ML20069F835
| ML20069F835 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 03/01/1983 |
| From: | WISCONSIN PUBLIC SERVICE CORP. |
| To: | |
| Shared Package | |
| ML111671157 | List: |
| References | |
| PROC-830301-01, NUDOCS 8303240102 | |
| Download: ML20069F835 (35) | |
Text
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. I!EVIS O 3-01-83 9 a p ,
4 . El[RCU:CY Pl.All IMPLETEllTIllG PROCEdF.IS
-Index--
Procr:dare j TITLE REVISIO.! ' DATl EP-AD-1 Plant Emergency Organization C- 01-03-33 EP-AD-2. Eraargency Class . Determination' E' 10-13-82 Unusual Event A 1 2 81 EPiiD-3= Alert A 1 2-21'-81' EP-A9-4 Site Emergency A 1 2-21.-81
;EP-AD General Emergancy A 12-21-81 EP- AD-6.-
EP-AD-7 Notification of Unusual Event . E 10-13-32 EP-AD-8 llotification of Alert' E 10-13 . EP-AD-9 Ilotification of Site Emergency ~E 10-13-82 EP-AD-10 Hotification of General Emergency E= 10-13-82 Emergency Radiation Controls A 12-21-Si Y EP-AD-11
- - EP-AD-12 Personnel Asset 61y and Accountability C 10-13-82 DELETED-EP-AD-13A Limited Area Evacuation Emergency Asserbly/ Evacuation DELETED.
EP-AD-133 Site Evacuation DELETED
- EP-AD-13C EP-AD-14 Search and Rescuo 12-21-0i-EP-AD-15 Recovery Planning 10-21-61 EP-AD-16 Personnel Injury or Vehicle- Accidents 12-21-61 EP-AD-17 Communications C 10-13-S?
EP-AD-18 Administration of lodine Blocki g: Agents 12-21-81 EP-ENV-1 Environmental Team Organization A 12-21-S1 EP-EtiV-2 Site Access Eacility (SAF) Ac'tivation A 12-21-Si 9 8303240102 830321 PDR ADOCK 05000305 F PDR
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REVISED- 3-01-83:
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Et4ERGE!!CYJPLAll Il4PLEI1EllTDIC' PROCEDURES
-Index-(cont'd)
REVISIO!! ~ DATE' Procedure li TITLE EP-E!!V-3A - Environuental- Protection' Director - F 10-13-82
' Actions and Directions.
'C 21-82 EP-E!!V-33 Envirannental lionitoring Team Actions C 03-01-83~
EP-EllV-3C . Primarf Detenaination of X/Q
~
B 110-13-82
. EP-E!!Y-30 - Alternate Dateraination ofLX/Q C_ 03-01-83 EP-EllV-3E 14anual Environ.1 ental Dose Projection Calculations A 03-01-83 EP-EllV-3F Protective Action Recodmendations -
B 05-21-82 EP-E!!Y-4A Saaple Acquisition, Portable Instrumentation Use i; B 05-21-82 EP-E!1V-4B Sample Acquisition,, Air Monitoring Devices - (. N- ~EP-E!!V-4C Sample Acquisition, Environr,cntal .B 05-21-82 Sanpling Techniques A 1 2-21-81 EP-EllV-5A - LCS-1 Operation A ~12-21-81 EP-EllV-5B 14S-3 Operation B- 01-22-82
. EP-E!JV-5C SAli II Operation A 12-21-81 EP-EllV-5D PAC-4G Operation 8-19-81 EP-E!1V-5E Reuter-Stokes Oparation'
- EP-EllV-6 Data Analysis, Dose Projections and Protective DELETED Action Recomaendations EP-EllV-6A Relocation of Site Access Facility 12-21-81 (1.
l abitabili ty) A 11-24-82 EP-EtiV-6B : SAF Environnantal Sample Analysis Relocation-A '7-02-82 EP-E!!V-7 Site Access Facility Comunications 12-21-81 > EP-EllV-8 Total Population Dose Estimate l .-(- ................---
U M A AS. T T M F 4 % V Page-3'of 5 .
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' -Index--
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REY SIO!. DATE Procedure #. UTITLE F 10-13-82 3EP-EOF-1
~ Corporate Staf f Emergency Response Organization:
C- 02-18-82 EP-EOF Emergency' Operations Facili ty- (E0F) Activation E. 06-18-82 EP-EOF-3
. Corporate' Response :to an Unusual Event
'F- 10-13-82 EP-EOF Corporate Response to an Alert-F. 10-13-82 EP-EOF-5 Corporate Response to a Site' Emergency F 10-13-82 EP-EOF-6 Corporate Response to'a General Emergency D- .05-21-82 EP-E0F-7 Communications and Documentation B del.ETED
.EP-E0F-8 Relocation of EOF D 10-13-82
-EP-EOF Interface with Support Organizations sh A 03-83 Control Room Emergency Organization ^
EP-0P-1 B 1-03.-83 ~ EP-0P-2 Emergency Activation of Control Room A 1-03-83 ii EP-0P-3 Control Room Comunications= A 1-15-82 EP-0SF-1 . Operational Support Facility (OSF) Organization A 05-21-82 EP-OSF-2 OSF Activation A 1-15-82 Work Requests During an- Energency ,
.EP-OSF-3 A 16-82 EP-OSF-4 OSF Conmunications
[. .................. B 21-81 Radiation Emergency Tean (RET) Organization EP-RET-1 f- B 12-21-31
- EP-RET-2 Inplant RET l , ,
~3-
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, . . . _ _ a
~ ~
.REVISCU 3-01 '
3Pags 4"of!5- -
. y3 -- , f-EMERGE)'CY PLAll -litPLEMEtlTI!!G PROCEDURES:-
~
.-liidex- . .
.(cont'd)
'REVISIO;l! DATE; r # TITLE' Procedn'e
/ ?B 21-82 EP-RET-2A -RP0/RAF Astivation ,
.C 03-01-83
-EP-RET-2B Gaseous F.f fluent Shap1'e and A'nalysis B . DELETED EP-RET-2C; Containment Air Sampling and Analysis _
A 12-21-81 EP-RET Emergency Radiation Entrys Controls;andi Impicaentation' 12-R1-81'
-EP-RET-2E 'llandling of injured Personnel.
A- 3-19-S? ' EP-RET-2F Personnb1 Decontanination-D 12-21-S1' EP-RET-3 Emergency Chcalst-y Tcaa - A = 12-21 -81 ' EP-RET- 3A Liquid Efficent Sanple and Analysis A 12-21-81 EP-RET-3B ' Post-Accident ReactorcCoolant. Interim Sampli ng -Proceduro L EP-RET-3C - Post Accident Oieration i of the'lligh Radiatisn 05-18 Sampic Roca
~ Contain.nent Air Sanpling Analysis Using CASS 11-01-82
-EP-RET-3D: .
B L12-21-81 EP-RET-4 Site RET-A- DELETED E0F Radiological tionitoring EP-RET-4A r, ~ 10-21-81 EP-RET-4B" Radiological Controls at1 Sitc Access facility (SAF) 12-21-81 EP-RET-4C Site Radiological lionitoring A 12-21-81 EP-RET-5: Plume Projections , A 12-21-B1 EP-RET-5A Pluce Projections (Backup _ttethod) A = 12-21 EP-RET-6 Dose Projection-12-21-S1. _ EP-RET-7 RAF/RPO Coamunications 12-21-81 EP-RET-8' Contamination Control at the Two Rivers Community llospital .
