+01 -
Ru-103 2.0 4.10E+00 - Ru-106 7.6 2.65E+01 . Ag 110m 6.2 4.94E+00 832E+00 Sb-124 2.6 4.37E+01 ? ME+00 s Sb-125 11A 2A6E+01 1.16E+00 ) Te 125m 2.5 3.23E402 ' 8.73E+02 Te-127m 3.7 7.82E+02 2.29E+03 Te 129m 1.9 1.52E+03 3.58E+03 Te-131m 1.0 1.12E+02 135E+02 Te 132 1.0 5.04E+02 537E+02 1 131 1.2 9.66E+01 1.69E+02 1 132 1.0 1.03E-01 2.95E-01 1133 1.0 . 3A7E+00 1.14E+01 1-134 1.0 2.15E-02 6.00E-02 1-135 1.0 6.58E-01 1.78E+00 Cs 134 103 5.80E+05 7.09E+05 Cs136 13 6.01E+04 835E+04 Cs 137 15.8 3.45E+05 5.26E+05
- Cs-138 1.0 9.18E-01 1.85E+00 Ba-140 13 2.65E+01 5.08E-01 La-140 1.0 4A7E-03 1.69E-02 ;
Ce-141 1.8 2.14E-02 1.89E-01 Ce-143 1.0 135E-04 1.22E+00 Ce-144 6.6 1AIE+00 1.10E+01 i Np 239 1.0 5.13E-04 ! 931E-04
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l VIRGINIA VPAP-2103 POWER REVISION 7 i PAGE 69 OF 156 ' l l ATTACHMENT 7 (Page 1 of 1) North Anna Liquid Pathway Dose Commitment Factors for Adults Bi = A iF i/ CIRC FLOW = (A i/ Effective Dilution Flowi) X 9.81E-3 hr ft3 pCi / sec ml Ci Radionuclide Effective Dilution How B Liver B (cygj,,c) Total (,,,,fBod [i).i (mrem /di) R3 2.28E+02 2.66E-04 2.66E-04 Na-24 339E+03 1.07E 04 1.07E-04 Cr-51 1.99E+03 5.445-06 N/A Mn.54 4.88E+02 1.73E 02 9.08E 02 Fe-55 3.01E+02 4.23E-03 1.81E-02 Fe-59 1.57E+03 5.93E-03 1.55E-02 Co-58 1.20E403 2.04E-03 9.10E 04 Co-60 2.55E+02 3.185-02 1.44E-02 Zn-65 5.60E+02 5.74E-01 1.27E+00 l Rb-86 234E+03 1.48E-01 3.1BE-01 i St-89 1.46E+03 5.84E-03 N/A Sr90 2.16E+02 1.09E+01 N/A Y-91 134E+03 2.50E-06 N/A Zr-95 127E+03 2.30E-06 3.40E-06 Zr.97 339E+03 433E-10 9.46E-10 Nb-95 1.78E+03 6 24E-04 1.16E-03 Mo-99 330E+03 2.22E-05 1.17E-04
. Ru 103 1.68E+03 2.40E-05 N/A -
Ru-106 4.48E+02 5.80E-04 N/A AF 110m 5.52E+02 8.78E-05 1.48E-04 Stul24 132E+03 T Z E-04 1.55E-05 Stw125 2. 98E+02 fl0E-04 3.80E-05 Te-125m 1.35E+03 235E-03 635E-03 Te 127m 9.16E+02 837E-03 2.46E-02 Te 129m 1.82E+03 8.19E-03 1.93E-02 Te.131m 3.38E+03 3.27E-04 3.92E-04 Te-132 3.27E+03 1.51E-03 1.6iE-03 1.I31 2.94E+03 3.22E-04 5.625-04 1132 3.40E+03 2.98E-07 8 51E-07 1 133 339E+03 1.00E-05 3.295-05 1134 3.40E+03 . 6.19E-08 1.73E-07 1135 3.40E+03 1.90E-06 5.15E-06 Cs.134 3.29E+02 1.73E+01 2.llE+01 Cs 136 2.62E+03 2.25E-01 3.12E-01 Cs-137 2.15E+02 1.57E+01 2.40E+01 7 s-138 3.40E403 2.65E-06 534E-06 ha-140 ' 2.65E+03 9.83E-05
~~ 1.88E-06 1.a-140 336E+03 131E-08 4.94E-08 l Cc-141 1.85E+03 1.14E-07 1.00E-06
! Ce-143 337E+03 3.93E 10 ' 3.55E-06 Ce-144 5.14E+02 2.70E-05 2.10E-04 Np-239 332E+03 1.51E-09 2.75E-09 I
VIRGINIA VPAP-2103
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i1- VIRGINIA VPAP-2103 ! . POWER REVISION 7 PAGE 71 OF 156 ; ATTACHMENT 8 (Page 1 of 3) ) Surry Radioactive Liquid Waste Sampling and Analysis Program i Liquid Release - Sampling Minimum Analy- Type of Activity - Type g, ) l Frequency sis Frequency Analysis ( Ci/ml),(Note 1) p p Pnnciple Gamma 5 x 10'7 Emitters (Note 3) (Each Batch) (Each Batch) 1131 1 x 104 Dissolved and l Batch Releases M Entrained Gases 1 x 10-5 B ) (Gamma Emitters) 1 (Note 2) P M Composite H3 1 x 10-5 (Each Batch) (Note 4) Gross Alpha 1 x 10'7 P Q Composite Sr89 and Sr# 5 x 10-8 (Each Batch) (Note 4) Fess 1 x 104 Continuous W Composite e a1G 5 x 10-7 (Note 6) (Note 6) 1131 1 x 10 4 Continuous M Dissolved and Releases Grab Sample Entraind Gases 1 x 10-5 (Gamma Emitters) (Note 5) Continuous M Composite H3 1 x 10-5 (Note 6) (Note 6) Gross Alpha 1 x 10~7 Continuous Q Composite Sr89and St# 5 x 10-8 (Note 6) (Note 6) Fe55 1 x 104
VIRGINIA VPAPo2103 POWER REVISION 7 PAGE 72 OF 156 A'ITACHMENT 8 d (Page 2 of 3) durry Radioactive Liquid Waste Sampling and Analysis Program NOTE 1: For a particular measurement system (which may include radiochemical separation):
~
4.66 s D LLD = _ (8-1) E e V e 2.22E+06
- Y e e-( AAt)
Where: _ ..:. LLD = the "a priori" (before the fact) Lower Limit of Detection (as microcuries per unit mass or volume)(see 4.8) sb = 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) V = the sample size (in units of mass or volume) 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable) A = the radioactive decay constant for the particular radionuclide At = the elapsed time between the midpoint of sample collection and time of counting Typical values of E, V, Y and At should be used in the calculation. The LLD is an "a priori" (before the fact) limit repfesenting the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement. NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Before sampling for analyses, each batch shall be isolated, and appropriate methods will be used to obtain a representative sample for analysis.
. 1 VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 73 OF 156 ATTACHMENT 8 1
(Page 3 of 3) l Surry Radioactive Liquid Waste Sampling and Analysis Program 4 < l NOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn54, p,59, Co ss, Co60, Zn65, Mo", Cs334 , Cs 337 , Ce343, and Celdd his 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 identi6ed and reported. NOTE 4: A composite sample is one in which the quantity of liquid sampled is proportional to the quantity ofliquid waste discharged and for which the method of sampling employed results in a specimen that is representative of the liquids released. 1 NOTE 5: A continuous release is the discharge ofliquid wastes of a non-discrete volume, e.g., from i l 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. l t' 0
.. .. . .. _ . - ~ - .. . .._.- - - ..- -- _. . . .. -P 2;'
VIRGINIA VPAP-2103 ? POWER -- REVISION 7 -- PAGE 74 OF 156 to
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VIRGINIA VPAP-2103 ., POWER REVISION 7 PAGE 75 OF 156 ATTACHMENT 9 (Page 1 of 3)
' North Anna Radioactive Liquid Waste Sarnpling and Analysis Program Liquid Release ~ Sampling Mimmum Analy- Type of Activity Lower Limit of Type - Frequency sis Frequency Analysis Detcction (LLD)
(pCi/ml), (Note 1) P P Prmciple Gamma 5 x 10-7 Emitters (Note 3) (Each Batch) (Each Batch) g131 1 x 104 Batch Releases P M Dissolved and 1 x 10 5 (One Batch /M) Entrained Gases (Gamma Emitters) (Notes 2 and 7) P M Composite H3 1 x 10-5 (Each Batch) (Note 4) Gross Alpha 1 x 10-7 P Q Composite gg9 and Sr" 5 x 10'8 (Each Batch) (Note 4) p,55 1 x 10 4
~
Principal Gamma 5 x 10-7 Emitters (Note 6) Continuous W Composite g131 1 x 10 4 ! Continuous (Note 6) (Note 6) Dissolved and Releases Entrained Gases 1 x 10-5 (Gamma Emitters) : (Note 5) Continuous M Composite 3 i H 1 x 10-5 (Note 6) (Note 6) Gross Alpha 1 x 10'7 Continuous Q Composite Sr89 and Sr* 5 x 10'8 (Note 6) (Note 6) pe55 1 x 104
w w VIRGINIA VPAP-2103 C* POWER REVISION 7 .- t PAGE 76 OF 156 A'ITACHMENT 9 (Page 2 of 3) North Anna Radioactive. Liqui,d Waste Sampling and Analysis Program i . NOTE 1: For a particular measurement system (which may include radiochemical separation):
~
7 ,, . 4.66 s b - ' LLD = (9-1) E
- V e 2.22E+06
- Y = e-(Aat) '
n- - - - u Where: r- -
~
LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above P (as microcuries per unit mass or volume) (see 4.8) !
=
sb 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) V = the sample size (in units of mass or volume) 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable) A = the radioactive decay constant for the particular radionuclide At = the elapsed time between the midpoint of sample collection and time of counting Typical values of E, V, Y and At should be used in the calculation. The LLD is an "a priori"(before the fact) limit repbsenting the capability of a measurement system and not a "posteriori"(after the fact) limit for a particular measurement. NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Before sampling for analyses, each batch shall be isolated, and then thoroughly mixed as the situation permits, to assure representative sampling.
VIRGINIA VPAP-2103 . . POWER REVISION 7 l PAGE 77 OF 156 i ATTACHMENT 9 (Page 3 of 3) l
' North Anna Radioactive IJguid Waste Sampling and Analysis Program -
NOTE 3: The principal gamma emitters for which the LLD speci6catie:i applies exclusively are the . followingradionuclides:Mn54,pg59 CO 5s, cow, Zn4, Mo", Cs334, CsI37, Celdl, and Cel44. This list does not mean that only these nuclides are to be detected and reported. l Other peaks that are measurable and identi6able, at levels exceeding the LLD, together j with the above nuclides, shall also be identi6ed and reported. l I NOTE 4: A composite sample is one in which the quantity ofliquid sampled is proportional to the , quantity ofliquid waste discharged and for which the method of sampling employed results ) in a specimen that is repmsentative of the liquids released. NOTE 5: A continuous release is the discharge ofliquid wastes of a non-discrete 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 I effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent releases. NOTE 7: Whenever the secondary coolant activity exceeds 10-5 Ci/ml, the turbine building sump pumps shall be placed 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 i basis. These samples are analyzed for gross activity or gamma isotopic activity within - 24 hours. i 1 1 1
VIRGINIA VPAP-2103
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- 1 4 VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 79 OF 156 1
ATTACHMENT 10 l (Page 1 of 5) Surry Radioactive Gaseous Waste Sampling and Analysis Program d
- Gaseous Release Sampling Minimum Type of Activity Lower Limit of
- Type- Frequency Analysis Analysis Detection (LLD)' i
- Frequency (pCi/ml),'(Note 1)
{ A. Waste Gas Prior to Release Principal Gamma Storage Tank (Each Tank) I x 10 4 3 Emitters (Note 2) t Prior to Release Principle Gamma 4 Prior to Release 1 x 10 B. Containment Emitters (Note 2) Purge ach P RGE)
,b p (Each PURGE) H3 1 x 104 C. Ventilation Weekly Principle Gamma i' (1) Process Vent (Grab Sample) Y 1 x 10a Emitters (Note 2)
(2) Vent Vent #1 (3) Vent Vent #2 (Note 3) (Note 3) H3 1 x 104 (4)SRF Vent Continuous Weekly (Note 5) I 1 x 1012 , (Note 4) (Charcoal Sample) ,133 1 x 10-10 Continuous Weekly (Note 5) Principal Gamma All Release (Note 4) Particulate Sample Emitter (Note 2) 1 x 10'11 Types as listed C mp s te Gross Alpha 1 x 10-31 (N t 4) Particulate Sample in A, B, and C Quarterly g Composite Sr 89 and Sr" l x 10'11
)
Particulate .. Continuous Noble Gas NobleGasesGross (Note 4)' Monitor Beta and Gamma 1 x 10'6 Weekly Principle Gamma a Weekly Condenser Air Emitters (Note 2) . Grab S ple @ote 3) Ejector H3 9 1 x 104 I l
4 03 VIRGINIA VPAP-2103 3- POWER REVISION 7 PAGE 80 OF 156 ATTACHM5NT 10 (Page 2 of 5)
, Surry Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sampling Minimum Type of Activity Lower Limit of
, Frequency Type Analysis Analysis Detection (11D)
Prequency ( Ci/ml),(Note 1) Ganuna Prior to Release Prior to Release ,' 1 x 104 (Grab Sample) (Each Release) H3 ~1 x 10 4 131 1 1 x 10-11 Continuous Charcoal Sample (Note 4) (Note 6) I333 . 1 x 10'in Containment Continuous Particulate Prmcipal Gamma H@ Pre- (Note 4) Sample (Note 6) Emitter (Note 2) 1 x 10-10 ' surization Composite Continuous PMcMae --Gross-Alpha 1 x 10-10
, Sample (Note 6)
Composite Conn.nuous P d culate S/' and Sr# 1 x 1010
** ) Sample (Note 6) 1
. 3 i VIRGINIA VPAP-2103
- ' POWER REVISION 7 PAGE 81 OF 156 ,
J ATTACHMENT 10 (Page 3 of 5) ;
\'
Surry Radioactive Gaseous Waste Sampling and Analysis Program NOTE 1: For a particular measurement system (which may include radiochemical separation): l 4.66 s ' b ' LLD = (10-1) . E
- V e 2.22E+06
- Y
- e-(Aot) l Where:
i LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above ; (as microcuries per unit mass or volume) (see 4.8). sb = the standard deviation of the background counting rate or of the counting I rate of a blank sample as appropriate (as counts per minute, cpm). ; E = the counting efficiency (as counts per disintegration). V = the sample size (in units of mass or volume). I 2.22E+06 = the number of dikintegrations per minute (dpm) per nucrocune. ' I 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. j The LLD is an "a priori" (before the fact) limif representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.
