ML20078C653
| ML20078C653 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/10/1983 |
| From: | Barkhurst A LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20078C644 | List: |
| References | |
| PROC-830710, NUDOCS 8309270725 | |
| Download: ML20078C653 (80) | |
Text
. - _____ - ____________
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WATERFORD 3 SES PLANT OPERATING MANDAL LoulSIANA MICDLE SOUTH UTR.mES SYSTEM POM VOLUME la hh~h0 l PCM SECTION ' APPROVAL DATE:
EFFECTIVE DATE: Fuel Load gjfg ,
EMERGENCY PLAN IMPLDfENTING PROCEDURE RADIOLOGICAL FIEID MONITORING LP&L W-3 RECORDS CONTROLLED COPY
{ No. n24 PORC Meeting No. fA.C AB I Raviewed: kk l
[
1 Cha Approved:
Plant Manager-Nuclear
[
8309270725 830922 PDR ADOCK 05000392 F p
l WATERFORD 3 SES )
PLANT OPERATING MANUAL l CHANGE / REVISION / DELETION REQUEST -
Procedure No. 6P-2-qdo Effective Date f u 0 L M Title b b A- uJ I d h-JeI=]
(if different from approval date)
Comnlete 1. B. era C A. Change No. M B. Revision No. A C. Deletion Nlk WFAMON FOR EHANCE. REVISTON. OR DELETTOM 0AM/jbw 1mh/6m N d
/ / /
REOUTRED STCMATitart originator bi- ^c o dt) Date 4 l L1- 8 Technical Review V
.MNbb Date 5 12 h 3 U
SAFETT EVALUATION Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR7 Y
- 2. Change the procedures as described in the FSAR7 _ Y 3 Conduct tests / experiments not d,escribed in the FSAR7 W '
- 4. Create a condition or conduct an operation which ex- _M ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safe y Evaluation checklist.
Safety Evaluation de O "W Date @D ~ D _
Group /Dep't. Head Review 4Nb$6k Date V -D- O U
Temporary Approva18 Date (NOS)
Temporary Approvale Date QC Review / NA GrY k L Date M f- E'3
- PORC Review I I
- dr W Wa #MA Meeting No.73-174 PlantManhedkuclearApproval Mh Date O//8 %
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2(e e<- y -,,,.re e-y--. mew,,.--.s-p g w.
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WATERFORD 3 SES l PLANT OPERATING MANUAL l CHANGE / REVISION / DELETION REQUEST Procedure No. Eb > cGo Title Aab roled i e ni AliA b /wwirdum Effective Date Fwd 1 Lc4 b (if different from approval date) l l
Camelete A. B. or C A. Change No. 1 B. Revision No. 1 C. Deletion N/4 FA ASON FOR CH ANCE. REVISION. OR DELETTON k C.& vtt d rh Ih !r m rl.L$ r/1.v_NA WAl $r A L1A&te f Emm hmJ AAd REQUIRED STCMATURES Originator M Date / d Technical Review N/4 Date N/4 SAFETY EVALUATION ,
Does this change, revision, or deletion: TES NO
- 1. Change the facil::.ty as described in the FSAR7 -
- 2. Change the procedtires as described in the FSAR?- _.<_
- 3. Conduct tests / experiments not described in the FSAR7 /
- 4. Create a condition or conduct an operation which ex- -
ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safet valuation checklist.
Safety Evaluation k Date hll'I 3 Group /Dep't. HeadRevNw 4MMM Date 9'(I ~ b O
Temporary Approval
- Date (NOS)
Temporary Approva18 Date QC Review AM Oft'Id- Date + - 'F- n PORC Review 1 b Da 4-1 k-I'3 Meeting No. I'3 -s rA PlantManagehNuclearApproval Mohd Date 17/& 9 cTempo'rary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
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WATERFORD 3 SES
/7 PLANT OPERATING MANUAL j
!. CHANGE / REVISION / DELETION REQUEST Procedure No. 8 dd O- Title Er/dP/d hd MM Effective Date (if differen't from PM-N approva1Tdate)
Chmnl ete it.- B . or C A. Change No. #/4 ,
B. Revision No. / l C. Deletion N/A l l
RFARON POR CHANGE. REVISION. OR DELETION .