+ o '
, : REVISES 31-83
, Pago,5'of*5
EMERGE!!CY PLAT! IMPLEllEllTIt!G PROCEDUP.Q
. -Index-(cont'd)
REVISION .DATE-
~ Procedure il TITLE Security Organization 12-21-81
;EP SEC-1 Security Force Response to Emergencies C 03-01-83
-EP-SEC-2 Manual' Activation of Emergency Sirens DELETED l-29-82 EP-SEC-2(a)
Personnel Accountability -(Initial . and i aintaining) C; .'10-13-82 EP-SEC-3 Dosimetry . Issue at SAF '12-21-81 EP-SEC-4 I Technical Support ~ Center (TSC) Orgsnf zation 12 81 EP-TSC-1 . TSC Activation B 05-21-82' EP-TSC-2. Plant Status Procedure A. 02-18-82 EP-TSC-3 , Emergency Design Change, Major Equip.nent Re;; air 12-21-81 EP-TSC-4 12-21-81 EP-TSC-5 TSC Communications Assessment of Reactor Core Damage 10-13-82 EP-T SC-6 9 6 e J \ 5
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el I,TITLEi:Prinary Detebination'of X/Q y o-lK,.eudumeef!!aclear? Power Plant ' s
.g .-{g;;pp g.eteorelogical Data)~
e ~' EMERGEl!CY PL5ti:1!;PLEMEllTi!!G PRCCEDURE 'l . .. . 1, . lTDATE: MAR' O I 1933 i PAGE 1 of ^6 ~ 3 7% r-- / - 3 . l. m i Y EWED !!W
; tj APPROVED'-BY h2/[q j
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~
-l.0' APPLICABILITY' This procedure.is used to estimate the atmospheric dispersion factor-(X/Q) using Keuanace lluclear Power Plant 14eteorological Data.
2.0 PRECAUTIO!!S 2.1 As a nininun, the following meteorological parameters frca the Ke_waunce
-Nuclear Power Plant Ibteorological,towce:are required to use this.
procedure. a.10ne wind speed indication (55 meter elevation or 11 neter elevation).
- b. One wind direction ~ indication (55 meter elevatTiin or 11 roter
' ~-
el evation) . _
- I c. Vertical Temperature Difference indication (Delta T between 11 meters and 55 reters).
If this minimuq data is not. available,. use EP-ENV-3D, Backup-Determination of X/Q (Green Bay Meteorological Data), 'to# determine atmospheric dispersion. 2.24 14eteorological . data mustL be re-evaluated every 30 ninutes or whenever significant changes occur, toidetermine if X/Q must be recalculated.
-2.3 When detemining X/Q or.Xu/Q for a' point of -. interest that falls between two isopleths 'on;an overlay, select the value of X/Q or Xu/Q that corresponds to the'i.sopleth lying closest to the: plume centerline.
- 1f a point' of interest lays between an isopleth and plure ccoterl,ine, 4
. select the value of X/Q or Xu/Q that corresponds to the nearest mile-marker on the centerline.
2.4 The WIND DIRECTIO!! CIRCLE on the Base Map may appear to the. user to. be shifted'180' degrees. This is.not an~ error. The WIND DIRECTION CIRCLE reflects the direct use ofTnTdirection information. 3.0 ' REFERENCES l URC Regulatory Guide 1.145, Atmospheric Dispersion liodels for Potential- ' 3.1, Accident Consequence Assessments at Nuclear Power Plants, August 1979
.( 3.2 llRC Regulatory Guide 1.23, Rev 1 (Proposed), Meteorological Programs In Support of Nuclear Power Plants, September 1980.
EF-WM-It WISC0ilSI11 PUP.LIC SEi!V1CE CDP.PORAT10!! . I ~ fl0. ~
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I TITLE: . Prinary Detenination of X/Q. _ tewaunce fluclear Power Plant. (KDP lieteor', logical Data) l l p EMERGEljCY ;PLA!! IMPLEliEllTit!G'PROCEDU?.E l 1 DATE: Mif, 011983 i PAGE 2 of 6 I I _
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4.0 IllSTRUCTIO!!S 4.1 Record lieteorological Parameters Section I on Form EllV-3C.1, Meteorological Data Worksheet. 4.2 Detemine the ' stability class using the Vertical Temperature Difference (item I-E on Forn EllV-3C.1) and the table in Section II of form
. EllV-3C .1 ) ..
4.3 Detemine release elevation from Section III of Form E!.7-3C.1. , 4.4 For Elevated Releases _ conplete steps 4.4.1 through 4.4.8. If the relea:.e is ground Tevel, proceed to step 4.5. 4.4.1 Place the elevated overlay for the stability class determined
~
in step' 4.2 o,n the Base Map. 4.4.2 Align the centerline of the overlay with the actual wind direction value from WD55 (item I-A on Fom Ei!V-3C.1) on the Base Map Wind Direction Circle. NOTE: If WD55 value is not available, use WD11 value.
.4.4.3 Record points of interest in the path of the pit:me in column 1 on Fom ENV-3C.2 and record the corresponding sector in column 2. _
4.4.4 Determine the distance from the release point to each point'of interest and record in column 3 of. Fom EllV-3C.2 (Base Map Scale: 2 inches = 1 mile). 4.4.5 Record wind . speed US55 in column 4 of Form EllV-3C.2 (Wind Speed is the same. for all points of interest). HOTE: If WS55 is not availabic, use WS11 value. 4.4.6 Calculate impact time (IT) using the formula on Form EllV-3C.2 and' record in column 5. 4.4.7 Detemine X/Q for each point of interest from the overlay and record in column 7 of Form ENV-3C.2. 4.4.8 Proceed to step 4.6 (step 4.5 is not required for elevated releases). [ . i
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.I -. .
.- .=- M ewau' nee'!!uclear Po.cr Plant 1 ~
l- TITLE: .Prinary Deteminention of X/Q 11' (K!!PP i'.eteorolocical . Data) c t E!'EPCE!:CY Pl.A!! 1:1PLE!'E!! Tit G P:lCCEDURE 1. _ . .
.. l
,l'DATE: IAAR 011333 1:' PACE 3 of 6'
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-4.5. For Ground Level Releases, ' complete steps 4.5.1.through .4.5.8 4.5.1 Place the ground icvel coverlay for thc lstabili ty class. determined in step 4.2 on the Base !!ap.
4.5.2 Align the centerline. of the overlay wi th. the actual wind direction -value from UD11 (itea I-B on Form E!!V-3C.1) on - the Base liap . Hind Direction . Circle.
!!OTE: If HD11-is not availabic, use UD55 value.
4.5.3 Record points of interest in the path of the plure in coluan 1 of Forn EllV-3C.2 and record the correspondir,3 sector in column 2 4.5.4 Determine the distance from the release poir.t to each point of interest and record in colunn 3 of Fora EllV-3C.2 (Base 11ap Scale: 2 inches = 1 mile). ,
. 4.5.5 Record wind speed US11 in column 4 of Fona E!!V-30.2 (Wind Speed .is the same for all ~ points of interest).
[:j . Il0TE: If US11 is not available, use US55 value'.
~4.5.6 Calculate. impact ~ time (IT) using the formula on Form EllV-3C.2 and record in column 5.