J
.- I 4 . .; . VIRGINIA VPAP-2103 POWER REVISION 7 -
PAGE 82 OF 156 A*ITACHMENT 10 (Page 4 of 5) Surry Radioactive Gaseous, Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD speci6 cation applies exclusively are the following radionuclides: Kr 87, Kr88,Xel33, Xe133",-Xel33, Xe135", and Xe138 for gaseous ~
~
54 , pe 59 , Co S8 , gg I 'I and Ce emis~sfons and Mn 60, Zn65, ggM, CsI34, CsI37, Ce I " for particulate emissions. This list does not mean that only,these nuclides are to be detected and reported. Other nuclides with half lives greater than 8 days, that are measurable and identifiable at levels exceeding the LLD, together with the above nuclides,'shall also 'be identified and reported. _ .) ~ NOTE 3: Sampling and analysis shall also be performed following shutdown, start-up, and whenever a thermal power change exceeding 15 percent of the rated thermal power occurs within any one-hour period, when: -
--~ -
- a. Analysis shows that the dose equivalent I l3I concentration in the primary coolant has increased more than a factor of 3; and
- b. The noble gas activity monitor shows that effluent activity has increased by more than
~
a factor of 3. .
~
NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the period covered by each dose or dose rate calculation made in accordance with 6.3.1, 6.3.3, and 6.3.4. NOTE 5: Samples shall be changed at least once per seven days and analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least seven days following each shutdown, start-up, or thermal power change exceeding 15 percent of rated thermal power in one hour, and analyses shall be completed within 48 hours of chahging. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if:
- a. Analysis shows that the dose equivalent 1 131 concentration in the primary coolant has increas.d by a factor of 3; and
- b. Noble gas monitor shows that effluent activity has increased more than a factor of 3.
~
VIRGINIA VPAP-2103
. , POWER REVISION 7 i PAGE 83 OF 156 i ATTACHMENT 10 (Page 5 of 5) 1 Surry Radioactive Gaseous Waste Sampling and Analysis Program l l l NOTE 6: To be representative of the quantities and concentrations of radioactive materials in gaseous effluents, composite sampling shall employ appropriate methods that will result in a ;
specinien representative of the effluent release. e
+
Ph 4 4 4 1 4 1 d .I .. 6 0 1 i 4
[ VIRGINIA POWER VPAP-2103 REVISION 7 - PAGE 84 OF 156 1 I Q. ;
.I- .
Intentionally Blank 9 4 e 6
VIRGINIA VPAP-2103
.. POWER REVISION 7 PAGE 85 OF 156 ATTACHMENT 11 (Page 1 of 4) orth Anna Radioactive Gaseous Waste Sampling and Analysis Program a , .*
Gaseous Release Sampling Minimum Type of Activity Lower Limit of Type- Frequency Analysis Analysis Detection (LLD) Frequency (pCi/ml). (Note 1) A. Waste Gas Prior to Release Principal Gamma 4 1 x 10 Storage Tank Grab Sample) (c ) tren @ te 2) Principle Gamma 4 Prior to Release Prior to Release 1 x 10 B. Containment . Emi tters (Note 2) ( hP Purge (Each PURGE) H3 1 x 10-6 Gb C. Ventilation Monthly Principle Gamma
" Y 1 x 10 4 (1) Process vent (Grab Sample) Emitters (Note 2)
(2) Vent Vest A (Notes 3,4, and (Note 3) H3 1 x 104 (3) Vent Vent B 5) Continuous Weekly I l31 1 x 1012 , (Note 4) (Charcoal Sample) g133 1 x 10-10 '[. Continuous Weekly Principal Gamma 1 x 10-31 All Release (Note 4) Particulate Sample Smitter (Note 2) Monthly Co .nuous Types as listed Composite Gross Alpha 1 x 10-11 Particulate Sample in A, B,and C Quarterly Continuous Composite Sr89 and Sr# 1 x 10-13 (Note 4) p ; Continuous Noble Gas - NobleGasesGross 1 x 10 6 (Note 4) Monitor Beta or Gamma Condenser Air Principle Gamma d Weekly Weekly 1 x 10 Ejector / Steam Emitters (Note 7) Generator Grab Sample Blowdown Vent H3 1 x 104 (Note 6) Containment Prmciple Gamma 4 Prior to Release Prior to each 1 x 10 Vacuum Steam Emitters (Note 2) , Ejector (Hogger) (Grab Sample) Release H3 1 x 104 (Note 8) o 6
" VIRGINIA VPAP-2103 i POWER - -
REVISION 7 - l PAGE 86 OF 156 i ATTACHM$NT 11 (Page 2 of 4)
- North Anna Radioactive Gaseons Waste Sampling ami Analysis Program
] NOTE 1: For a particular measurement system (which may iriclude radiochemical separation):~
~_' ..
. 4.66 s b
~
LLD = - (11-1) l E e V e 2.22E+06
- Y e e-(Aat) e.
i : ? l Where: . . _ i.
- LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (as microcuries per unit mass or volume) (see Subsection 4.9)
- =
sb the standard deviation of the background counting rate or of the counting { rate of a blank sample as appropriate (as counts per minute, cpm) i ! E = the counting efficiency (as counts per disintegration) i V = the sample size (in units of mass or volume) i . 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie ) 4 Y = the fractional radiochemical yield (when applicable) i A = the radioactive decay constant for the partichlaHadionuclide i At = the elapsed time between the midpoint of sample collection and time of ] Coun6Dg j
- Typical values of E, V, Y and At should be used in the calculation.
i ' ! The LLD is an "a priori" (before the fact) limit representing the capability of a j measurement system and not as "posteriori" (after the fact) limit for a particular ! measurement i i i
}
d ? i
-^
VIRGINIA VPAP-2103
. POWER REVISION 7 l PAGE 87 OF 156 ATTACHMENT 11 (Page 3 of 4)
' North Anna Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the 87 followingradionuclides:Kr ,Kras,Xel33, Xe133", Xe135, Xel33", and Xe138 for gaseous emissions and Mn 54 , pe 59 , Co ss, Co", Zn 65
, Mo" Csl34, CsI37, Celdl and Ce l44 for particulate emissions. This list does not mean that only these nuclides are to be detected and reponed. Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identi6ed and reported.
NOTE 3: Sampling and analysis shall also be performed following shutdown, start-up, and whenever a thermal power change exceeding 15 percent of the rated thermal power occurs within any .- one-hour period,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 period covered by each dose or dose rate calculation made in accordance with 6.3.1,6.3.3, and 6.3.4. NOTE 5: Samples shall be changed at least once per seven days and analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least seven days following each shutdown, start-up or thermal power change exceeding 15 percent of rated thermal power in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if: 131
- a. Analysis shows that the dose eq' uivalent 1 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 factor of 3.
l 1
- .~ VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 88 OF 156 ATTACHMENT 11 (Page 4 of 4)
North Anna Radioactive Gaseous Waste Sampling and Analysis Program . NOTE 6: Whenever the secondary coolant activity exceeds 10 5 Cihn!, samples shall be obtained and analyzed weekly. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours. NOTE 7: The principal gamma emitters for which the LLD speci6 cation applies exclusively are the following radionuclides: Kr87,Kr 88 ,Xel33, Xel33", Xe135, Xe135", and Xe138 for gaseous emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, at levels exceeding the LLD together with the above nuclides, shall also be identi6ed and reported. NOTE 8: If the secondary coolant activity level in any Steam Generator supplying steam to the Hogger exceeds 1.0E-5 pCi/ml, Steam Generator samples shall be obtained and analyzed prior to release.
~ . .
1
~
4 l 1 _
VIRGINIA VPAP-2103 L.:.
. , POWER REVISION 7 PAGE 89 OF 156 ATTACHMENT 12 (Page 1 of 3)
Gaseous Emuent Dose Factors for Surry - (Gamma and Beta Dose Factors) -
- 3 x/Q = 6.0E-05 sec/m at 499 meters N Direction Dose Factors for Ventilation Vent Noble Gas Kw Lin Min N;w Radionuclide Total Body Skin Gamma Air Beta Air mrem /vr mrem /vr mrad /vr mradlyr Curie /sec Curie /sec Curie /sec Curie /sec Kr-83m 4.54E+00 -
1.16E+03 1.73E+04 Kr-85m 7.02E+04 8.76E+04 7.38E+04 1.18E+05 Kr-85 9.66E+02 8.04E+04 1.03E+03 1.17E+05 Kr-87 3.55E+05 5.84E+05 3.70E405 6.18E+05 Kr-88 8.82E+05 1.42E+05 9.12E405 1.76E+05 Kr-89 9.%E+05 6.06E+05 1.04E+06 6.36E+05 Kr-90 9.36E+05 4.37E+05 9.78E+05 4.70E+05 Xe-131m 5.49E+03 2.86E+04 9.36E+03 6.66E+04 Xe-133m 1.51E+04 5.%E+04 1.96E+04 8.88E+04 Xe-133 1.76E+04 1.84E+04 2.12E+04 6.30E+04 Xe-135m 1.87E+05 4.27E+04 2.02E405 4.43E+04 Xe-135 1.09E+05 1.12E+05 - 1.15E+05 1.48E+05 Xe-137 8.52E+04 7.32E+05 9.06E+04 7.62E+05 Xe-138 5.30E+05 2.48E+05 5.53E+05 2.85E+05 Ar-41 , 5.30E+05 1.61E+05 5.58E+05 1.97E+05
l l VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 90 OF 156 ATTACHMENT 12 (Page 2 of 3)
- Gaseous Efnuent Dose Factors for Sorry. . , - . .... -
(Gamma and Beta Dose Factors)
' ~ ~
y/Q = 1.0E-06 sec/m3 at 6il4 iheters N Direction' ~ Dose Factors for Process Vent Noble Gas Ki Li M,ip N-Radionuclide Totalbody SE Gamma Air I Beta Air mrem /vr mrem /vh mrad /vr mrad /vr Curie /sec Curie /sec Curie /sec Curie /sec Kr-83m 7.56E-02 - 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 , 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93EM3 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E402 1.56E+02 1.11E403 - Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar 41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l l l
VIRGINIA VPAP-2103
. POWER REVISION 7 .
I PAGE 91 OF 156 ] , NITACHMENT 12 1 (Page 3 of 3) Gaseous Emment Dose Factors for Surry . .) l 3 (Inhalation Pathway Dose Factors) i 3 Ventilation Vent x/Q = 6.0E-05 sechn at 499 meters N Direction 3 '
~ Process Vent X/Q = 1.0E-06 sec/m at 644 meters S Directi~on '
Radionuclide Pin Pip mrem /vr mrem /vr j Curie /sec Curie /sec ; H-3 6.75E+04 1.12E+03 I Cr-51 5.13E+03 8.55E+01 l Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-90 ND ND ,l 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 3.64E+05 6.07E+03 Te-129m 3.80E+05 6.33E+03 Cs-134 ND - ND
~
Cs-136 . ND ND Cs-137 ND ND Ba-140 ND ND Cc-141 ND ND Ce-144- ND ND l-131 9.75E+08 1.62E+07 I-133 2.31E+08 3.85E+06 ND - No data for dose factor according to Regulatory Guide 1.109, Revision I
VIRGINIA VPAP-2103 ":i'. POWER REVISION 7 - PAGE 92 OF 156
.i ,5 Intentionally Blank 9
I S
. - - - - -- . . . . - . . - - . _ _ - - ~ - . . - .- . . - . . . . . - . .
VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 93 OF 156 ATTACHMENT 13 9 (Page 1 of 3) Gaseous Emuent Dese Factors for North Anna i~ . (Gamma and Beta Dose Factors) 3
- x/Q = 93E-06 sec/m at 1416 meters SE Direction '
Dose Factors for Ventilation Vent l Noble Gas Kiw Liw Min Nin 4 Radionuclide Total Body Skin Gamma Air BetaAir mrem /vr mrem /vr mrad /w mrad /vr
- Curie /sec Curie /sec Curie /sec Curie /sec j Kr-83m 7.03E-01 -
1.79E+02 2.68E+03
- Kr-85m 1.09E+04 1.36E+04 1.14E+04 1.83E+04 i
- Kr-85 1.50E+02 1.25E+04 1.60E+02 1.81E404 i
i Kr-87 5.51E+04 9.05E+04 5.74E+04 9.58E+04 J } Kr-88 1.37E+05 2.20E+04 1.41E+05 2.72E+04 1 ~ Kr-89 1.54E+05 .9.39E+04 1.61E+05 9.86E+04
- Kr-90 1.45E+05 6.78E+04 1.52E+05 7.28E+04 i
l Xe-131m 8.51E+02 4.43E+03 1.45E+03 1.03E44 Xe-133m 2.33E+03 9.24E403 3.04E+03 l 1.38E+04 1 Xe-133 2.73E+03 2.85E+03 3.28E+03 9.77E+03 Xe-135m 2.90E+04 6.61E+03 3.12E+04 6.87E+03 i Xe-135 . 1.68E+04 1.73E+04 - 1.79E+04 2.29E+04 Xe-137 1.32E+04 1.13E+05 1.40E+04 . 1.18E+05
- Xe-138 8.21E+04 3.84E+04 8.57E+04 1 4.42E+04 Ar-41 8.22E+04 2.50E+04 8.65E+04 3.05E+04 1
4 4
- l
, VIRGINIA VPAP-2103
~ POWER REVISION 7 .- PAGE 94 OF 156 ATTACHMENT 13 (Page 2 of 3)
~
Gaseous Emment Dese Factors for North Anna i
'~IGir5ma~a~n~d Beta Dose FactorsT' - -
y/Q = 1.2E-06 sec/m3at 1513 meters S Duection - Dose Factors for Process Vent -- -- - - - Noble Gas Kp . Li Mip Nip Radionuclide Total Body SE Gamma Air ' Beta Air - mrem /vr mrem /vr - mrad /w mrad /vr Curie /sec Curie /see Curie /sec Curie /sec Kr-83m 9.07E-02 - 2.32E+01 3.46E+02 Kr-85m 1.40E+03 1.75E+03 1.48E403 2.36E+03 Kr-85 1.93E+01 1.61E+03 2.06E+01 2.34E+03 Kr-87 7.10E+03 1.17E+04 7.40E+03 1.24E+04 Kr-88 1.76E404 2.84E+03 1.82E+04 3.52E403
~
Kr-89 1.99E+04 1.21E+04 2.08E+04 1.27E+04 Kr-90 1.87E+04 8.75E+03 1.%E+04 9.40E+03 Xe-131m 1.10E+02 5.71E+02 1.87E402 1.33E+03 Xe-133m 3.01E+02 1.19E+03 3.92E+02 1.78E+03 Xe-133 3.53E+02 3.67E+02 4.24E+02 1.26E+03 Xe-135m 3.74E+03 8.53E+02 4.03E+03 8.87E+02 Xe-135 2.17E+03 2.23E403 2.30E+03 2.95E+03 Xe-137 1.70E+03 1.46E+04 1.81E+03 1.52E+04 Xe-138 1.06E+04 4.%E+03 1.11E+04 5.70E+03 Ar-41 1.06E+04 3.23E+03 1.12E+04 3.94E+03
. l
' i VIRGINIA VPAP-2103 1 POWER REVISION 7 i PAGE 95 OF 156 l t i i l ATTACHMENT 13 , (Page 3 of 3) i Gaseous Emment Dese Factors for North Anna I p (Inhalation Pathway Dose Factors) 3 l Ventilation Vent X/Q = 9.3E-06 sec/m at 1416 meters SE Direction _; l ' Process Vent y/Q = 1.2E-06 sec/m3 at 1513 meters S Direction j Radionuclide Piw Pip mrnm/vr mrem /vr l . Curie /see Curie /sec l
- H-3 1.05E+04 1.35E+03
~
Cr-51 7.95E+02 1.02E+02 . ! Mn-54 ND
- ND l 2
Fe-59 ND ND < 1
- Co-58 -ND- ND l Co-60 ND ND 1
l { Zn-65 ND ND Rb-86 ND ND i Sr-90 ND ND 1 ! Y-91 ND -) ND ! Zr-95 ND ND ! Nb-95 ND ND 1 Ru-103 ND ND . Ru-106 ND ND i
- Ag-110m ND ND l Te-127m 5.64E+04 7.28E+03 j Te-129m 5.88E+04 7.59E+03 j Cs-134 ND -
ND ! Cs-136 ND ND s ! l Cs-137 ND ND I
- Ba-140 ND ND 3
Ce-141 ND ND Ce-144 -ND ND l j- I-131 1.51E+08 1.95E+07 j 1-133 3.58E+07 4.62E+06 j ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1 i l ! r
.,7- y .--. -
r - , - . . - - . - __ _ _ _ _ - - - - - -
a C VIRGINIA VPAP-2103 POWER REVISION 7 -
- PAGE % OF 156 u .
J r- r- y <22e:-rm.c ;e - nytnu m m. -e y , 4 i
- . . . . ~ . . . . . .. ... .
r I i 9 9- 4> e ) d e i .i Intentionally Blank 1 i ) . 1 i .i 1 J 1 i i l l l 4 1 4 4 3 a 4 m h j i 4
-I N
VIRGINIA VPAP-2103
., POWER REVISION 7 PAGE 97 OF 156 ATTACHMENT I4 (Page 1 of 3)
Surry Radioactive Gaseous Fmuent Monitoring Instrumentation MINIMUM
~
INSTRUMENT OPERABLE . ACTION CHANNELS
- 1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 1-GW-RM-102 ,,
1 1 1-GW-RM-130-1 (b) lodine Sampler Process Vent Continuous HP Sampler, or
~
1-GW-RM-130-1 1 2 (c) Particulate Sampler Process Vent Continuous HP Sampler, or 1 2 1-GW-RM-130-1 (d) Process Vent Flow Rate Monitor 1-GW-FT-100 1 3 (e) Sampler Flow Rate Measuring Device KAMAN Flow Rate Measuring Device 1 3 (Parameter #19), or HP Sampler Rotometer
- 2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor 1-SV-RM-111 2-SV-RM-211 2 (one pr unit) 1 (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP-F1-1 A l
1-VP-FI-l B Unit 2: 2-VP-FI-l A 2 (one per unit) 3 2-VP-FI-lB
- 3. VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF: RRM-101 1 1 SPS: Vent #1 1-VG-RM-104 1 1 Vent #2,1-VG-RM -110, or 1 1 1-VG-RM-131-1 I
VIRGINIA VPAP-2103 POWER REVISION 7 - PAGE 98 OF 156 ATTACHMENT 14 (Page 2 of 3) Surry Radioactive Gaseous Emuent Monitoring Instrumenta' tion MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS (b) Iodine Sampler SRF: RRM-101 1 . 2 SPS: Vent #1,1-VG-RM-2 04 1 2 r Vent #2, Continuous HP Sampler, or 1 2 1-VG-RM-131-1 (c) Particciate Sampler SRF: RRM-101 1 2 SPS: Vent #1, VG-RM-104 1 2 - Vent #2, HP Continuous Sampler, or 1 2 1-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor SRF: 01-RHV-FT-156 - - - - - -. 1 3 SPS: Vent #1,1-VS-FT-119 1 3 Vent #2,1-VS-FT-116 1 3 (e) Sampler Flow Rate Measuring Device - SRF: RRM-101 1 3 SPS: Vent #1,1-VG-RM-104 1 - 3 Vent #2, KAMAN Flow Rate Measuring Device 1 3 (Parameter #19), or HP Sampler Rotometer e
VIRGINIA VPAP-2103 POWER _ REVISION 7 PAGE 99 OF 156 ATTACHMENT 14 (Page 3 of 3)
'Surry Radioactive Gaseous Emuent Monitoring Instrumentation ACITON 1: If the number of operable channels is less than required, effluent releases via this path may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours.
ACI1ON 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 required in Attachment 10. -- ACTION 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 hours. 4 9'
3
,c VIRGINIA VPAP-2103
- ^ POWER REVISION 7 PAGE 100 OF 156
.c ,5 - -
- ~ea;a :., ,;;, , :
. .u .: .r. :. . . ,~, wrc._c:.
9 . ~. *t. 4 _ .. . , . . _ . _ . . . _ _ . . _ _ . _ . . . _ . . . . . Intentionally Blank O' e.,- 4 O $
VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 101 OF 156 i'
4 ATTACHMENT 15 (Page 1 of 3)
- North Anna Radioactive Gaseous Emment Monitoring Instrumentation -
1 4 I INSTRUMENT MINIMUM ACTION _ ._ . . i J--OPERABLE CHANNELS
- 1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor .
1-RM-GW-102 l-RM GW-178-1 I 2' 4 l f (b) Iodine Sampler l 1-RM-GW-178-1 i Process Vent Continuous HP Sampler 1 2, 5 l (c) Particulate Sampler j ' ! l-RM-GW-178-1 Process Vent Continuous HP Sampler 1 2, 5 i , (d) Total Flow Monitor j 1-GW-FT-108 1 1 (e) Sampler Flow Rate Measuring Device j KAMANS Flow Rate Measuring Device (Parameter 19) j HP SamplerRotameter I I
- 2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor
- UnitI l-SV-RM-121
)* Unit 2 2-SV-RM-221 1 3 (b) Flow Rate Measuring Device i Unit I l SV FI-100A i 1-SV-FI-101 A i 1 SV-FI-100B 1 (NOTE 1) 1 4 1 SV-FI-101B Unil2 2 SV-FI-200A 2-SV-FI-201 A 2 SV-F1200B 1 (NOTE 2) 1 2-SV FI-201B
.~
VIRGINIA VPAP-2103 f POWER REVISION 7
- I PAGE 102 OF 156 ATTACHMkNT 15 l~ ,
(Page 2 of 3) North Anna Radioactive Gaseous Emment Monitoring Instrumentation - l l j MINIMUM '
' INSTRUMENT OPERABLE ' ACTION CHANNELS
- 3. VENTILATION VENT A i l
(a) Noble Gas Activity Monitor ' 1-RM-VG-104 l RM-VG-179-1 I ' 2 (b) Iodine Sampler 1-RM-VG-179-1 1 2 Vent Vent A Continuous HP Sampler (c) Particulate Sampler l l-RM-VG-179-1 '
~
I Vent Vent A Continuous HP Sampler I (d) Total Flow Monitor - - - . 1 HV-FT-1212A 1 1 (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate ideasuring Device (Parameter 19)
; g HP Sampler Rotameter
- 4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-RM-VG-i l3 1-RM-VG-180-1 I 2 (b) lodine Sampler 1 RM-VG 180-1 -
Vent Vent B Continuous HP Sampler 1 2 (c) Particulate Sampler 1 RM VG 180-1 Vent Vent B Continuous HP Sampler I 2 (d) Total Flow Monitor 1-HV-FT-1212B I 1
- (c) Sampler Flow Rate Measuring Device i
- KAMANS Flow Rate Measuring Device (Parameter 19) g g HP Sampler Rotameter 4
l l l
-._m_______ _ _ _ _ _ _ _ _ . . _
3 VIRGINIA VPAP-2103
. POWER REVISION 7 i I
i PAGE 103 OF 156 A'ITACHMENT 15 l - (Page 3 of 3) l Nortb Anna Radioactive G=aaana Emment Monitoring Instrumentation ,
]
l ACTION 1: If the number of operable channels is less than required, effluent releases, via this path, may continue if the flow rate is estimated at least once per four hours. l ACTION 2: If the number of operable channels is less than required, effluent releases, via this path, may continue if grab samples are taken at least once per 12 hours and these samples are l analyzed for gross activity or gamma isotopic activity within 24 hours. i ACTION 3: If the number of operable channels is less than required, effluent releases, via this path, may continue if the frequency of the grab samples provided by Technical Speci6 cation requirement 4.4.6.3.b is increased to at least once per four hours and these samples are analyzed for gross activity or gamma isotopic activity within eight hours. ACTION 4: If the number of operable channels is less than required, the contents of the Waste Gas Decay Tanks may be released to the environment provided that prior to initiation of the l release: i a. At least two independent samples of the tank's contents are analyzed, and:
- b. At least two technically qualified members of the Station staffindependently verify
, the release rate calculations and discharge valve lineup. ACTION 5: If the number of operable channels is less than required, effluent releases from the Waste Gas Decay Tank may continue provided samples are continuously collected with auxiliary sampling equipment as required in Attachment 11. NOTE 1: A channel shall consist of:
- a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (1-SV-FI-100A,101 A), or Train B (1-SV-FI-100B,101B) or both.
- b. Flow instruments 101 A and 101B provide low range measurement. Flow instruments 100A and 100B provide high range measurement.
NOTE 2: A channel shall consist of: ' i
- a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (2-SV-FI-200A, 201 A), or Train B (2-SV-FI-200B,201B) or both.
l b. Flow instruments 201 A and 201B provide low range measurement. Flow instruments 200A and 200B provide high range measurement. t l l l
'.. i VIRGINIA VPAP-2103 !