Y -/ h /es-d dw S2 W //lf ubh s/ W- : 8 b41 2M ]6)*d W - --
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Originator 4 ~
Date ) '!b -~~
Technical Revie[--k b '
- - ' ' - - Date - bl'I M -~ ~
0 1 SAFETY EVALUATION p Does this change, revision, or deletion: YES NO Q_
s.. 1. Change the facility as described in the FSAR7 .
- 2. Change the procedures as described in the FSAR7 '
3.
Conduct tests / experiments not described in the FSAR7 4 Create a condition or conduct an operation which ex- U ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation b bk - - - --
-- Date - blO O ----
Group /Dep't. Head Review N bodL --- Date dl-19'tSL -
U i Temporary Approval'
- ~ ~ -- - -
Da te - ~~~~
-- (NOS)
Temporary Approval * - - -- --- Date -
QC Review & W b: 1? - - * - -------
Date - l~ / 3 5- - * - -
PORC Review N A N -
Date. 'l_-l i-I? --- Meeting No. -b OPd Y PlantManagerYuclearAppLoval b '~ --- - Date -M/Q-
- ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1) e s-, , m..~,w ,,,.7, .-.w. .mw.m-~__ ,,q .,7,y.g.w-,._,,w9. ,,,,,_m ,,,,,,,,,,,s.w., ,,_,,g,,___,yg .,_-,.y..-g ,.,..e-,,,w. ,, ,. p
Emergency Plan Implementing Procedure EP-2-060
. Radiological Field Monitoring Revision 1 k.
TABLE OF CONTENTS 1.0 PURPOSE , ..
2.0 REFEREN CES -
3.0 RES PONSIBILITIES
' 4.0 INITIATING CONDITIONS 5.0 PROCEDURE s
6.0 FINAL CONDITIONS ,
7.0 ATTACHMENTS 7.1 Dose Rate & Air Sample Data Log (1 page) 7.2 Radiological Field Monitoring Kit Location and Contents (1
- page)
- 73 Ludlum 2218 Switch / Meter Locations (2 pages)
LIST OF EFFECTIVE PAGES -
~
Title ,
Revisio'n 1 1-t4 4 , 6 -li Revision 1 5 Cet Au e I e
l l
1 l
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 1.0 PURPOSE To define the methods and techniquer to be utilized in performing field monitoring following a suspected release of radioactive material.
2.0 REFERENCES
2.1 EP-2-050, Offsite Dose Assessment (Manual) 2.2 EP-2-051, Offsite Dose Assessment (Computerized) 30 RES PONSIBILITIES The Radiological Field Monitoring Teams are responsible for implementing this procedure.
4.0 INITIATING CONDITIONS .
4.1 This procedure is to be initiated upon any of the following conditions:
4.1.1 Declaration of any of.the following emergency classifications in which the event includes an actual or potential release of radioactive material to the atmosphere.
4.1.1.1 Alert 4.1.1.2 Site Emergency 4.1.1.3 General Emergency 4.1.2 At the discretion of the Health Physics Coordinator (HPC) or the Radiological Assessment Coordinator (RAC). l 5.0 PROCEDURE 5.1 Assignment of Radiological Field Monitoring Teams 5.1.1 The assignment of personnel to Radiological Field Monitoring Teams will be made by the Radiological Controls Coordinator at the direction of the Health Physics Coordinator.
2
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 5.1.2 Each Radiological Field Monitoring Team should comprise two individuals, at least one qualified in the operation of the field monitoring equipment.