- 4.5.7 -Determine Xu/Q for. cach point of interest' from the overlay and-
~
record in column 6 of Form EllV-3C.2.
-4.5.8 Calculate X/Q for each point:of interest using the formula on Form EllV-3C.2 and record in column 7.
'4.6 Detenaine if lake breezc exists using Fora EllV-3C.2. -If. lake breeze conditions exist, implement special field monitoring in accordance with
. EP-ENY-3A, section 6.0.
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EP-E!N-3C - pg g W9p F0P,14 E!W-3C.1 i. 11ETEOROLC31 CAL DATA UORKSHEET DATE Tl!4E
.I. - Meteorological Parameters Pa rane ter - Paranster Parcaenter Description' Hate Indication A. Wind' Direction at 55 aeter level WD55 Degrees B. Wind Direction at 11 o'.eter level WD11 . Degrees C. Wind speed at 55 meter level US55 mph x 0.447 =- m/sec D. Wind speed at 11 mater level WS11 mph x 0.447 = m/sec E. Vertical Temperature Dif ference VTD 'F 4
11.. Stability Class Use belon' table and VTD to detennine stability class.
-{ -
VTD ( 'F ) S_tabil ity- Cl ass VTD > 1.5 A 1.5 > VTD T 1.3- B 1.3 >.VTD T 1.2 .C 1.2 > YTD T '0.4 0 0.4 > VTD T -1.2 E
- 1.2 > VTD T -3.2 F
-- 3.2 > VTD ~ G t
L . STABILITY CLASS r
. III. Release Elevation
~ An Elevated release must meet all of the beloa criteria, otherwise the release is considered Ground Level.
l a.' Primary to Secondary leak is in progress. ._
- b. Release is from Steam Generator Safety Valves, Stean Generator Powr Operated 9
. Relief Yalve or Auxiliary Feed Pump Turbine Exhaust.
- c. Wind speed is less than im/sec.
l
- d. Stability class is A, B, C or D.
l ( Elevated Ground level b l o e rv- 9
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' EP-E!!V-3C I:,: ' M0R 0
.' . Pag 9 5 $?8$t
.+
- F0PJ1 EIN-3C.2 RELEASE UORKSilEETJ DATE TIME
^
l1 2
.3 i ,
s p 1
. (D) -
-(WS) . .. (TT)*'
Point of . Distance Wind Speed . Impact Time. Xu/Q** X/Q***. (neters-2 Interest Sector. (miles) (meters /sec)~ (minutes) (sec/ meters 3)- w.
<( .
f i
-
- IT = D/WS x 27
** N/A for Elevated Release (Xu/Q)
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*** When calculating for Ground t.evel Release: X/Q = W5 e
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y 2 - I;P EUV-3C.
- i:!AR 0 i /883 Page 6 of 6
, l F0PJ4 Et!V-3C.3 ' .
_ (? '~ U;
. LAKE BREE2E: EFFECT t!0P.KSilEET-
. DATE tit 4E I. Is local wind: direction (UD11 from Form hD.1lor WD55 if UD11;is not available) between 20and 170' clockwise?
Ho --t!o lake . breeze ef fect Yes - P'roceed .t:0_ Step II~ , II. ' Call Green Bay National lleather Station and 'get wind direction in' degrees. li -(Phone Humber Wind Direction __ i III. Is Green Bay wind direction between 210* and 330* clockwise? l No
.No lake breeze of fect .
Yes' - Lake breeze ef fect M l - (
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hIl5UUlG@ATVtWE16 NWermaamanur -- --~T wo---~ - l Kewaunec !!uclear Power Plant l TITLE: llanual Environmental Dose
' ' Projection Calculations 1
~ E!!ERCE!!CY PLAN IMPLEMENTitlG PROCEDURE I I l DATE: 1 of'8
. MAR 011983 lPAGE
- EVIEWED BY [ l s MV&. '
APPROVED BY Uf ad
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1.0 APPLICABILITY This procedure will be utilized by the Environmental Protection Director during any incident that involves a significant release of radioactive materials to the en/ironment, for the purpose of projecting a radiological dose impact. 2.0 PRECAUTI0lls .
. 2.1 Ensure all data on the forms of this procedure is accurately recorded.
2.2 Check all calculations for accuracy. 3.0 REFEREllCES 3.1 U.S. IIRC Regulatory Guide 1.109, Calculation of Annual Doses to 11an ( from Routine Release of Reactor Ef fluents _for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1, Revision 1, October 1977. 3.2 U.S. EPA, Manual of Protective Action Guides and Protective Actions for !!uclear Incidents, EPA-520/1-75-001, September 1975. Appendix 0 Technical Bases for Methods the Estimate the Projected Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to Airborne Radioiodines and Radioactive Noble Gases. 4.0 INSTRUCTIONS , 4.1 Whole Body Dose Projection Estimate If the source term is identified by sample results which quantifies specific nuclide content, then a conservative whole body dose estimate may be calculated using fonn ENY-3E.1, Estimated Whole Body Dose Calculation Worksheet. 4.1.1 Acquire the data needed for Section I of Fom EllV-3E.1 from the Radiation Protection Director (RPD) or Tech Support Center Director (TSCD).
. NOTE: Data Heeded: Release rate of Noble gas in (Ci/sec),
actual or estimated release duration, and X/Q from EP-EIN-3C or 3D.
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.1ITISC0llSIll,PUBL'IC SEliVICE CORPORATI0tl. liti0i I
. EP-E!!Vl 3E ' ~
+ Kewau'nce !!uclear Power Plant . ,I TITLE: 'anual Environmental Dose-1 Projection Calculations ~
EliERGEllCY--PLA!1 IMPLEllEllTit!G PROCEDURE 'l . I
'l DATE: Mi?. 'O 11983 1. PAGE 2 of 8
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.4 '1.2 ~ Calculate the llhole Body Dose Projecticn Estimate usi ng' Section II -
- of Fom E!!V-3E.1 and the following equation:
~
'D(REll)- = X/Q(Sec/m3) x Q(Ci/Sec) x T(hrs) x DF(REM
~
~
- n3) ct - prs where:
D = projected whole body dose estimate;(REM)
'X/Q = Atmospheric dispersion coefficier.t determined on-Fona EIN-3C.2 or ENC-3D.2 (Sec/m3}-
Q = lluclide equivalent release rate (Ci/Sec) frc7 EP-RET-5 KARL input sheet DF = Whole body dose conversion factor (REM - n3)
-(ti - brs)
NOTE: The whole body dose conversion facter is calculated from !!RC Regulatory Guide 1.109, Rev 1, dated October 1977. 4.1. 3 Field Sample Analysis Method (Marinelli Beaker of a Field { Drawn RAP Sample). - Complete Sections I & II of Form EIN-3E.2 and the following equation:
. D(REM) = FC x DF x T Wiere:
D = Is Dose in REM-DF = Whole body dose conversion factor (REM - I'.3)
. (ci - hrs)
T = Release duration in hours FC = Field Concentration'of specific nuclide in uC/cc as per Gamma Scan result NOTE: A separate Calculation Fom is required for each point of interest. . 4.2 Thyroid Dose Projection Estimate If an Iodine Source Tem is identified, calculate the projected or 1 estimated dose for each point of interest by using a' separate Fonn EIN-3E.2 and one of the following methods.
i l WISCOM51tl .PU3LIC SERVICE -CORPORATIO!! ! !!0. EP-EllV-3E o 1
*Kewauneciliucicar Power' Plant i . TITLE: lunual .Envi'ronmental Dose l' Projection Calculations '
* ' EMERGEt;CY PLA!!~ IMPLEMEllTillG PROCEDURE l- l l DATE: MA.c. 011993 i PAGE 3 of 8
'l 1
~4.' 2 .1 Inplant Sample Method Complete Section~1 of Form Et!V-3E.2 for each point of interest if the release rate of Iodine-131'(Ci/sec) is available for a thyroid dose projection estimate.