- POWER ~ REVISION 7 !
PAGE 104 OF 156 a s .
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VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 105 OF 156 ATTACHMENT 16 (Page 1 of 2)
Surry Radioactive Gaseous EmuentMonitoring Instrumentation Surveillance Requirements
' L CHANNEL CHANNEL SOURCE CHANNEL yNCTI AL DESCRIPTION CHECK CHECK CALIBRATION TEST
- 1. PROCESS VENT SYNItM _
(a) Noble Gas Activity Monitor-Pmviding Alann and Automatic Tennination of Release 1-GW.RM-102 1-GW-RM-1301 D M'* R Q (b) lodine Sampler Pmcess Vent Continuous HP Sampler, or 1-GW-RM- 1301 W N/A N/A N/A (c) Paniculate Sampler Pmcess Vent Continuous HP Sampler, or 1-GW-RM- 130-1 W N/A N/A N/A (d) Pmcess Vent Flow Rate Monitor l l-GW FT-100 D N/A R N/A (e) Sampler Flow Rate Measuring . Device HP Sampler Rotometer,or - D N/A SA N/A KAMAN Flow Rate Measuring D N/A R N/A , Device (Parameter #19) l 2. CONDENSER AIR EJECTOR SYSTEM l (a) Gmss Activity Monitor Unit 1: 1-SV-RM-111 D R Q Unit 2: 2-SV-RM 211 (b) Air Ejector Flow Rate Measuring Device i Unit 1: 1-VP-F1 1 A l l-VP-F1-1B Unit 2: 2-VP-FI-1 A O N/A R N/A 2-VP F1-1B
- 3. VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF: RRM 101
, SPS: 1-VG-RM -I l0 D M R Q 1-VG-RM -131-1
1;q VIRGINIA POWER VPAP-2103 l REVISION 7 - I PAGE 106 OF 156 l s ATTACHMENT 16 I (Page 2 of 2) Surry Radioactive Gaseous Emuent Mortitoring Instrumentation Surveillance Requirements
' CHANNEL CHANNEL SOURCE CHANNEL- L DESCRIPTION CHECK CHECK CALIBRATION CTI R TEST (b) lodine Sampier SRF: RRM 101 SPS: Vent #1,1-VG-RM-104 Vent #2, Continuous HP Sampler, or 1 VG-RM-131- W N/A N/A N/A 1 i l
(c) Particulate Sampler SRF: RRM-101 SPS: Vent #1,1-VG-RM-104 Vent #2, Continuous HP
)
Sampler, or 1 VG-RM-131- W N/A N/A N/A i 1 (d) Ventilation Vent Flow Rate Monitor SRF: 01-RHV-FT-156 SPS: Vent #1,1-VS-FT-119 D N/A R N/A - Vent #2,1-VS FT-116 (e) Sampler Flow Rate Measuring Device SRF: RRM-101 D N/A R N/A SPS: Vent #1,1-VG-RM 104 D N/A R N/A Vent #2,KAMAN Flow Rate D N/A R N/A Measuring Device (Parameter #19), or HP D N/A N/A I Sampler Rotometer S/A
- Prior to cacti Waste Oas 13ecay lank release
VIRGINIA VPAP-2103
., POWER REVISION 7 PAGE 107 OF 156
, ATTACHMENT 17- l (Page 1 of 3) i
' North Anna Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Require:nents CHANNEL CHANNEL COURCE CHANNEL CHANNEL DESCRIPTION CHECK CHECK CALIBRATION FUNCTIONAL ~
TEST
- 1. PROCESS VENTSYSTEM j (a) Noble Gas Activity Monitor j 1-RM-GW-102 D M(NOTE 5) R Q(NOTE 1) l RM-GW-178-1 D l M (NOTE 5) R Q(NOTE 1) l 1
(b) Iodine Sampler 1-RM-GW-178-1 W N/A N/A N/A Process Vent Continuous HP i Sampler D(NOTE 3) N/A N/A N/A j ' (c) Paniculate Sampler
- l-RM-GW-178-1 W N/A N/A N/A
- Process Vent Continuous HP 1
Sampler D(NOTE 3) N/A N/A N/A (d) Total Flow Monitor - 1-GW-FT-108 D N/A R Q (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D(NOTE 3) N/A R N/A Device (Parameter 19) HP Sampler Rotameter D(NOTE 3) N/A SA N/A
- 2. CONDENSER AIR EJECTOR SYSTEM (a) Noble Gas Activity Monitor Unit I l-SV-RM 121 Unit 2 2-SV-RM 221 D 'M R Q(NOTE 1)
(b) Flow Rate Measuring Device UnitI l-SV-H-100A 1-SV-FI-101 A 1-SV-FI 100B D N/A R N/A 1-SV-FI-101B Unit 2 2-SV-H-200A 2 SV-FI-201 A 2-SV-FI-200B D N/A R N/A 2-SV-FI 201B
VIRGINIA. VPAP-2103 POWER . REVISION 7 - PAGE 108 OF 156 ATTACHMENT 17 ~' (Page 2 of 3) North Anna Radioactive Gaseous Emuent Monitoring Instrurnentation Surveillance n Requirernents CH3NNEL - -- CHANNEL SOURCE CHANNEL HAN E DESCb7'10N "
~ CHECK CHECK CAIDRATION FUNCII NAL
- 3. VENTILATION VENI A -_
(a) Noble Gas Activity Monitor 1-RM-VG-104 . D M R Q (NOTE 2) j 1-RM VG-179-1 D M (NOTE 5) R Q(NOTE 2)
~ l (b) Iodine Sampler -
1-RM-VG-179-1 W N/A N/A N/A 1 Vent Vent A Continuous HP Sampler i D(NOTE 3) N/A N/A N/A (c) Peticulate Sampler 1 RM-VG-179-1 W N/A N/A N/A ; Vent Vent A Continuous HP Sampler D(NOTE 3) N/A N/A N/A (d) Total Row Monitor 1 HV-FT-1212A D N/A R Q (c) Sampler Row Rate Measuring Device - KAMANS Row Rate Measuring D(NOTE 3) N/A R N/A Device (Parameter 19) HP Sampler Rotameter D (NOTE 3) N/A SA N/A
- 4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-RM VG-113 D M R Q(NOTE 4) 1-RM VG-180-1 D M (NOTE S) R Q (NOTE 2)
(b) Iodine Sampler j 1-RM-VG-180-1 W N/A N/A N/A Vent Vent B Continuous HP Sampler D(NOTE 3) N/A- N/A N/A l (c) Particulate Sampler j 1-RM-VG-180-1 W N/A N/A N/A i Vent Vent B Continuous HP Sampler _ D (NOTE 3) N/A N/A'. N/A (d) Total Row Monitor 1-HV FT-1212B D N/A R Q (e) Sampler Row Rate Measuring ~ Device KAMANS Row Rate Measuring D(NOTE 3) N/A R N/A Device (Parameter 19) HP Sampler Rotameter D(NOTE 3) N/A SA N/A
VIRGINIA VPAP-2103 - POWER REVISION 7 < PAGE 109 OF 156 l ATTACHMENT 17 (Page 3 of 3) North' Anna Radioactive Gaseous Emment Monitoring InstrumentationSurveillance Requirements , 1 NOTE 1: The chanad Functional Test shall demonstrate: a ' Aubmatic actuation of the valves in this pathway and Control Room alarm annunciation occur if the instrument indicates measured levels above the alarm / trip setpoint.
- b. Alarm annunciation occurs if the instrument controls not set in " operate" mode.
NOTE 2: The Channel Functional Test shall demonstrate: l
- a. Control Room alarm annunciation occurs if the instrument indicates measured levels are above the alarm / trip setpoint.
- b. Alarm annunciation occurs if the instrument controls not set in " operate" mode. I t
NOTE 3: Channel Checks shall consist of verifying indication of flow during periods of release. ! Channel Checks shall be made at least once per 24 hours on days on which continuous,
. periodic, or batch releases are made.
1 NOTE 4: The Channel Functional Test shall demonstrate that: , l
- a. Control Room alarm annunciation occurs if the instrument indicates measured levels are above alarm / trip setpoint.
- b. The Instrument mode selection control automatically resets to " operate" mode when l released.
NOTE S: Monitors 1-RM-GW-178-1,1-RM-VG-179-1, and 1-RM-VG-180-1 are electronically source checked using an LED. l 1 4
_ . - _ . _ . _ -~___ _-_.._. .___. _ _ __ _ . _ _ . _ . _ _ _ . . . _ -. _ . _ ._ _ . . _ VIRGINIA VPAP-2103 , POWER REVISION 7 - r
- i, PAGE 110 OF 156 1 '
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m VIRGINIA
, POWER VPAP-2103 REVISION 7 PAGE 111 OF 156 ATTACHMENT 18 (Page 1 of 2)
) Critical Organ.and Inhalation Dose Factors for Surry (Critical Pathway Dose Factors)
' Ventilation Vent D/Q = 9.0E-10 m-2at 5150 meters S Direction
- Process Vent D/Q = 4.3E-10 m-2 at 5150 meters S Direction Radionuclide RMw. RM p muim62 maalgt Curic/see Curie /see H-3 7.20E+02 3.12E+02 Mn-54 ND ND Fe-59 ND ND
~
Cr-51 6.45E+01 3.08E41 Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND - Y-91 ND ND Zr-95 ND ND, Nb-95 ND ND Ru-103 ND- ND Ru-106 ND ND Ag-110m ND ND Te-127m 8.06EW4 :3.85E+04 Te-129m 1.25E45 5.98E+04 1-131 6.21E+08 2.97E+08 l-133 5.79E+06 2.77EW6 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Cc-144 ND ND ND - No data for dose ft ctor according to Regulatory Guide 1.109, Revision 1
~
, . i i
VIRGINIA VPAP-2103 ' '- REVISION 7 - POWER PAGE 112 OF 156 ATTACHMEffr 18 (Page 2 of 2) Critical Organ and Inhalation Dose Factors for Surry .
)
(Inhalation Pathway Dose Pactors) ] Ventilation Vent y/Q = 3.0E-07 sec/m3 at 5150 meters S Direction Process Vent y/Q = 1.3E-07 sec/m3 at 5150 meters S Direction Radionuclide RMw RM-mrem /vr mrenb - Curic/sec' Curie /sec H-3 1.94E+02 8.41E+01 Cr-51 1.73E+01 7.48E+00 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND
- Zn-65 ND ND !
Rb-86 ND ND Sr-89 ND - ND ND Sr 90 ND Y-91 ND ND ! Zr-95 ND ND Nb 95 ND ND ' Ru-103 ND ND Ru-106 ND ND : Ag 110m ND ND Te-127m 1.46E+03 6.33E+02 r Te-129m 1.64E+03 7.12E+02 I-131 4.45E+06 1.93E+06 I-133 1.07E+06 4.63E+05 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Cc-141 ND ND i Cc-144 ND ND - t ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1
VIRGINIA VPAP-2103
. . POWER REVISION 7 PAGE 113 OF 156 ATTACHMENT 19 (Page1of1)
Critical Organ Dose Factors for North Anna - (Critical Pathway Dose Factors) - Ventilation Vent D/Q = 2.4E-09 m-2 at 3250 meters N Direction - _. - Process Vent D/Q = 1.1E-09 m-2 at 3250 meters N Direction Radionuclide RMj6 RM3p mrem /vr mrem /vr Curie /sec Curie /sec H-3 1.73E+03 9.36E+02 Mn-54 ND ND Fe-59 ND ND Cr-51 1.50E+02 6.89E+01 Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND - Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-110m ND ND Te-127m 1.97E+05 :9.04E+04 Te-129m 2.95E+05 1.35E+05 1-131 1.45E+09 6.72E+08 1-133 1.33E+07 6.12E+06 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Cc-141 ND ND Ce-144 ND ND ND - No data for dose factor accordmg to Regulatory Guide 1.109, Revision 1
VIRGINIA VPAP-2103 l POWER REVISION 7 - - l PAGE 114 OF 156 l 1 1
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t VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 115 OF 156 l
A'ITACHMENT 20 (Page 1 of 3) Surry Radiological Environmencd Monitoring Program , Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location Frequency ' Analysis *
- 1. DIRECT RADIATION -
About40 Routine -- -- Monitoring Stations to be placed as follows: I - -
- 1) Inner Ring in general-area of site boundary with station in each GAMMA DOSE sector ,
- 2) Outer Ring 6 to 8 km from the site with a Quarterly Quarterly station in each sector
- 3) 'Ihe balance of the 8 dosimeters should be
, placedinspecialinterest areas such as population centers, nearby residents, schools, and in2or 3areasto serveas '
controls
- 2. AIRBORNE Samples from 7 locations:
a) I sample from close to the site boundary location of the highest Radioiodine Canister calculated annual - 1131 Analysis Weekly average ground level Continuous Radioiodines and D/Q Sampler Particulates b) 5 sample locations 6-8 operation with Particulate Sampler km distance located in a samplecollection Gross beta radioactivity concentric ring around weekly analysis following filter the Station change; c) 1 sample from a control . . . location 15-30 km Gammaisotopicanalysis distant, providing valid f composite (by background data 1 cadon)quanerly
a VIRGINIA VPAP-2103
, POWER REVISION 7 .-
PAGE 116 OF 156 i 1 ATTACHMENT 20 (Page 2 of 3) Surry Radiological Entironmental Monitoring Program Exposure Pathway Number of Sample and - Collection 7 , Type and Frequency of and/or Sample Sample Location Frequency Analysis
- 3. WA'IERBORNE
- ~~ ~~ -
Gammaisotopic analysis a) I sample upstream ~ a) Surface thiYi Monthly Sample "Canposite b) I sample downstream fdtritium , analysis quarterly - Gammaisotopicandtritium b) Ground Sample from 1 or 2 sources '7 Quarterly" analysis quarterly c) Sediment I sample from downstream Gamma isotopic analysis from area with existing or Semi-Annually semi-annually shoreline potentialrecreational value 5 samples from vicinity of Gamma isotopic analysis d) Silt the Station 3 , y semi-annually
~ ~
- 4. INGESTION a) Milk a) 3 samples from milking (NOTE 1) animals,in thevicinityof Gamma isotopic and 1 131 b) mp e rom nulking Monthly aulysis monthly animals at a control l location (15-30 km l
distant) a) 2 samples of oysters in the vicinity of the Semi-Annually Gamma isotopic on edibles Station b) 4 samples of clams in the vicinity of the Semi-Annually Gamma isotopic on edibles b) Fish and Station Invertebrates c) I sampling of crabs - from the vicinity of the Annually Gamma isotopic on edibles Station d) 2 samples of fish from the vicinity of the . Station (catfish, white Semi-Annually Gamma isotopic on edibles perch, cel) l l l
s 2 VIRGINIA VPAP-2103 p*. ' POWER REVISION 7 PAGE 117 OF 156 ATTACHMENT 20
- (Page 3 of 3)
Surry Radiological Environmental Monitoring Program o _
- Exposure Pathway Number of Sample and _ Collection Type and Frequency of.