5.2 Radiological Field Monitoring Teams will normally be dispatched from the Operational Support Center (OSC); however, the HPC may prescribe monitoring assignment; upon initial notification of certain team members. The Radiological Field Monitoring Teams, as assigned, will proceed to the nearest storage location for field monitoring kits as identified in Attachment 7 2.
5.3 The team shall obtain kit. Kits with broken seals should be avoided l
unless necessary.
3.4 Each kit will be opened and quickly inventoried. Inventory lists are posted inside the individual kits.
5.5 In addition to the inventory, the following equipment checks shall i be performed:
5.5.1 R0 Visual Check and Battery Check 5.5.2 Ludlum 2218 and Detector - Visual Check and Source Check with Barium-133 Source l
1 3
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1 l
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 l
NOTE
- 1. This check is n21 to determine instrument efficiency. Once a response is noted (counts being accumulated), the instrument can be considered operational.
- 2. The Radiological Field Monitoring Teams will be directed by the Health Physics Coordinator (HPC) or, if activated by the HPC, the Dose Assessment Coordinator (DAC). Once the EOF has been activated, the teams will be directed by the Radiological Assessment Coordina*or.
The onsite field monitoring teams will remain under the direction of the HPC.
5.5.3 Radio Communications Check - Communications must be established prior to leaving the OSC.
5.5.3.1 For Alert emergencies (Technical Support Center activation),
establish communications with the Dose Assessment Coordinator.
5.b.3 2 For Site and General emergencies (EOF activation) establish com-munications with the Field Monitoring Communicator at such time that responsibility for dose assessment has been transferred to the EOF.
5.6 During initial communications check, each t>e 1 receive a team designation (Alpha, Bravo, etc.) from the HPC/DAC a. ~" tial instructions.
5.7 Each team shall leave the OSC and obtain their designated vehicle.
4
1 1
Cuergency Plan ~ miementing Procedure EP-2-060
( $2diological Field Monitoring Revision 1 NOTE As soon as they leav.h the'OSC, the dose rate instrument should be turned on and monitor'ed continuously. The HPC/DAC or RAC should j be updated on dose rates and location frequently, about every 2-3 minutes.
5.0 Proceed to the locat on as identified by the HPC/DAC or RAC.
At l that location, perform the foliowing:
5.8.1 Ga==a survey with R0-2 5.8.2 Beta survey (open-window) with RO-2 k
ll NOTE SurveysshouldbeperformedwithR0-2$ eld vertically at one (1) meter above groEnd level. The monitor should slowly rotate 360 degrees and determine the maximu= dose rate.
5.9 Notify the HPC/DAC or RAC of the levels monitored. l 5.9.1 If levels are below the =inimum sensitivity of the instrument, report results as "less than" the mini =um scale deflection.
eWLY Tis Npc/ DM C, UNLESS OTHERDRE EEQUESTE 5.9.2- Report ga==a sred beta levels 4e- "C --^' i c. . . ~ f;. si;;; :nd 4 1 ZA y,A_ glyGS joP!N ysnoonD Shout.D. EE REcoR DED BUT hot ljcmf l REPORTED. 1 l
5.i0 ?.ecord all data on Attachment 7.1. j 5.11 Unless otherwise directed by the HFC/DAC or RAC, obtain an air sam- ]
pie at this location as follows:
l
. l l
5
Emergency Plan Implementing Procedure EP-2-060 i I
Radiological Field Monitoring Revision 1 5.11.1 Install particulate filter and silver zeolite cartridge in the air sampler cartridge holder. Air drawn into sampler must pass through particulate filter first, then through the silver zeolite cartridge. Silver zeolite filter must be inserted so that air pa'sses through in the direction of the arrow on the side of the filter.
5.11.2 Turn on sampler and stopwatch. Note flow rate.
CAUTION Monitor flow rate frequently. If air sampler is powered by car battery with the car running and the en'gine is then stopped, the flow rate will decrease.