4.2.2 Field Sample Analysis Method Complete Section~ II of Fona E!!V-3E.3 fer each point of interest if the actual measured Iodine-131 airborne concentration (uC/cc) is available for;a thyroid dose projection estinate. This_ method is also to be used as a backup for the Inplant Staple Method. NOTE: This method assumes only Iodine-131- exposure, so it will only be an -approximation of the total Iodine dose. 4.3 Record all results.of Dose Projections by the method used on Fora EllV-3A and the field map. Also, report thi s' data to the Ra'd iological Protection Director, Emergency Response fianager, and To:hnical Support (.L Center Communicator. , 4.4 Proceed to procedure EP-ENV-3F, Protective Action Reconr.endation Deter-mination, to determine the appropriate Protective ' Action Recommendations. I e i e e b w --_ _ _ _ _ _ . _ _ ,
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'.Page 4 o'f ' 8 y. :.'
" FORM ENV-3E.1
~
ESTIMATEDWHOLE-BODYDOSE:CALCULAiIONWORKSHEET2 ,
.FOR ;>
SPECIFIC NOULT GAS RELEASE - b - DATE TIME- - LOCATION: Sector / Point 4 14 I. . Enter . data available; below: A. (Record in Column 1 of section II below) Noble Gas Nuclides release Lrates (Data is available from the'RPD or TSCD) ' 4 IB. -(Sec/m3)- - l X/Q as determined and recorded on Fom ENY-3C.2 or 3D.2 C. ~ (Data available from RPD.or TSCD) Release Duration (hrs)' II. Calculate dose for each nuclide and sum all ; doses to get total exposure dose by using the, formula below: Release - Rate (REM-m3) !' x.. Dose Factor: 4 t,i- br) = Dose-(REM)- ! -(Ci/Sec) x X/0(Sec/m3) x Release Duration (hrs) Nuclide,l. .
=
Kr-85 1 x x' x 1.84 i i ! Kr-85m- I x' .x' x 1 34 x 102 . t
'I Kr-87 I "x x x- 6.76 x 102 = ^
I x 1.6R x 103 n ! Kr-88 1 x x 4 .
'x- 3.36 x'101 '='
i Xc-133 i x x i Xc-133m I x x- x 2.87 x'101 =- I Xe-135 1 'x x x 2.06 x 102 =.
~
Xe-135m I x .x x 3.56 x1102 .. l i Signature of Completing TOTAL Wil0LE BODY ' l = Authority ana: Title (dignature) EXPOSURE DOSE L ' ( Ti +1 M ' ,
3 4 fr [g. y j N ;
" f unn 09 ?.:,63 3<?
* . 'Page'5.off83 * :{ ,,
LFORM ' ENY-3E.2- .
' FIELD SAMPLE ANALYSIS METHOD'0F KHOLE BODY' -TIME DOSE CALCULA :.
* . DATE
'l LOCATION:. Sector / Point E
-Section'I_'(Enter data. available -below) .
A. Record the. Field Conctnrrations . (Data is-:available of Gamma from 'RP0/RAF Scan or. Identified TSCD) Noble. Gases - in SectionJII, Column I.
- B. Release Duration (actual or ' estimated) by1 Section.II - Calculate doses for each nuclide 'and sum a11) doses :to get' total exposure dose using .the formula -below. .
Release . Fiel d Dose (REM-m3) Dose ' (RB4) Nuclide 'FactorJ(Gi-nr) Duration'(hrs) Concentration (uG/cc) = i x x 1.84-Kr-85 l
'= _
1
-x' 1.34 xr10% x _
Kr-85m: 'l
;y
' ==
I . ~ 6.76 x 102 x x- _ I Kr l '
=
.I 1.68 x 103- ~x' x
Kr-88 1
~=
3.36 x 101 x
.Xe-133 l' ac ac 2.87 i 101 x _
Xe-133m i -_ I J2 .06 x .102 x x Xe-135 !
-l x x 3.56'x:102 Xe-135m i TOTAL-WHOLE: ,
Signature -of Completi ng BODY DOSE ='
- { Signature)
Authority and Title
' lT' tl e)
A
l, 7 * ' ' QAD 011[8b 60
..: F0PJ4 ENV-3E.3
' ESTIMATED THYROID' DOSE PROJECTIOM CA'.CULATIO!!
. f' . '
LOCATIONi Sectdr/Pointi DATE TIME
~ I'. ' It! PLANT- SAMPLE METil0D . m
=A. . lodineil31 Release Ratds .(Ci/sec)
'B. .X/Q at the. point of interest from form ENY-3C.2 or-33.2
;(Sec/m3)
C. Release Duration (Data available from RPD or TSCD). - :(hrs))
.D. Calculated lodine-131 ' Concentration at the' point 'of~ interest.
Release Rate (Ci/Sec) x. X/Q(Sec/m3) = uC/cc of I-131-X '= uC/cc - of I-131 E. Determine Estimated Total ~ Thyroid Dose fr,oa FigJre EW-3E. Use the: Calculated Iodine-131 Concentration on the .X-axis ard go vertically up the graph to -intersect the appropriate Release Duration line, ther read of f
^ the Y-axis the Estimated Total . Thyroid Dose.
Calculated 1-131 Concentration vs. Release Duration => Total Thyroid' Dose uC/cc vs. hrs => REM y k F; ' Multiply Thyroid Dose (in REM) by:2 and make recomT.endation based en corrected ' thyroid dose. , ,
. Thyroid Dose (f'roa step "E") x 2 = Corrected Thyroid Dose-in REM. . REM x 2 = - REM NOTE: . EPA'Guideli.nes state that protective action recoacendations~ based on thyroid dose should use the dose;calculatef for children in the-af fected t.opulation.
i 9 4
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ESTIt1ATED TilYROID DOSE PROJECTIO1.CALCul.ATION [* II. FIELD SANPLE' ANALYSIS ttEi!!0D ,
. A .' - Field Saaple Analysis I-131' Concentration at the point of interest UC/cc-(hrs)
~
B. Release Duration L(Data available fros the RPD or TSCD)- C. Deten:iine Estimated Total Thyroid Dose fron Figure ENV-3E. Us? the field sanple' analysis I .131' concentration on the X-axis and go verti: ally up the graph to intersect the appropriate Release Duration line, then read off the. Y-axis the Estiaated Total Thyroid . Dose.
' Field Sample Analysis .
Iodine-131 Concentration vs. Release Duration => Total Thyroid Dose 9
.uC/cc vs. hrs => REli D.liultiply Thy'roid Dose (in RE!!)'by- 2.and nake recommendation based on corrected thyroid dose. '
' Thyroid Dose (froa step "E") x 2 = Corrected Thyroid Dose in RE!4.
REf4 x 2 = REl4
- ( .