j and/or Sampfe Sample Location Frequency - Analysis .I 4. INGESTION
- (Continued) l a) I sample corn - - - --
b) I sample soybeans Annually -G a % ic o M & r c) I sample peanuts PoMon ] l d) I sample of a broadleaf j vegetation of two 4 different available i offsite locations with j highest annual average j c) Food groundlevelD/Q,ifone Products or more milk samples Monthly, if Gamma . isotopic and I 133 are unavailable available, or at e) 1 sample of a broadleaf harvest
""*l I *i' i vegetation grown 15-30 j
kmin the available,least
.}
1 prevalent wind direction,if one or more i milk samples are unavailable j j NOTE 1: If milk sampling cannot be performed, use item 4.c.(d). l l 1 1 i i l 4
+t ~'
VIRGINIA VPAP-2103 E.. POWER REVISION 7 . - ) PAGE 118 OF 156 l 1
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VIRGINIA VPAP-2103 I
.~ POWER REVISION 7 PAGE 119 OF 156 ATTACHMENT 21 (Page 1 of 5)
North Anna Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection , Type and Frequency of .I and/or Sample Sample Location (NOTE 2) Frequency Analysis
- l. DIRECT RADIATION (NOTE 3) -
36 routine monitoring stations,either with two of more dosimeters or with one instrument for measuring and recording dose rate continuously, to be placed as follows:
- 1) An inner ring of stations, one in each emergency GAMMA DOSE meteorological sector
~ within the site boundary .
- 2) An outer ring of stations, one in each '
emergency meteorological sector Quarerly Quarmrly within 8 km range from the site
- 3) The balance of the stations to be placed in specialinterest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations
,- VIRGINIA VPAP-2103 POWER REVISION 7 .- i PAGE 120 OF 156 )
A'ITACHMENT 21 l (Page 2 of 5) I i North Anna RadiologicalEnvironmental Monitoring Program q Exposure Pathway Number of Sample and_. . Collection .. Type and Frequency of l and/or Sample Sample Location (NOTE 2) Frequency Analysis J l
- 2. AIRBORNE - ~^ ~ ~~ ~~~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~~ -"
~ ~
Samples from 5 locations: ,, _ ]~ _ _ _ _ _ a) 3 samples from close to . , _ _ . . _ . _ _ _ _ . the 3 site boundary .. __ locations (in different _1._ _._ _ __. gg sectors) of the highest . . . . _ calculated historical ..3131 Analysis, weekly annual average ground Continuous . . . Radiciodines and levelD/Q sampler, . . _ _ Particulates b) I sample from the operation with - vicinity of a community sample ._ Particulate Sampler having the highest collection Gross beta radioactivity calculated annual weekly -- _ .. -._ analysis following filter
, .verage ground level change;(NOTE 4)
D/Q c) I sample from a control Gammaisotopic analysis location 15-40 km of composite (by distant and in the least location) quarterly prevalent wind directiori (NOTE 5)
- 3. WATERBORNE Samples from 3 locations:
Gamma isotopic analysis a) I sample upstream monthly;(NOTE 5) a) Surface b) 1 sample downstream Grab Monthly c) I sample from cooling analysis quarterly lagoon Sample from 1 or 2 sources Gammaisotopic and tritium b) Ground only iflikely to be affected Grab Quarterly analysis quarterly (NOTE 5) I sample from downstream . . . area with existing or amma is topic analysis c) Sediment Semi-Annually potential recreational value senu annually (NOTE 5) O
a. l- VIRGINIA VPAP-2103 L . POWER REVISION 7 RAGE 1210F 156 ATTACHMENT 21 l (Page 3 of 5) [ l North Anna Radiological Environmental Monitoring Program Exposure Pathway NumberofSampleandSample Collection Type and Frequency of and/or Sample Location (NOTE 2) Frequency Analysis
- 4. INGESTION a) Samples from millang animals in 3 locations within -
5 km that have the highest potential. If there are none, then I sample from milking animals in each of 3 areas a) Milk between 5 to 8 km where Monthlyatall Gammaisotopic(NOTE 5) (NOTE 7) doses are calculated to be times and1131 analysis monthly , greater than 1 mrem per yr (NOTE 6) b) I sample from milking animals at a controllocation ' (15-30 km in the least
. prevalent wind direction) .
a) 1 sample ofcommerciallyand recreationallyimportant . species (bass, sunfish, catfish) b) Fish and in vicinity of plant discharge Gamma isotopic on edible Invertebrates area 3 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 c) Food ground level D/Q if milk Monthlyif Gammaisotopic(NOTE 5) Products sampling is not performed """**'# and1831 analysis b) I sample of broad leaf at harvest , vegetation grown 15-30kmin the least prevalent wind j direction if milk samplingis l not performed 1
VIRGINIA VPAP-2103 POWER ' REVISION 7 - PAGE 122 OF 156 A'ITACHMENT 21 (Page 4 of 5) North Anna Radiological. Environmental Monitoring Program . NOTE 1: The number, media, frequency, and location of samples may vary from site to site. 'Ihis table presents an acceptable minimum program for a site at which each entry is applicable.
~
Loca1 site characteristics must be examined to determine if pathways not covered by this table may signi6cantly contribute to an individual's dose and be included in the sampling program. 2 . ' ; ' r - 7 ... . NOTE 2: For each and every sample location in Attachment 21, speci6c parameters of distance and direction sector from the centerline of the reactor, and additional description where pertment, shall be provided in Attachment 23. Refer to Radiological Assessment Branch Technical Positions and to NUREG-0133, Ly Mon of Radiological Effluent Technical Speci6 cations for Nuclear Power Plant. Deviations are permitted from the required sampling schedule if specimens are unattainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unattainable due to sampling equipment malfunction, every effort shall be
, made to complete corrective action before the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to 6.7.1. It is recognized that, at times, it may not '
be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable attemative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to 6.7.2, identify the cause of the unavailability of samples for that I pathway and identify the new locations for obtaining replacement sampl'es in the next Annual Radioactive Effluent Release Report, and include revised figures and tables from the ODCM reflecting the new locations in the report. 1
VIRGINIA VPAP-2103 POWER REVISION 7 ' PAGE 123 OF 156 ATTACHMENT 21 (Page 5 of 5) North Anna Radiological Environmental Monitoring Program NOTE 3: One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. l Por the' purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be I l 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. De 36 stations I are not an absolute number. De number of direct radiation monitoring stations may be l 1 reduced according to geographical limitations, e.g., at an ocean sit'e, some sectors will be l 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 speci6c system used and should be selected to obtain optimum dose information with minimal fading. NOTE 4: Airbome particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron ilaughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples,
~
gamma isotopic analysis shall be performed on the individual samples. NOTE 5: Gamma isotopic analysis is the identification and quantification of gamma-emitting radionuclides that may be attributable to effluents from the facility. NOTE 6: The dose shall be calculated fo'r the maximum organ and age group, using the methodology and parameters in the ODCM. NOTE 7: If milk sampling cannot be performed, use item 4.c (Page 3 of 5, Attachment 21) I 9
VIRGINIA VPAP-2103 POWER REVISION 7 - PAGE 124 OF 156 p, t 1 1 -
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l" VIRGINIA VPAP-2103 {
. POWER -
REVISION 7 PAGE 125 OF 156 : i i ATTACHMENT 22 ; l' ' (Page 1 of 4) i $ Surry Environenental Sampling Locatione - -
. i SAMPLE LOCATION DISTANCE DIRECTION REMARKS !
! MEDIk (MILES) ; i Air Charcoal Site Boundary , i and Particulate Surry Station (SS) .037.-- . ._ NNE location at Sector ;
- j. with Highest D/Q ,
j Hog Island Reserve (HIR) 2.0 NNE ! Bacons Castle (BC) 4.5 SSW l Alliance (ALL) 5.1 WSW j Colonial Parkway (CP) 3.7 NNW I Dow Chemical (DOW) 5.1 ENE ) 4 Fort Eustis (FE) 4.8 ESE j Newport News (NN) 16.5 ESE Control Location Environmental Control (00) Onsite ** l l TLDs West North West (02) 0.17 .WNW Site Boundary Surry Station Discharg 0.6 NW Site Boundary
, (3) -
! North North West (04) 0.4 NNW Site Boundary North (05) 0.29 N Site Boundary l 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 l { East (Exclusion) (09) 0.31 E Onsite i ! West (10) 0.40 W Site Boundary j West South West (11) 0.45 WSW Site Boundary { South West (12) 0.30
- SW Site Boundary l 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 f South East (16) 1.00 SE Site Boundary i East (17) 0.57 E Site Boundary I Station Intake (18) 1.23 ESE Site Boundary } HogIsland Reserve (19) 1.94 NNE Near Resident 3 j . i j l l,
VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 126 OF 156 ATTACHMENT 22 l (Page 2 of 4)
- l Surry Environinental Sarnpling Locations .
1 t SAMPLE ~~
. LOCATION DISTANCE DIRECTION REMARKS !
MEDIA (MILES) Environmental Bacons Castle (20) 4.45 SSW Approx. 5 miles TLDs Route 633 (21) 3.5 SW Approx. 5 miles i Alhance (22) 5.1 WSW Approx. 5 miles Surry (23) 8.0 WSW Population Center l Route 636 and 637 (24) 4.0 W Approx. 5 miles ; Scotland Wharf (25) 5.0 WNW Approx. 5 miles Jamestown (26) 6.3 NW Approx. 5 miles Colonial Parkway (27) 3.7 NNW Approx. 5 miles - Route 617 and 618 (28) 5.2 NNW Approx. 5 miles Kingsmill - (29) 4.8- - . -- N - Approx. 5 miles ; Williamsburg , (30) 7.8 N Population Center Kingsmill North (31) 5.6 NNE -
-Approx. 5 miles ,
Budweiser (32) 5.7 NNE Population Center Water Plant (33) 4.8 NE Approx. 5 miles Dow (34) 5.1 ENE Approx. 5 miles ; 1.c e H all (35) 7.1 ENE Population Center Goose Island (36) 5.0 E Approx. 5 miles j Fort Eustis (37) 4.8 ESE Approx. 5 miles Newport News (38) 16.5 ESE Population Center ; James River Bridge (39) 14.8 SSE Control , Benn's Church (40) 14.5 S Control Smithfield (41) 11.5 S Control i Rushmere (42) 5.2 SSE Approx. 5 miles Route 628 (43) 5.0 S Approx. 5 miles l Milk Epp's 4.8 SSW l Colonial Parkway 3.7 NNW l Judkin's 6.2 SSW ; William's 22.5 S Control Location m , -- ,
*. i
! VIRGINIA VPAP-2103 l L. POWER REVISION 7 PAGE 127 OF 156 ATTACHMENT 22 (Page 3 of 4) Surry Environmental Sampling Locations . SAMPLE ~ LOCATION DISTANCE DIRECTION REMARKS MEDIA (MILES) Well Water Surry Station Onsite*** Hog Island Reserve 2.0 NNE Crops (Corn, Slade's Farm 2.4 S Peanuts, _
)
Soybeans) Brock's Farm 3.8 S Crops Spratley's Garden 3.2 S (Cabbage, Kale) Carter's Grove Garden 4.8 NE Lucas's Garden "*' I " (Chester, Va.) River Water Surry Discharge 0.17 NW (Monthly) Scotland Wharf 5.0 WNW Control Location Sediment Chickahominy River 11.2 WNW Control Location l
~
(Silt) Surry Station intake 1.9 ESE Surry Station Discharge 1.0 NNW Hog Island Point 2.4 NE
~
Point of Shoals 6.4 SSE J l l I l
$ VIRGINIA VPAP-2103 POWER REVISION 7 - PAGE 128 OF 156 ATTACHMENT 22 + (Page 4 of 4) Surry Environmental Sampling Locations SAMPLE , LOCATION DISTANCE DIRECTION REMARKS MEDIA - (MILES) Clams - Chickahominy River 11.2 WNW Control Location Surry Station Discharge 1.3 NNW Hog Island Point 2.4 NE Lawne's Creek 2.4 SE Oysters Kingsmill 2.9 NE l Mulberry Point 4.9 EESE Crabs Surry Station Discharge 0.6 NW Fish Surry Station Discharge 0.6 NW Shoreline Hog Island Reserve 0.8 N Sediment Onsite Location -in Lead Shield Onsite sample of Well Water-taken from tap-water at Surry Environmental Building
( . VIRGINIA !. POWER VPAP-2103 REVISION 7 PAGE 129 OF 156 ATTACHMENT 23 (Page 1 of 4) North Anna Environinental Sampling Locations Distance and Direction From Unit No.1 Sa -S- - Lation Station Distance Direction Collection REMARKS Media No. (Miles) Frequency { Envimnment NAPSSewageTW2 ent I al Plant 01 0.20 NE Quanedy & Annually On-Site A Ds Frederick's Hall 02 5.30 W"'iY A SSW Annually Mineral,VA 03 7.10 WSW W "I'Y A Annually ; Wares Crossroads 04 5.10 WSW W"Y A I Annually l Route 752 05 4.20 NNE W"Y A Annually j Sturgeon's Creek Marina 05A 3.20 8'Y A N , Levy, VA 06 4.70 9" YA ESE Bumpass, VA 07 7.30 Q" SSE
$A End of Route 685 Q" 21 1.00 WNW g$A Site Boundary -
Route 700 22 1.00 WSW Quane & g Site Boundary
" Aspen Hills" 23 0.93 SSE 9" A Site Boundary Orange, VA 24 22.00 Quane & Control NW g Bearing Cooling'Ibwer N-IS3 0.06 N Quarterly On-Site l Sturgeon's Creek Manna N-2S4 3.20 N l Quanerty Parking Lot "C" NNE-3S$ 0.24 NNE Quanerly On-Site Good Hope Church l NNE-486 4.% NNE Quanerly Parking 1.ot "B" NE-5S7 0.20 NE Quarterly On-Site i Bogg's~ Drive NE-6S8 1.46 NE Quanerly WeatherTower Fence l
ENE 7S9 0.36 SNE Quanerly On-Site l Route 689 ENE-8/40 2.43 ENE Quanerly NearTraining Facility E-9/41 0.30 E Quanerly On-Site "Moming Glory Hill" E-10/42 2.85 E Quenedy Island Dike ESE-II/43 0.12 ESE Quanerly On-Site Route 622 ESE-12/44 4.70 ESE Quanerty i l r l l
VPAP-2103 VIRGINIA REVISION 7 .-
. POWER PAGE 130 OF 156 1
ATTACHMENT 23 (Page 2 of 4) North AnnaEnvironmentalSampling3* s 1 Distance and Direction Froen Unit No. I Sa
~ Location Station Distance Direction (Whetlan REMARKS M No. (Miles) Frequency Emritorment Biology Lab SE-13/45 0.75 SE Quanedy On-Site 1 al - ... . s -
i TLDs Route 701 (Dan Entrance) SE-14/46 5.88 SE Q My ,
" Aspen Hills" SSE-15/47 - 0.93 SSE Quanedy Site Bo -A3 Elk Creek . SSE-16/48 2.33 SSE Quanedy NAPS Access Road S-17/49 - 0.47 S_ Quanedy On-Site l j Elk Creek Omrch S-18/50 1.55 S Quanedy .
NAPS Access Road SSW-19/51 0.42 SSW Quanedy On-Site l Route 618 SSW-20/52 5.30 SSW Quanedy 500KV Tbwer SW-21/53 0.60 SW Quanedy On-Site l [ Route 700 SW-22/54 4.36 SW Quartedy 0.38 WSW Quanedy On-Site l NAPS RadioTbwer WSW-23/55 l Route 700 WSW-24/56 1.00 WSW Quanedy Site Boundar) l
~
South Gate of Switchyard W-25/57 0.32 W Quanedy On-Site l Route 685 W-26/58 1.55 W Quanedy . End of Route 685 WNW-27/59 1.00 WNW Quanedy Site Boundar) Route 685 WNW 28/60 1.40 WNW Quanedy l l Laydown Area North Gate NW 29/61 0.45 NW Quanerly On-Site l ; Lake Anna Campground NW-30/62 2.54 NW Quartedy ,
#1#2 Intake NNW-31/63 0.07 NNW Quanedy On-Site Route 208 NNW-32/64 3.43 NNW Quanedy l Bumpass Post Office C-1/2 7.30 SSE Quanedy Contml Orange, VA C-3/4 22.00 NW Quanerly Control Mineral. VA. C-5/6 7.10 ,. WSW Quartedy Control :
t Louisa. VA C-7/8 11.54 WSW Quanedy Control t
VIRGINIA VPAP-2103 i - . POWER REVISION 7 { PAGE 131 OF 156 ATTACHMENT 23 {- (Page 3 of 4) North Anna Environenental Sasnpling Locations Distance and Direction Fruen Unit No.1 1 l Sample . Location Station Distance Direction Couection REMARKS - ! ! Media ~ ~ No. (Miles) Frequency I j Airbome NAPSSewageTmannent 01 0.20 NE Weekly On-Site
- Plant t j Particulate Frederick's Hall 02. 5.30 SSW Weekly - ;
! and Mmeral, VA 03 7.10 Wsw Weekly !' Radioiodine Wams Crossroads 04 5.10 WNW Weekly l Route 752 05 4.20 NNE Weekly l Sturgeon's Creek Marina 05A 3.20 N Weekly l levy,VA 06 4.70 ESE Weekly l Bumpass, VA 07 7.30 SSE Weekly
, End of Route 685 21 1.00 WNW Weekly Site Boundary l Route 700 22 1.00 WSW Weekly Site Boundary l ; " Aspen Hills" 23 0.93 SSE Weekly Site Boundary l Orange. VA 24 22.00 NW Weekly Control Surface Water Waste Heat Treatment
- ~
[ Commitment Facility (Second Cooling 08 1.10 SSE Monthly 3.2.2] Lagoon) . North Anna River I
- (upstream)Rt669 Blidge 09A 12.9 WNW ' Monthly Control (Brook's Bridge)
- North Anna River 5.80 11 SE Monthly (downstream)
Biology Lab OIA 0.75 SE Quarterly j Aquade Waste Heat Treatment j Sediment. Facility (Second Cooling 08 1,10 SSE Semi Annually Lagoon) North Anna River
- i (upstream)Rt 669 Bridge 09A 12.9 WNW Semi Annually Control (Brook's Bridge) .
North Anna River 5.80 11 SE Semi-Annually (downsneam) ! ) Shoreline Soil Lake Anna (upstream) 09 2.20 NW Semi-Annually Soil SewageTreatment 01 0.20 NE Once per 3 yrs On-Site 4 1
~
i r
/
i 4
w VIRGINIA VPAP-2103 POWER REVISION 7 - PAGE 132 OF 156 i ATTACHMENT 23 (Page 4 of 4) ; North Anna Envir6nenental Sainpling Locations i Distance and Direction Frern Unit No. I ; Sa Location , Direction Station Distance ~ CMiection REMARKS M in No. pr ***'
- Soil Fredericks Hall' - 02 5.30 - suW Once per3 yrs ,
(continued) Mineral, VA .. . 03 .7.10 WsW Once per 3 yrs s Wares Crossroads 04 5.10 WNW Once per 3 yrs , t Route 752 05 4.20 NNE Once per 3 yrs ./ Sturgeon's Creek Marina 05A 3.20 N Once per 3 yrs ; levy, VA 06 4.70 ESE Once per3 yrs Bumpass, VA 07 7.30 SSE Once per 3 yrs ; I End of Route 685 21 1.00 WNW Once per 3 yrs Site Boundary Route 700 22 1.00 WsW Once per 3 yrs Site Boundary ;
" Aspen Hills" 23 0.93 SSE Onm per 3 yrs Site Boundary l Orange, VA . 24 22.00 NW Once per 3 yrt Control {'
Milk Holladay Dairy 12 8.30 NW Monthly (R.C. Goodwin) ; Tenell's Dairy 13 5.60 SSE Monthly. (Frederick's Hall) Fish Waste Heat Treaunent Sesni- !' Facility (Second Cooling 08 1.10 SSE Annually Lagoon) 25 16.50 NW 88'"I* Lake Orange Control Annually Food Products Route 713 14 vanes NE (Broad Leaf Route 614 15 vanes SE Monthly vegetation) Route 629/522 16 varies NW if available,or Control Route 685 21 varies WNW at harvest i'
" Aspen Hills" Area 23 varies SSE l
i f r h i
VIRGINIA VPAP-2103
. POWER REVISION 7 PAGE 133 OF 156 i
ATTACHMENT 24 1 (Page 1 of 2) Detection Capabilities for Surry Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD) Airbome Food Analysis Water Particulate Milk Products Sed.e nt 1 (NOTE 2) (pCi/l) or Gases EI (pCi/l) (pCi/kg) I EI ' (pCi/m3) ) (wet). Gross beta 4 0.01 1 H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 i 1-131 (NOTE 3) 1 0.07 1 60 Cs-134 15 0.05 130 15 60 150 i 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 given in Regulatory Guide 4.13. NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Other peaks ; that are measurable and identifiable, together with the above nuclides, shall also be l identified and reported. l 1 NOTE 3: LLD for the Ground (drinking) Water Samples. The LLD for the surface (non-drinking) water samples is 10 pCi/1. 1 l J
l VIRGINIA VPAP-2103 POWER
- REVISION 7 l PAGE 134 OF 156 i NITACHMENT 24 (Page 2 of 2) k)etection Capabilities for Sorry Environmental Sample Analysis
~
LOWER LIMIT OF DETECTION (LLD) - NOTE 1: For a partiqular measurement system (which may include radiochemical separation): w-
- 4.66 sg.
LLD = ., (24-1) E
- V = 2.22E406
- Y e e-(Aat) u
+.
Where: - LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above . r (as microcuries per unit mass or volume) (see 4.8) sb = 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) V = the sample size (in units of mass or volume) 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable) A = the radioactive decay constant for the particular radionuclide At = the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmehtal samples, not plant effluent samples) .. Typical values of E, V Y and At should be used in the calculation. The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement, r l l
_u m__ _ _ . . ._ .a.. _ ,-.=m _ __.-a._.. _._2-_.___.__,4~_._.2m.,_m g. 4# _ ._2.- 4__ i : VIRGINIA VPAP-2103
. . POWER REVISION 7
- l PAGE 135 OF 156 ATTACHMENT 25 (Page 1 of 2)
Detection Cap bilitic for North Anna Environmental Sample Analysis i ! LOWER LIMIT OF DETECTION (LLD)
~
Airborne Food i Analysis Water Particulate Milk Sediment Products (NOE 2) (pCi/l) or Gases ( E} ( E} (pCi/l) (pCi/kg) (pCi/m3) ("*"} I"*"I (wet) Gross beta 4 0.01
- H-3 2,000 ~
l Mn-54 15 130 - Fe-59 30 260 Co-58,60 15 130 1 Zn-65 30 260 ! Zr-95 30 Nb-95 15 j I-131 (NOTE 3) 1 0.07 1 60 Cs 134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 l Ba-140 60 60 La-140 15 15 j NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. NOTE 2: This list does not mean that only these nuclides are to be detected and' reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported. NOTE 3: LLD for the ground (drinking) water samples. The LLD for the surface (non-drinking) water samples is 10 pCi/1. ' l
1 VIROINIA VPAP-2103 4 POWER REVISION 7 . PAGE 136 OF 156 i ATTACHMENT 25 (Page 2 of 2) Detection Capabilities for North Anna Environmental-Sample Analysis . LOWER LIMIT OF DETECTION (LLD) (NOTE 3) . NOTE 3: For a particular measurement system (which may include radiochemical' separation): i .. 4.66 s b ~ t LLD = (25-1)
. E e V e 2.22E+06
- Y e e-(AA0 )
Where: ,. i LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above ! (as microcuries per unit mass or volume) (see 4.9) . sb = 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)
.i V = the sample size (in units of mass or volume) 2.22E406 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radi.ochemical 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 should be used in the calculation. l The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.
VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 137 OF 156 ATTACHMENT 26 (Page1of1) Reporting Levels for Radioactivity Concentrations in Environmental Samples at Surry -
~
- Water M' **
.. Fish Milk Food Products
"*'# " (PCill)
(PCi/kg, wet) (pCi/l) (pCi/kg, wet) Ga. p i/ ) H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 (NOTE 1) 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 - NOTE 1: Reponing 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. l
VIRGINIA VPAP-2103 PO M REVISION 7 - i PAGE 138 OF 156
,y 7 ,- ,, ,, .. ,
-u. u - , , ,o , e , ,.