NOTE: EPA Guidelines state that protective ' action re.commeridations b'ased - on thyroid dose should use the dose calculated for children in the af fected ' popula tion. C0l4PLETED BY LIi tle) 4 y 9 O 9 f f - -
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(1) Valuew are calculated usine,tlie old dose conversion for 1-131 6 The new constant in tiie reference is 1.5 x 10 f'.' It'o wever, the old conversion. 1.8 x 10 , is used for conservati. (2) To approximat e the child (6 r.ont hs to one year worst case) thyroid dese from the adult dose tault iply; it by a factor of 2 -
a l','I'A0!iSIt! P_UdLIC SERYlCE' CORPOP.ATIO'l .v
-I ' 1:0.
EP-EllV-3F REV . A -
' -.: . ,. l-f.edaunec !!uclear Power Plant Ll TlfLE: ' Protective Action Reccanentiatioe:
.I -"
C'.EP. gel!CY PLA!! -I:4?LE:4EllTING PROCEDURE . l . l i l'DATE: Mtf. 011303 l' PAGE 1.'of 6
-1 I -
EVID!ED 8Y ,)Q /d, / < -APPROVED. CY- ' utrvo
1.0 APPLICABILITY
' This procedure applies to all emergency situations when envirannental nanitoring and' dose assessment is necessary, and Environnental (1anitoring
- Teans have been dispatched.
2.0 ' PRECAUTIONS , L 2.1 Accurate recording of data acquired froa the Radiological Protection Director (RPD) or Environmental lionitoring Tea i (EMT) Coardinator is essential . 2.2 All conclusions dredn fron environ:nontal data nust be accurately docunanted. 3.0 REFEREtlCES
-k 3.1 EP-ENY-3C, Primary Datonnination of X/Q (KNPP 'eteorological Data) 3.2 EP-E!1Y-3D. Alternate Determination of X/Q (Green Bay !!steorological . Data) 3.3 EP-EIN-3E, Manua1' Environmental Dose Projection Calculations .
24.0 INSTRUCTIONS 4.1 Short Term Protective Action Determinations 4.1.1 Obtain the completed data sheets and worksheets of the following-procedures:
- a. Fora EIN-3A, Radiological Environaantal Monitoring and .
Sampling Worksheet.
- b. Fona E!N-3C.2 or 30.2, Release llorksheet .
4.1. 2 Compare the results of the dose projection calculations and measure.aents from EP-ENV-3E, Manual Dose Projection Calculations, for all points of interest to TABLES ENY-3F.1 as follods: TABLE ENV-3F.1: Take the. projected Dos:(s) and enter the chart aTThe appropriate level by projected Doses listed in the lef t hand colunn. Read across from the Doses and obtain the corres-ponding Recomnended Actions and co.nments.
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,, Kewaynee fluclear Power Plant l TITLE: Protective *: tion Reco.nmendatior
. . l EMERGEllCY PLAll !!iPLEMEllTI:lG PROCEDURE I I
- 1 DATE: ;.3.
. 0 1 1333 1 PAGE 2 of 6 I I 4.1.3 Record the impact times on the Field l'aps at the points of interes t.
~
Il0TE: Impact times c .1 be taken from Fara E!!V-3:.2 or ENY-3D.2. 4.1. 4 Evaluate the iapact time, pirat conditions (past, present and future), weat:wr conditions, and evacuction ti.ne estietes, and determine the nast beneficial and appet?riate Prctective Actions the public can take to redece tSeir expoIure. 4.1. 5 Verify previoas reconnendations, if any are still valid, for l any nes data that is now available. 4.1. 6 Reoort Protective Action P,ecomendations to the I.r.ergency Response Mana3er. 4.1.7 Repeat steps 4.1.2 through 4.1.6 as necessary as new infor.Jation is received froa the Environmental l'ani taring Teras. 4.1.8 Any changes in noteorological conditfor.s nust be factored through EP-E!;V-3C or 30, as applictble. ( 4.2 Long Term Protective Action Determinations
- 4. 2.1 Obtain data froa the results of gecund deposition samples reported by the Envirornental Consaltant.
4.2.2 Compare these results to Table E!!V-3~.2 to dateraine the appropriate Protective Action Recow.endations as follaws. Table ENV-3F.2: Section I, Part A: Compare the projected dose above ground, Ground Contanination level measurements, or exposure rates i rr.eter above ground and at or above tSase base limits proceed to Part B for the P.accranded Protective Actions. Section II, Part A: Evaluate the results of the Environmental Consultant. The results of a specific nuclide cancentration (1-131, Cs-137, Sr-90, and/or Sr-S3) a :1 the medf u, in which it was obtained are listed for conparison against the reported resul ts. For exaaple, if a milk analysis was re;orted by the Environnental Consultant at 0.012 oc/nl of I-131, proceed to the 1-131 colunn under the heading *:uclide. Then read to the right for the Action Levels and ccqcentrtio1 in 'iilk & Water ( Preventive or Emergency Levels, and cc para the levels to the
~
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5h WisC0f!$lil PUa!.1C SCRYldE CORPOP.AT10:1 - 130. EP-F'r/-3F
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Pr otec ti ve Ac ti o n ' P.cco aatend a ti o c., t - *' Kewonee scicar: Poacr P1 ant- . liTlTLE: I ~ ~ D DtGE!!CY PLAll:Iti?LD E!!fl':G PROCCOU3E .1 l . b l DATE: -1,mk 011303 i PAGE 3~of'6~ 1 l-t reported result. If the Reported result is less than the preventive icvel', no protective action 'is necess.try. . If the results are higher than the preventive or Eiaargen:y level, then proceed to the next.page and recorend the listed protective action recosaan:lations, as in the exanple, .the' recora:nndations under preventive' level .
~
4.2.3 P.ecord Protective - Action Reco.mnandations in EPD Log llook. 4.2.4 Report Protective Action Recofinen:!stions to.the Emergency llesponsa ilana3er. 4.2.5 P.cpeat steps 4.2.1 through 4.2.4 as necessary as ne,i infor.aation
-is received fro 6 the Environiuntal Consultant.
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- r. . nc-nv-w -
MAR 0.1:1983 .. , Pare 4.of 6-4 TABLE ENY-3F.1-
. RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLE BODY AND THYROID DOSE Projected Dose (Rem) to ' .
.Cbmments-Individual in General Public . Recommended Actions (a)
Previously recommended ! . Whole body <1 'No planned Protective Actions.(b) Protective Actions may State may issue an advisory to seek
.or shelter and await. further instructio,ns. ima reconsidered or terninated.-
Thyroid <5 - -
- Monitor environmental radiation levels.. *-
If' constraints exist, special-Whole body 1 to l < 5 Seek' shelter as a minimun. consideration should be given or Consider evacuation. Evacuate unless for evacuation of children and
. constraints make it impractical . *
. Thyroid _5 to < 25 pregnant women.
Monitor environmental radiation . levels. . ~ Control access to the affected area.
~ '
Conduct mandatory evacuation. _Sceking shelter would be an - Whole body 5 and above alternative if. evacuation - or Monitor environmental radiation levels were not immediately possibic. Thyroid 25 and above and adjust area for mandatory evacuation based on these icvels. Control ~ access to the af fected areas.- Protective Action' decisions at;the : time of;the' , I These actions are recommended for planning purposes. incident must tak.c existing conditions into consideration. I At the time of the incident. officials may implement low-impact Protective Actions in keeping withlthe - principle of maintaining radiation exposure as low as reasonably achievabic. i l-1 ference: Manual of Protective Action Guides and Frotective Actions for Nuclear-Incidents, ~ EPA-520/1-75-001, Septeaber 1975, .U.S. Environmental Protection Agency.
m f*- FMR 011983 - Page 5 off 6
,.- ?