.'t' 4...- ..1. . . ':: . J i
Intentionally Blank I i I I 1 I i l J
VIRGINIA- VPAP-2103
._ POWER REVISION 7 PAGE 139 OF 156 ATTACHMENT 27 (Page 1 of 1)
Reportins' Levels for Radianctivity Concentrations in Environmental Samples at North Annq t-i
- Water Fish Milk Food Products
'I (PCill) g [y (pCi/kg, wet) (pCill) (pCi/kg, wet)
H-3 (NOTE 1) 20,000
~
Mn-54 1,000 30,000 Fe-59 400 , 10,000 Cc-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 '
c' O e 1
VIRGINIA VPAP-2103 POWER ' REVISION 7 - PAGE 140 OF 156 f i 4 w d I 1 I i a _ . d intentionally Blank 3 2 8 1 d 5 e ~ i I 1 i J 4 d .1 f J
*i
VIRGINIA
- VPAP-2103
- POWER REVISION 7 .
PAGE 141 OF 156 ATTACHMENT 28 (Page 1 of 8) ,
- 1 Surry Meteorological, Liquid, and Gaseous Pathway Analysis i 1.0 METEORLOGICAL ANALYSIS ,
1.1 Purpose l
~
- The purpose of the meteorological analysis was to determine 'he t annual average %/Q and D/Q l i l values at critical locations around the Station for ventilation vent (ground level) and process '
vent (mixed mode) releases. The annual average %/Q and D/Q values were used in a dose j pathway analysis to determine both the maximum exposed individual at site boundary and l 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. I l 1.2 Meteorological Data, Parameters, and Methodology i
~
Onsite meteorological data for the period January 1,1979, through December 31,1981, were l used in calculations. These data included wind speed, wind direction, and differential temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (i.e., ventilation vent), and those characterized as mixed mode (i.e., process vent). De portions of release characterized as ground level were based on -l AT158.9ft.28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were ! based on AT158.9ft.28.2ft and 158.9 ft wind data. l 1
%/Qs and D/Qs were calculated using the NRC computer code "XOQDOQ - Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations",
September,1977. De code is based upon a straight line airflow model implementing the assumptions outlined in Section C (excluding C1a and Clb) of Regulatory Guide 1.111,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."
The open terrain adjustment factors were applied to the X/Q values as recommended in Regulatory Guide 1.111. De site region is characterized flat terrain such that open terrain correction factors are considered appropriate. The ground level ventilation vent release ! calculations included a building wake correction based on a 1516 m2 containment minimum ! cross-sectional area. The effective release height used in mixed mode release calculations was l based on a process vent release height of 131 ft, and plume rise due to momentum for a vent l diameter of 3 in. with plume exit velocity of 100 ft/sec. >
. VIRGINIA VPAP-2103
- POWER REVISION 7 -
PAGE 142 OF 156 i A'ITACHMENT 28~ r (Page 2 of 8) Surry Meteorological, Liquid, and Gaseous Pathway Analysis l Ventilation vent, and vent releases other than from the process vent, are considered ground 2 level as specified in Regulatory Guid: 1.111 for release points less than the height of adjacent _ l solid stnictures'. Terrain elevations were obtained from Surry Power Station Units 1 and 2
- Virginia Electric and Power Company Updated Final Safety Analysis Report Table 11A-8.
- %/Q and D/Q values were calculmed for the nearest site boundary, verddent, 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 ventilatan vent releases. l l
j According to the definition for short term in NUREG-0133,"Prgaration of Radiological j - Effluent Technical Specifications for Nuclear Power Stationt," October,1978, some gaseous releases may fit this category, primarily waste gas decay tank releases and containment purges. However, these releases are considered long term for dose calculations as past releases were i both random in time of day and duration as evidenced by reviewing past release reports. ( j Therefore, the use of annual average concentrations is appropriate according to NUREG-0133. j 1.3 Results The %/Q value that resulted in the maximuth total body, skin, and inhalation exposure for ventilation vent releases was 6.0E-05 sec/m3 at a site boundary location 499 meters N sector. For process vent releases, the site boundary X/Q value was 1.0E-06 sec/m3 at a location 644 meters S sector. The discharge canal bank %/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 7.8E-05 sec/m3 at a location 290 meters NW sector. The discharge canal bank %/Q value for process vent was 1.6E-06 sec/m3 at a location 290 meters NW sector. l Pathway analysis indicated that the maximum exposure from 1131, 1133, and from all radionuclides in particulate form with half-lives greater than 8 days, was through the grass-cow-milk pathway. He D/Q value from ventilation vent releases resulting in the maximum exposure was 9.0E-10 per m2 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 sec/m 3, and 1.3E-07 sec/m3 or f process vent releases at a location 5150 meters S sector. The inhalation pathway is the only other pathway existing at this location. Derefore, the %/Q values given for tritium also apply for the inhalation pathway.
. 1 VIRGINIA VPAP-2103
. POWER REVISION 7
, PAGE 143 OF 156 NITACHMENT 28 (Page 3 of 8) : Surry Meteorological, Liquid, and Gaseous Pathway Analysis ) 4 2.0 LIQUID PATHWAY' ANAL.YSIS 2.I Purpose The purpose of the liquid pathway analysis was to deternune the maximum exposed member j of the public in unrestricted areas as a result of radioactive liqmd ef0uent releases. De 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 j Effluents. I i
2.2 Data, Parameters, and Methodology Radioactive liquid effluent release data for the years 1976,1977,1978,1979,1980, and 1981 were compiled from the Surry Power Station effluent release reports. The data for each year,
- j. along with appropriate site specific parameters and default selected parameters, were entered into the NRC computer code LADTAP as described in NUREG-0133.
. l
- Liquid radioactive effluents from both units are released to the James River via the discharge 4
canal. Possible pathways of exposure for release from the Station include ingestion of fish and invertebrates and shoreline activities. De irrigated food pathway and potable water pathway do not exist at this location. Access to the discharge canal by the general public is gained two ways: bank fishing, controlled by the Station and limited to Virginia Power employees or guests of employees, and by boat as far upstream as the inshore end of the discharge canal I groin. It has been estimated that boat sport fishing would be performed a maximum of 800 l hours per year, and that bank fishing would be performed a maximum of 160 hours per year. i For an individual fishing in the discharge canal, no river dilution was assumed for the fish pathway. For an individual located beyond the discitarge canal groins, a river dilution factor of 5 was assumed as appropriate according to Regulatory Guide 1.109, Rev.1, and the fish, j mvertebrate, and shoreline pathways were considered to exist. Dose factors, bioaccumulation j factors, and shore width factors given in Regulatory Guide 1.109, Rev.1, and in LADTAP were l 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.
i j
,i VIRGINIA VPAP-2103 POWER REVISION 7 -
PAGE 144 OF 156 A'ITACHMENT 28 (Page 4 of 8) Surry Meteorological,Liipuid, and Gaseous Pathway Analysis 2.3 Results For the years 1976,1977,1979,1980, and 1981, the invertebrate pathway resulted in the largest dose. In N78 the fish pathway resulted in the largest dose. De 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. De ingestion dose factor, A1,in 6.2.3 includes the fish and invertebrate pathways. Ai dose factors were calculated for the total body, thyroid, and GI-111 organs. . 3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose A gaseous effluent pathway analysis was performed to determine the location that would result in the maximum doses due to noble gases, for use in demonstrating compliance with 6.3.1.a. , and 6.3.3.a. The analysis also included a determination of the location, pathway, and critical organ, of the maximum exposed member of the public, as a result of the release of1131, 1133, tritium, and for all radionuclides in particulate form with half-lives greater than eight days for use in demonstrating compliance with 6.3.4.a. In addition, the analysis included a l determination of the critical organ, maximum age group, and sector location of an exposed individual through the inhalation pathway from 1133, 1333, tritium, and particulates to demonstrate compliance with 6.3.1.a.. ; 3.2 Data, Parameters, and Methodology Annual average X/Q values were calculated, as described in Section 1 of this attachment, for the nearest site boundary in each directional sector and at other critical locations accessible to the public inside site boundary. The largest X/Q value was determined to be 6.0E-05 sec/m3 at site boundary for ventilation vent releases at a location 499 meters N direction, and 1.0E-06 sec/m3 at site boundary for process vent releases at a location 644 meters S ducction. De maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble l gases would be at these site boundary locations. De doses from both release points are summed in calculations to calculate total maximum dose. e
- s ;
!m VIRGINIA VPAP-2103 P. POWER REVISION 7 l - P. AGE 145 0F 156 ' I l i, ATTACHMENT 28 ! 1 (Page 5 of 8) ' 4 Surry Meteorological, Liquid, and Gaseous Pathway Analysis ) J Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and X/Q values determined for maximum noble gas doses can be used to determine the l maximum ~ dose from 1131, 1133, tritium, and for all radionuclides in particulate form with half-
! lives greater than 8 days for the inhalation pathway, i
The NRC computer code GASPAR," Evaluation of Atmospheric Releases," Revised 8/19/77, was run using 1976,1977,1978,1979,1980, and 1981 Surry Power Station gaseous effluent release report data. Doses from 1131, 1133, tritium, and particulates for the inhalation pathway l were calculated using the 6.0E-05 sec/m3 site boundary X/Q. Except for the source term data ' and the X/Q value, computer code default parameters were used. Results for each year indicated { that the critical age group was the child and the critical organ was the thyroid for the inhalation I pathway. In 1979, the teen was the critical age group. However, the dose calculated for the teen j was only slightly greater than for the child and the doses could be considered equivalent. ' The gamma and beta dose factors Ki vy, Li vy, Mi vy, and Ni vv in Attachment 12 were obtained by performing a units conversion of the ayymydate dose factors from Table B-1, Regulatory Guide 1.109, Rev.1, to mrem /yr per Ci/m3 or mrad /yr per Ci/m3, and multiplying by the .; ventilation vent site boundary X/Q value of 6.0E-05 sec/m3. The same approach was used to calculate the gamma and beta dose factors Kipy, Lipy, Mipy, and Nipv in Attachment 12, using the process vent site boundary X/Q value of 1.0E-06 sec/m3 t Inhalation pathway dose factors P i vy and Pipv in Attachment 12 were calculated using the ' equation: P; = K'(BR) DFA;(x/Q)(mrem /yr per Curie /sec) (28-1) where: - K' = a constant of unit conversion, IE+12 pCi/Ci l BR 3
= the breathing rate of the child age group,3700 m /yr, from Table E-5, Regulatory Guide 1.109, Rev.1 i 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.1 X/Q = the ventilation vent site boundary X/Q,6.0E-5 sec/m3, or the process vent site ;
boundary %/Q,1.0E-06 sec/m3, as appropriate 4
! VIRGINIA VPAP-2103 POWER ' REVISION 7 - !. PAGE 146 OF 156
- ATTACHMENT 28 i ,
(Page 6 of 8) Surry Meteorological, Liquid, and Gaseous Pathway Analysis ! Step 6.3.4.a., requires that the dose to the maximum exposed member of the public from 1133,
- 1133, tritium, and from all radionuclides in particulate form with half-lives greater than 8 days .
i be less than or equal to the specified limits. Dose calculations were performed for an exposed member of the public within site boundary unrestricted areas, discharge canal bank, and to an exposed member of the public beyond site boundary at real residences with the largest %/Q values using the NRC computer code GASPAR. Doses to members of the publ'ic 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 public within site boundary would be using the discharge canal bank for fishing a maximum of 160 hours per year. De maximum annual X/Q at this location was deternuned to be 7.8E-05 sec/m3 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. De 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-milk pathway was greater than : the dose to the member of the public within site boundary, nearest residence, vegetable or meat pathways. Therefore, the maximum exposed member of the public was determined to be the infant, exposed through the grass-cow-milk pathway, critical organ thyroid, at a location 5150 meters S sector. The only other pathway existing at this location for the infant is nhalation. 6 4 1
VIRGINIA "' s VPAP-2103 l POWER REVISION 7 i PAGE 147 OF 156 ATTACHMENT 28 (Page 7 of 8) Surry Meteorological, Liquid, and Gaseous Pathway Analysis The RM iyv and RMipv dose factors, except for tritium,in Attachment 18 were calculated by multiplying the appropriate D/Q value with the following equation: RM; = K'OF nap)pm (r) M; ) ff (1 - fps f ) e-At, -Ah Ps 4 e (28-2)
. P s _
where: - K' = a constant of unit conversion, IE+12 pCi/Ci Qp = cow's consumption rate, 50, in Kg/ day (wet weight) Unp = infant milk consumption rate, 330, liters /yr Yp = agricultural productivity by unit area of pasture feed grass,0.7 Kg/m 2 ) Ys = agricultural productivity by unit area of stored feed,2.0, in Kg/m2
~
Fm = stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev.I r = fraction of deposited activity retained on cow's feed grass,1.0 for radioiodine, 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 Ai = decay constant for the ith radionuclide, in sec-1, from Table ofIsotopes, Lederer, Hollander, and Perlman, sixth Edition. Aw = decay constant for removal of activityofleaf 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,1.73405, in seconds th = transport time from pasture, to harvest, to cow, to milk, to receptor,7.78E406, in seconds fp = fraction of year that cow is on pasture,0.67 (dimensionless),7.78E+06 in seconds
=
f fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensionless Parameters used above were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev.l.
, - - =' '" ~
w
VPAP-2103 VIRGINIA
- POWER REVISION 7 PAGE 148 OF 156 ATTACHMENT 28 (Page 8 of 8)
Surry Meteorological, Lipdd, and Gaseous Pathway Analysis . Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used: R H3 = K'K'"F,Qp U,p(DFL Hs ) 0.75(0.5/H) %/Q -(28-3) where: K'" = a constant of unit conversion IE403 gm/kg H = absolute humidity of the atmosphere,8.0, gm/m3 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 UQ = the annual average concentration at a location 5150 meters S sector,3.0E-07 sec/m3 for ventilation vent releases, and 1.3E-07 sec/m3 for the process vent releases Other parameters have been previously defined. The inhalation pathway dose factors RIivy and RIjp v in Attachment 18 were calculated using , the following equation: RI. = K'(BR) DFA;(x/Q) (mrem /yr per Curie /sec) 3 (28-4) where: K' = a constant of unit conversion, IE+12 pCi/Ci BR = breathing rate of the infant age group,1400 m3/yr, from Table E-5, Regulatory Guide 1.109, Rev.1 DFAi = thyroid organ inhalation dose factor for infant age group for the ith radionuclide, in mrem /pCi, from Table E-10, Regulatory Gliide 1.109, Rev.1 UQ = ventilation vent UQ,3.0E-07 sec/m3, or the process vent site boundary UQ, 1.3E-07 sec/m3, at a location 5150 meters S sector. J
VIRGINIA VPAP-2103 , .< POWER REVISION 7 PAGE 149 OF 156 ATTACHMENT 29 l (Page 1 of 8)
' North Anna Meteorological, Liquid, and Gaseous Pathway Analysis -
1.0 METEOROLOGICAL ANALYSIS 1.1 Purpose j The pu'rpose 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 to perform a dose pathway analysis to determir.e 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 13 and 19. 1.2 Meteorological Data, Parameten, and Methodology Onsite meteorological data for the period January 1,1981, through December 31,1981, were used in calculations. These 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 . ATtS8.9ft.28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were based on ATt38.9tt.28.2ft 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 airflow model implementing the assumptions outlined in Section C (excluding C1a and Clb) of Regulatory Guide 1.111,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."
The open terrain adjustment factors were applied to the %/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 release calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area. r
VIRGINIA VPAP-2103 POWER
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North Anna Meteorological / Liquid,and Gaseous Pathway Analysis . 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 plurrie exit velocity of 100 ft/sec. Ventilation vent, and vent releases other than from the
~
process vent, are enaMered ground level as specified in Regulatory Guide 1.111 for release points less than the height of adjacent solid structures. Terrain elevations were obtained from North Anna Power Station Units 1 and 2,. Virginia Electric and Power Company Final Safety Analysis Report Table llc.2-8. o l 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 Nonh Anna Power Station Annual Environmental Survey Data for 1981. %/Q values were also calculated for the nearest lake shorehne 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 releases and containment purges. However, these releases are considered long term for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past reinse reports. - Therefore, the use of annual average concentrations is appropriate accordi.n g to NUREG-0133. The X/Q and D/Q values calculated from 1981 meteorological data are :omparable to the values presented in the North Anna Power Station UFSAR. i 1.3 Results The X/Q value that resulted in the maximum total bodh, skin and inhalation exposure for ventilation vent releases was 9.3E-06 sec/m3 at a site boundary location 1416 meters SE sector. For process vent releases, the site boundary X/Q value was 1.2E-06 sec/m3 at a location 1513 meters S sector. The shoreline %/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 1.0E-04 sec/m3 at a location 274 meters NNE sector. The , shoreline X/Q value for process vent was 2.7E-06 sec/m3 at a location 274 meters NNE sector. i I
1
, VIRGINIA -
VPAP-2103
.s POWER )
REVISION 7 i PAGE 151 OF 156 l i ATTACHMENT 29
- (Page 3 of 8) 1 North Anna Meteorological, Liquid, and Gaseous Pathway Analysis ,
Pathway analysis indicated that the maximum exposure fmm I-131,1133, and from all radionuclides in particulate form with half-lives greater than 8 days was through the grass-cow-milk pathway. He D/Q value from ventilation vent releases resulting in' the maximum ' exposure was 2.4E-09 per m2 at a location 3250 meters N sector. For processvent releases, the i D/Q value was 1.1E4)9 per m2 at a location 3250 meters N sector. For tritium, the %/Q value from ventilation vent releases resulting in the maximum exposure for the milk pathway was , 7.2E-07 sec/m3, and 3.9E-07 sec/m3 for process vent releases at a location 3250 meters N sector. 2.0 . LIQUID ATHWAY 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. He analysis ) includes a determination of most restrictive liquid pathway, most restrictive age group, and
. critical organ. This analysis is required for Subsection 6.2. I 2.2 Data, Parameters, and Methodology Radioactive liquid effluent release data for the years 1979,1980, and 1981 were compiled from the North Anna Power Station semi annual effluent release reports. ' Die 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.
Re-concentration of effluents using the small lake connected to larger water body model was selected with the appropriate parameters determined from Table 3.5.3.5, Design Data for Reservoir and Waste Heat Treatment Facility frorii Virginia Electric and Power Company, l Applicant's Environmental Report Supplement, North Anna Power Station, Units 1 and 2, March 15,1972. Dilution factors for aquatic foods, shoreline, and drinking water were set to one. Transit time calculations were based on average flow rates. All other parameters were defaults selected by the LADTAP computer code.
VIRGINIA VPAP-2103 POWER
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North Anna Meteorological,. Liquid,and Gaseous Pathway Analysis 2.3 Results
- For each year, the fish pathway resulted in the largest dose. The critical organ each year was
~
the liver, and the adult and teenage age groups received the same organ dose. However, since the adult total body dose was greater than the teen total body dose for each year, the adult was selected as the most restrictive age group. Dose factors in Attachment 7 are for the maximum exposed member of the public, an adult, with the critical organ being the liver. 3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose A gaseous effluent pathway analysis was performed to determine the location that would result in the maximum doses due to noble gases for use in demonstrating compliance with 6.3.1.a. and 6.3.3.a. The analysis also included a determination of the criticai pathway, location of maximum exposed member of the public, and the critical organ for the maximum dose due to 1131, 1133, tritium, and for all radionuclides in particulate form' with half-lives greater than 8 days for use in demonstrating compliance with requirements in 6.3.4.a.1. In addition, the analysis included a determination of the critical pathway, maximum age group, and sector location of an exposed individual through the inhalation pathway from 1131, 1333, tritium, and particulates with half-lives greater than 8 days to demonstrate compliance with 6.3.1.a.. 3.2 Data, Parameters, and Methodology Annual average %/Q values were calculated, as described in Section I of this attachment, for the nearest site boundary in each directional sector and at other critical locations beyond the site boundary. The largest %/Q value was determined to be 9.3E-M sec/m3 at site boundary for ventilation vent releases at a location 1416 meters SE direction, and 1.2E-06 sec/m3 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 beta radiation due to noble gases, would be at these site boundary locations. The doses from both release points are summed in calculations to calculate total maximum dose. I J
t VIRGINIA VPAP-2103 a POWER REVISION 7 PAGE 153 OF 156 ATTACHMENT 29 (Page 5 of 8) North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the kx:ations and %/Q values determined for maximum noble gas doses can be used to determine the maximum' dose from 1131, 1133, tritium, and for all radionuclides in particulate form .with half-lives greater than 8 days for the inhalation pathway. De NRC computer code GASPAR, " Evaluation of Atmospheric Releases," Revised.8/19/17,
- was run using 1979,1980 and 1981 North Anna Power Station Gaseous Effluent Release Report data. Doses from1131, 1133, tritium, and partim1=*as for the inhalation pathway were i calculated using the 9.3E-06 sec/m3 site boundary %/Q. Except for the source term data and the X/Q value, computer code default parameters were used. Results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway, l i
The gamma and beta dose factors Ki vy, Li vy, Mi vy, and Njyy in Attachment 13 were obtained I by performing a units conversion of the appropriate dose factors from Table B-1, Regulatory Guide 1.109, Rev.1, to mrem /yr per Ci/m3 or mrad /yr per Ci/m3, and multiplying by the
-l ventilation vent site boundary %/Q value of 9.3E-06 sec/m3. He same approach was used in l
calculating the gamma and beta dose factors Kipy, Lipy, M ip y, and Nipv in Attachment 13 using l the process vent site boundary %/Q value of 1.2E 06 sec/m3 The inhalation pathway dose factors Pivy and Pipv in Attachment 13 were calculated using the following equation- i l P; = K'(BR)DFA;(x/Q) (mmm/yrperCurie/sec) (29-1) l where: - K' = a constant of unit conversion, IE+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, Rer.ilatory Guide 1.109, Rev. I
%/Q =
the ventilation vent site bounduy %/Q,9.3E-06 sec/m3, or the process vent site boundary %/Q,1.2E-06 sec/m3, as appropriate.
1 VIRGINIA VPAP-2103 POWER REVISION 7 PAGE 154 OF 156 A'ITACHMENT 29 (Page 6 of 8) North Anna Meteorological,. Liquid,and Gaseous Pathway Analysis I Step 6.3.4.a., requires that the dose to the maximum exposed member of the public from I131, 1133, 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 performed for an exposed member of the public within site boundary umestricted areas, and to an exposed member of the public beyond site boundary at locations identified in the North Anna Power Station Annual Environmental Survey Data for 1981. 2 , . , l It was determined that the member of the public'within site boundary would be using Lake Anna for recreational purposes a maximum of 2232 hours per year. It is assumed that this member of the public would be located the entire 2232 hours at the lake shoreline with the largest annual X/Q of 1.0E-04 at a location 274 meters NNE sector, ne NRC computer code GASPAR was run to calculate the inhalation dose to this individual. The GASPAR results were corrected for the fractional year the member of the public would be using the lake. Using the NRC computer code GASPAR and annual average X/Q and D/Q values obtained as
~
described in Section 1 of this attachment, the member of the public receiving the largest dose beyond site boundary was determined to be located 3250 meters N sector. The critical pathway was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid. For each year 1979,1980, and 1981 the dose to the infant from the grass-cow-milk pathway was greater than the dose to the member of the public within site boundary. Therefore, the maximum exposed member of the public was determined to be the infant, exposed through the grass-cow-milk pathway, critical organ thyroid, at a location 3250 meters N sector. Pathway analysis results indicate that existing pathways, including ground and inhalation, within five miles of North Anna Power Station, yield R dose i factors less than those determined for the cow milk pathway. Although the cow-milk pathway does not exist within five miles of the Station, NUREG-0133 requires the use of cow-milk R idose factors since these values result in the most limiting doses. There is no requirement to include the other pathways. [ Commitment 3.2.3]
-- - _ -. ___-_ __- __- _ _ _ _ _ - - - _ _ _ _ - - ---_- a
I VIRGINIA VPAP-2103
- O. POWER REVISION 7 PAGE 155 OF 156 A'ITACHMENT 29 (Page 7 of 8)
North Anna Meteorological, Liquid, and Gaseous Pathway Analysis The RM ivv and RMipv dose factors, except for tritium, in Attachment 19 were calculated by multiplying the appropriate D/Q value with the following equation: . R.M; = K' RP pm (r) M; ) s 0 p s) e4t f 4 (29-2) 4 . P s _ where: A K' = a constant of unit conversion, IE+12 pCi/Ci QF = cow's consumption rate,50, in Kg/ day (wet weight) Unp = infant milk consumption rate,330 liters /yr Yp = agricultural productivity by unit area of pasture feed grass,0.7 Kg/m2 Ys = agricultural productivity by unit area of stored feed,2.0, in Kg/m2 , Fm = stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev.1 - i r = fraction of deposited activity retained on cow's feed grass,1.0 for radioiodine, and 0.2 for particulates DI-Li= thyroid ingestion dose factor for the ith radionuclide for the infant, in mrem /pO, from Table E-14, Regulatory Guide 1.109, Rev.1 Ai = decay constant for the ith radionuclide, in sec-1, from Table of Isotopes, Lederer, Hollander, and Perlman, sixth Edition. Aw = decay constant for removal of activity ofleaf and plant surfaces by weathering, 5.73E-07 sec-1 (corresponding to a 14 day half-life) 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,7.78E46, in seconds fp = fraction of year that cow is on pasture,0.58 (dimensionless),7 months per year from NUREG-0597 fs = fraction of cow feed that is pasture grass while cow is on pasture,1.0, dimensionless Parameters used in the above equation were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev.l. N ;
VIRGINIA VPAP-2103
., POWER REVISION 7 -*
PAGE 156 OF 156
. ATTACHMENT 29 (Page 8 of 8)
North Anna Meteorological, Liquid,and Gaseous Pathway Analysis Since the concentration of tritium in milk is based on the airborne concentration rather than the
~~
deposition, the following equation is used: H3
- m OFU,(DFLH3 ) 0.75(0.5/H)
%/Q (29-3) where: t K'" = a constant of unit conversion 1E+03 gm/kg H = absolute humidity of the atmosphere,8.0, gnVm3 0
0.75 = the fraction of total feed that is water
.4 0.5 = the ratio of the specific activity of the feed grass to the atmospheric water X/Q = the annual average concentration at a location 3250 meters N sector,7.2E-07 sec/m3 for ventilation vent releases, and 3.9E-07 sec/m3 for the process vent releases .
f Other parameters have been previously defined. s
- , . .n.. . v}}