TABLE E!1V-3F.2,
. G'JIDELit!ES FOR PROTCCTIO!1 AGAI!!ST It!GESTIO!10F C0!JTA.41!:*.TI0ft I. . GRC'J'!D C0!!TAMl!!AT10!!
A. - Action Levels-11 . Projected whole-body dose above the ground 11 Rai.
- 2. Ground Conta,ninition icycls > 4.4 4 107 DPM/100:n2 at t = 1 he post-accident 3 .' Expr ure rate 112 n?./hr at 1 mater 'above ground at t = 1 hr post-accident B. Recorrended Protective Actions
- 1. Evacuation of affected areas.
- 2. Restriction of entry to' contaminated 'of fsite areas until radiation level has decreased'to State approved levels.
1 1. - FOOD A!!D WATER C0_lTAMIllATIO!! A. Actica levels , ~( . Preventive Level: 0.5 RC4 K'O or bone,1.5 R04 thyrsid . Emergency Level: 5 REM WB or bone,15 REM thyroid Concentration in Total Intake via all Pasture Grass Milk or Water Food and Water Pathways (Fresh Weight) Preventive Energency Preventive Emergency Preventive Emergency Level Level Level Level -level- Level fluclide* (uCi/1) (uCi/1) (uC1) (uC1) (uCi/kg) (uCi/kg) 1-131 (thyroid) 0.012 0.12 0.09 0.9 0.27 2.7 Cs-137 (whole body). 0.34 3.4 7 70 3.5 35 Sr-90 (bone) 0.007. 0.08 0.2 2.0 0.7 7 Sr-89 -- 0.13 1.3 2.6 26 13 130 (bone)
- If other nu:lides are present, Reg. Guide 1.109 wi',1 be used to calculate the dose to the critical organ (s). Infants are the critical segment o' t'ie population.
** hkEP,"d' 1333
. : . t. .'- Page 6 of 6
(. TABLE' ENY-3F.2 ' (con t' d) GUIDELIllES l'0!t PROTECTIO!! A'iAlt!ST Il1GESTIC:! CF CONTAMI!3TIO"
~ RECOlNEllDED; PROTECTIVE - ACTIO!!S ,
' Preventive Level Erergency-
- 1. Renoval of lactating dairy co.vs frca Isolate feed ard? tater. from its contaminated pasture and substitution introd>ction in o cornerce af ter
~
of uncontaminated stored feed. consi:nri ng:
- 2. Substitute source of uncontaninated - a. availabilit/ of other possible wate r. . actions;
~
- 3. Withhold contaainated milk fr'oa carket . b. irportance of particular: food to allost radioactive decay, in' nutritio ;
, 4. Divert fluid milk to production of c. tine and effort to take action;.
-( dry whale milk, butter, etc._ .
- d. availabilit/ of other foods.
References U.S. Food and Drug Administration, 21 CFR Part 1090, Federal Register, Vol . 43, No. 242, Dec.15,1978.- A a g 9 G 4
F j !!I'icn:Witt PUdt lC ' SOiVICE CORPORATIO!!' . l 110. EP. RET-2B REY...+
'- .- . ,1:cuabnce'!!uclear Power Plant l TITLE: G: nous Ef fluent Sample l .a d Analysis
~.- El'ERiEliCYL PLAtl - 1MPLGEt1IIt!G L PROCEDURE l [
l DATE: IW .01 DE,3 ~ l' PAGE 1 'of : l7 I I 1Ei'IEvlE0 BY..~ . _, ._ f.u /jg)];)t,/p3 g
- /IPROVED BY k.
m- /. I
- 1.0 APPLl_CADILITY
- The following procedure will be utilized by the Inplan'. Radiation Emergency Tea;n (RET) to quantify elevated releases from the Auxiliary Building Stack or Steaa Relief llenders.
- 2.0 PRECAUT10!is, 2.1 If Control Room readings on tha Containaent Vent ranitor (RE P.9076) or Aux Stack nanitor (RE 29078) exceed 1 R/hr, process ar. Emargency Radiatio:1-Mork Per.ni t (EP-AD-11).
.2.2 Continuous radiation nonitoring is required durin:. all personnel. entries to the fan roc:n, 657' elevation, Auxiliary Building.
-2.3 Supplied air breathing epparatus should be utilized during . sampling if the Control Roo.n read 9ut.s on the R-13 or R-14 stack n;aitors exceed 25,000 cpa.
'(
2.4 The-following taSle can be utilized to estimate auxiliary building stack gas sample activity: APPR0XD1 ATE APPR0XDIATE SAI1PLE I10!!! TOR READillG SPECIFIC' ACTIVITY _ CO:ITACT DOSE RATE R13/14 25K to 125Kcpa 1 to 5 E-5 uCi/cc 150 mr/hr
, RE 29078 .25,nr/hr . 1 to 5 E-4 uCi/cc 1.5 R/hr RE 29078 .3 ar/hr 5 E-3 uCi/cc 1 R/hr RE 29078 50-100.ne/hr 1 E-2 uCi/cc 1 R/hr RE 29078 1 R/hr 1 uCi/cc 1 R/hr 3.0 -REFEREllCES Ilone 4.0 INSTRUCT 10!!S (Aux Buildin] Stack Sanple) .
4.1 R-13 or R-14 less than 25,000 cp:n ' 4.1.1 Connect a standard 4 liter Marinelli beaker to a RAP punp, preceded by a particulate and Silver Zeolite filter.
'4.1.2 Connect the sanpler at R-13A and take a 5 ninute saaple.
(f 4.1.3 Count the liarinelli for 5 minutes and report on Forn RC-!!?-167. 4 4 4 O
d
. . WIStuubitj PU' LIC SLRVICE C0kPORA110!l I 11 0 . EP-RET-2B i
Kcuaunce llucicar Power Plant l TITLE: Gaseous Effluent Sample l ar.d Analysis " Ei!ERGEllCY PLA!! IMPLEMEllfItJG PROCEDURE -. 1 l l' - l DATE: L%R 01083 i PAGE 2 of 7 1 I 4.1. 4 Check the particulato anJ Silver Zeolite f11ters '.it th an 014-14, using the ll? 210 probe in a known area of lw backgr:und radiation. If .the -direct. reading is less than 5.0 E+' :pa, the fil ters can be
. counted directly (5 minute count). . lf the filters es:cced 5.0 E+4 cpm, perfor.n steps 4.1.5 through 4.1.7.
4.1. 5 Connect a particulate filter and Silver Zeclite filter to the tritium sample pu.ap at R-134. 4.1. 6 Take a 5 minate sample at about 100 cc/ min. 4.1.7 : Count the filters for 5 ainutes on the GeLi detector and report on Form RC-ilP-167. , 4.1.8 Save all particulate and iodine samples for further analysis. 4.2 R_-13 or R-14 at 25,000 cpm to 125,000 cpm or P.E 2079 Less Than 1 mR/hr
~
4.2.1 Connect a 4 liter liarinelli to a RAP puas at R 13A. ( 4.2.2 Take a 5 minute sanple. 4.2.3 Count the Marinelli on the GeLi detector ar1 report on Fora RC-HP-167. 4.2.4 -Connect a particulate filter and Silver Zeolite cartridge to the tritium sample puap at R-13A. 4.2.5 Take a 5 minute sample at about 100 cc/nin. 4.2.6 Count the filter and cartridge on the GeLi detector and report on Form RC-HP-167. 4.3 RE 29079 at 1 to 10 mR/hr 4.3.1 Connect a tritium sample puap at R-13A usia.3 tygon tJbing as the ' suction hose and discharging back into the duct. Do not put a liarinelli beaker in line. 4.3.2 . Start the punp at 100 cc/ minute and alloa t) run for a minimun of 5 minutes. - 4.3.3 Withdraw a 5 cc sanple fro,a the suction hose and inject into a 4 liter liarinelli.
,l 4.3.4 Withdraw a 1 cc sanple froa t'ho suction hose for iodine analysis.
o m - - _. w. . V !y.t/MI:!'PU. EIC SERVICC Col!PORA110:1
, il -!!0. EP-RET-?B- - -
.i- _
C {Eaaimeo !!uclear PdderJPlant 'lTITLE: Gaseous Erfluent Sample _ _ ... , .. . l and' Analysis'- ' ~~'
- E".E G~.!3Y-PLA!! lliPLE::E;'ill!G _PROCE00'lE1 ,1. .
I ---(i 1 DATEi Mf2 0 1 1333 1:. PAGE _3 of 7
- l~
- . = . . -- _I _ ..
4
.1 4.3.5 Count 'the !!arinelli fo'r 'S minutes 'on ths C2Li . ul t": ply _ the resul ts' by l800 to convert,to uCi/cc.and report on RC-IIP-167.
,4.3.6 ; Connect 'a Silver. Zeolite cartridge to?a vacfua'sodrce and establish
- flow through the cartridge.
4.3.7 Inject the 1 cc ,saaple in 'the suction side of the cartridca.
. 4.3.0. Count the cartridga for 5' minutes on the GeLi ddtect0c and report on
~RC.HP-157.. .
4.4 : RE 29079 at 10 to 100' r.R/hr -
-4.4.1 Coriacct a tritiun sanple pynp at R-13A using only tygon tubing as the suction hase and dischargiry back into the duct.
. 4.4.2 ' Start the puap at 100 cc/ minute and alloa to rur for a nir.itnun of 5 .
. mi nu tes . ,
-4.4.3 liithdra.t a 1 cc sample fro.a the suction hose and iaje:S into a 4 liter ihrinelli .
- {-
1: 4.4.4 liithdra a .1 cc: sample' frea the' section hose for iodine analysis.
' I 4.4.5 Count the 11arinelli for 5~ minutes o'n the GeLi. liultiply the result'
. l- by 4000 to convert to uCi/cc and report on RC-HP-167.
' 4.4.6 - Connect a Silver Zeolite -cartridge to a vacuum. source and' establish.
flod through the cartridge. 4.4.7: Inject the 1.cc sample in the suction side of.the cartridge. 4.4.8 Count th? cartridge for 5 minutes on the GeLi' detector and report on
- RC-IIP-167.
4.5 RE '29379 at 100 to 1000 rG/hr 4 . 5.1 Connact a tritium sa:aple puop at R-13A using tygan tobing as lthe
> suction hose and discharging back~into the duct.
4.5.2 Start the pump at 100 cc/ minute and allow to run for a minimua of 5~ minutes. 4.5.3 Wi thdraa a 0.1 cc saaple - froa the suction . hose and inject into a-4 liter. Ib rinelli .
UlStul!Siti PU:*lIC SEiWICQ. LORNRAIIW i h0. _ Le-ht i -m
, , Kewaunce lluclear Power Plant l TITLE: Gaseous Ef fluent sample I and Analysis ~ . EMERGEllCY PLAfl IMPLEME:lTING PROCEDURE l i l DATE: t,'M 0 1 1393 i PAGE 4 of 7 l I 4.5.4 Withdraw a 0.1 cc sample from the suction rose for isdine analysis.
4.5.5 Count the liarinelli for 5 ninutes on the GRi. "ultiply the results by 4 E+4 to convart to uCi/cc and repyt o- RC-!!P-1: 7 4.5.6 Connect a Silver Zeolite cartridge to a vav;un souru and establish flow through the cartridge. 4.5.7 Inject the 0.1 cc senple in the suction si'a of the cartridge. 4.5.8 Count the cartridge for 5 minutes on the CEi detectw ard report on RC-IIP-167. Multiply result by 10 to convert to uCi!:c. 4.6 RE 29079 Greater Than 1 R/hr 4.6.1 Grab sampling ani laboratory analysis are not feasible at these concentrations. Refer to EP-AD-2 for Er.er;ency classes. Confi rmatory measureaents will be nade in the predicted pluu path. 5.0 INSTRUCT 10tlS ( Aux. Building Stack - SPI!1G-4 Use) ( 5.1 Iodine Release 5.1.1 Readout the last 2310 ninute averages ('lHT MIM, 0103, ENTER). 5.1. 2 Divide the latest average (in, uCi) by the integrated sanple flod (SE+11 Ci/uCi-cc) to determine average release concentration in Ci/cc. 5.1. 3 Multiply the concentration by stack flow rate in cc/sec, to determine release rate. Assume all the iodine release to be I-131, 5.2 Noble Gas Reicase 5.2.1 Readout the current value of the t.ow, !!cdi n, and Hijh Range channels (DATA, 0105 or 0107 or 0109, Et!TET). 5.2.2 Select which channel to use based on the channel status inforaation. Do not use a channel in the " Fall. HI" condition. 5.2.3 Multiply the channel concentration in uCi/:c by the stack floa rate to determine a gross release rate. 5.2.4 Multiply the gross rate by the isotopic noualizati:q factors given in Table 1 to predict isotopic release rates. Time 0 on the table is the time of reactor trip.
TD 3 > 27MYWYMTON~3DWfTipWOJartf00E , - innuc ty;wrT; W
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Ks.taunce-:!dcl00$Pd:or P1 ant .- r .. l .-11TLE : LGas?ous Ef fluent San;ild ! q '* y 1 .
.a- . .
l v 'j6q Analysir,
~~ '
~
D*.EP,%!!CY PL A!! 1"PLDO!f t:!G PROCEDU?L -l, l
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((. I DATE: ' 7[i." NE33 -1: PAGE'idiof" 7.
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. 16'.0~' I!:STRUCTIONS J (STE*" kr.l.lFF lif.ADERS DIRECT RDAIATIO I O'lITO:tS); ,
, .6.1 '
Contact ;the Toc Suppqrt Center for- the Steca 1.inellonitorf rcadings and; Ethetreleass path. (valves opan). , 16.2 ' Select- the pra;ier balib' ration factor ' fro.a Tablei2,1 based fon TJ D b61ng the- time V -of thd reactor' trip, to calculate the gross releas: rate. 6.3' Use the 'appropeiate noraalization. factors;froa Table lito calculate isotopic-releasa rates.- G l..
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';- -.1 ISOTO'JE NORMALIZATION FACTOR
~
f i c S '. 1 0 HR '0.5 HR. .1' HR - . 2 HR - 8 HR'- 1 DAY: L 1 L'EEK -
~
- 1. KR-85 .0015 .00567 .'018 0 .0019~ . 0023 -J0028 .'00 69 ..
2.;.KR-85M .06 .061 .060 .055 .027 .027- 20'
- 3. KR .11- .0965' .075 .047- .0022 0 0
- 4. KR-88 .159 .149 .139 .119 .0033 .0008 , 0..
- 5. XE-133 . 421 .465 .491 .526 .649 .754 .95
- 6. XE-133M .064 . .~ 0 71L .075 .079' .094 .099 .0'44
- 7. 'XE-135 .095 . 105 .120 .139 .171 .112 'O
- 8. XE-135M .095 .050 .038 . 033- .021- .0047. , 0
- g(.f t(DF)g - 419 381 349- 299 .78.9 56.2 33.2 I' t. ,
3 ACTIVITY x 10-6 x FLOW RATE x RELEASE DURATION (HRS)' x X/Q (Sec/m ) x [ fi(DF)g = TNT DOSE (RDO
.(uC1/cc) (C1/uC1) (cc/sec) REM - m3-ci-hr ,
2 bI ca c-~; c' % . g m: o . y- M:
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Page . 7 <of.' 7f 9- '
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GROSS RELEASE' 'RATP liETERMlliATION TOR STEAM RELEASES , s.- . uci /c.c - R/hr. x
~
, ki b r x cc/Ecc-
,'St.m. !!d r. _ Cal l'an:.or .x 10-6Ci/uci- =
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. Mon.,;PdL . F1ow hate - - Gross Relence -
. Rate'
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'FLON RATES: Assu .e steara line relief flow to ba c. qual to safety injection flow for a tube rupture.
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_ i .,; 1: { Calibration Factors: TIME
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14.5' 16.7 20.3 30.4 67.9 887 3.08 x 10 .l.93'x 10 uC1/cc R/hr
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n;;,Ctc,1N lit!BI IC SLRVICf. CORP 02Afl0:! !!O. FP-sic.? _ IT V_. C _, s y. TITLE: 5:: ri'.y Force ~ pc se
. te,winee fluclear Power Plar.t
,, to " t gencies T
(' L::EPCiI:CY PLAl: Il4Pl.f fTf Tll:G PPOCEDt!PE DATf: 1,',AP. 0 1 '333 l I-PAGE 1 of 3
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4 I!EVIEMEli PY )10.[hf,h/.J ,[3fg.,,.u._ _ APPROVE:' hY _ , 7' I I . 1.0 , APPL ICAB il.Il Y The Security Force shall inple. ment this precedu e u;on declarition of a plant emergency. 2.0 f RECAtlT10 iS 2.1 If the plant energency is caused by a security event, ti a Cor.tingency Plan and precedures have priority over the tctior,s in t!.is procedere. 2.2 All Security personnel shall wear their dcsimetry af ter declaraticn of a plant e,iergency. 2.3 if the Security Building becotaes uninhabiteMe, ections of the Security Force should be directed by the Shif t Captain fro;n the Site Access Facility.(SAF) 3.0 REffREffCES 3.1 EP-AD-12, Personnel Assenbly and Accountability 3.2 EP-AD-13, Personnel Evacuation 3.3 EP-AD-14, Search and Rescue 4.0 SECllRITY DIRECTOR /S!!IFT CAPTAl!! II:STRl!CT10"S 4.1 linusual Event l 4.1.1 If required, ready the emergeocy vehicle and prc.ic'e energency vehicle driver to transport injured incividual ta of fsite medical facilities. Il01E: A plant high band radio (or Shif t Captain's desk) should be taken with the vehicle. 4 .1. 2 If Personnel Assenbly is announcec' cver the Gai-tronics, TrT;;1eneITP-StW37 Personnel Acccur.:c:ility ; hitial and flai rit a ining . 4 .1. 3 Direct any search and rescue operations required. I;0TE : Controlled area entries must be coordinr..d with the Radiological Protection Dircctor.
P WIS;0';51'! PUP.I.1C SI RVICI CuRPDRA110:1 fl0, EP-SFC-2 KewaNRe'!1oclear Power Plar.t TIT 1.E : Security Ecrce hspor.se
** to 1:r.ergenci es f:'EPGEt;CY PLA!! If!PLEI'll;Tir:C PRDCf DURI.
f DATE: g,g g 1 G 3 PAGE 2 of 3 I ! 4.2 Alert, Site Emernency, or General Emergency 4.2.1 If needed, provide energency vehicle driier to tr;nsport injured individual to offsite riedical fa:ilities. Il0TE: A plant high band radio (at the Rtt iaticn Frotection Office) should be taken with the vehicle. 4.P.2 If Personnel Assembly is announced over the Cai-t onics, Ese'rfiitiff iiiplement I.P-SLC-3. 4.2.3 Disptch an of ficer to the Site Access f acility (IAF). lie /she shall:
- a. Obtain StF keys from thc' Shift Captain.
l b. Take the energency vehicle and radie to the SAF, l c. Stopping off traffic on !!uclear Road, (use rcidblecks cs needed),
- d. Impler.ent EP-SEC-4, Dosimetry Issue at SAF,
- e. Only allow personnel with Kewaunee Plant 1.D.'s access, unless authorized by:
Shift Supervisor Support Activities Director Emergency Director Security Director Event Operations Director Energency Response itanacer Radiological Protection Director Environc.er.tal Protection Dir. TSC Director Idnin/ Logistics Director
- f. Inforn Shif t Captain and ilWY 42 officer by radio of authorized in-coming personnel, and 9 Record the names of personnel teleptonir.g the SAF that they are in transit and give list to Environr.antal ttonitoring Tean Coordinator af ter his arrival.
l 4.2.4 Dispatch an of ficer to the plant HUY 42 entrance. ~He/she shall:
- a. Report to the llHY 42 entrance and place a road block,
- b. Direct any reporting personnel to the Site Access Facility, and
- c. Only allow entrance,to those personnel cleared by the SAF officer.
b ; )!!SC0!!Siti.Dullt.lC SERVICE CORPORATIC:! -l!0. f P-SFC .'i { 0 'Kew Te8t!uclearPowerPlant LTITIE: 1 Security force Pespcns t '_ - to frerger:cies __
- EMERGffiCY PL.At! IMPLEMf flTil!G PPOCEDUPE l'7 DATE:. . .pp4i.33 .
.PAGE 3 of,3
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4.2.5'Dispatchano[ficertotheEmergencyOperationsTacility ' (EOF). lie /she shall notify the Trio Pivcts' Chief of1olice a nt' Manitowoc Country Sherif f's DepartrAnt of the E.0.F. opening. Ile/she shall open the EOF ard log in responte personnel . 4.P.6 Contact the Shift' Supervisor or Energer:y Directcr for cny information on hazardous site areas. Osteristne a safe route for.. exit,. then dispatch 'an of ficer -to t'e fishir; aret. lle/she shdll inforn people they should ' eave thel site, using the following statenent: ,
"The plant site has been temporarily cl sed and ,uu are requested to leave. (Specify route . Flease do so at this tiine."
N0 OTHEll itif(WI.T10!! S1:0ll1.0 BE GIVT!:. 4.2.7' Direct any search and res, cue operaticns. , f' NOTE: Controlled area entries must be coordinated wi-h the I 1 Radiological Protection Director. . l 4.2.8 Assist in the evacuation of plant perscinel (EP .;D-13}. 4.2.9 Contact additional Security force persc1nel to augment the normal shift complement. . 4 I5
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