5.11.3 Run air sampler to obtain an air sample volume of at least 10 cubic feet.
CAUTION Air sampler should not be placed with the nozzle near any surface which is potentially contaminated.
5.11.4 While air sample is running, prepare two envelopes, labeling each with the following information:
5.11.4.1 Date and Time 5.11.4.2 Sample Number 5 11.4.3 Location 5.11.4.4 Flow Rate (CFM) 5.11.4.5 Sampling Duration (minutes) l 6
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 1
1 NOTE Samples will be given a sequential number preceded by the team designation, i.e., A1, A?, A3, or B1, B2, and so on. j 5.11.5 After appropriate volume is collected, stop air sampler, remove particulate filter and silver zeolite cartridge and place into envelopes.
5.11.6 Record all sample data on Attachment 7.1.
5.12 Unless otherwise directed by the HPC/DAC or RAC, analyze the air j sample for iodine activity using the Ludlum 2216 as indicated below, Samples obtained on site will normally be returned to the Health Physics Lab for analysis.
NOTE Background radiation levels may interfere with counting equipment. If dose rates exceed 5 mR/hr, do not attempt to count filters; proceed to low background area.
5.12.1 Verify (or set) the following settings on the Ludlum 2218 (see Atcachment 7.3 for location of switches):
Switch Position A. Stabilizer Toggle Switch On B. Channel 1 Toggle Switch In C. Channel 2 Toggle Switch Out D. Channel 1 Window 40 7
i l
l Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 1
1 Switch Position E. Channel 1 Threshold 344 F. Channel 1 Multiplier Bypass G. Channel 2 Multiplier Bypass H. Add-Off-Subtract Switch Channel 1 Add I. Add-Off-Subtract Switch Channel 2 Off J. Live-Clock Toggle Switch Live K. Time-Multiplier Switch X1 L. F-S Toggle Switch S M. CH1-CH2-Sealer Switch CH1 N. Range X1K (Initially)
O. Recycle Toggl'e Switch (on back) Off NOTE Range setting should be reduced during count-ing to give on-scale reading.
5.12.2 Detector Operation and Setup 5.12.2.1 Verify that the Nal detector is connected to the Ludlum 2218.
l 5.12.2.2 Insert detector into shielded sample holder.
5.12.2.3 Place power selector switch to "BATT." Allow approximately 5 minutes for equipment to stabilize.
5.12.2.4 Set count timer to 2 minutes. Start the background count by pushing the COUNT RESET button. Run background count for 2 minutes. Use Attachment 7.1 for recording analysis data.
8 1 I
1 l
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 5.12.2.5 Place silver zeolite cartridge in shielded sample holder with the inlet side of the cartridge facing the detector.
5.12.2.6 Reset count timer to 5 minutes and push the COUNT RESET button. Count sample for 5 minutes. Record on Attachment 7.1.
5.13 Notify the HPC/DAC or RAC of the results of sampling and analysis for I-131 including:
5.13.1 Team Designation 5.13.2 Sample Number 5.13.3 Sample Location 5.13 4 Sample Duration 5.13.5 Sample Flow Rate 5.13.6 Total Sample Counts (5-min. count) 5.13 7 Total Background Counts (2-min. count)
' 5.14 Proceed as directed by'the HPC/DAC or RAC to additional monitoring l points. Continue performing surveys and air sampling / analysis as directed.
5.15 While in transit to monitoring points, maintain continuous dose rate monitoring and notify the HPC/DAC or RAC of any significant l
findings, paying particular attention to the location of the highest measured dose rates.
5.16 Retain all air samples in plastic bags.
NOTE The HPC/DAC or RAC will designate a specified !
location where all samples and data sheets will be returned.
9
Emtrgency Plan Impicmenting Procedure EP-2-060 R,aciological Field Monitoring Revision 1 6.0 FINAL CONDITIONS 6.1 Releases have terminated or reduced to levels below the EAL's for an Alert emergency classification.
6.2 All surveys and air samples requested have been completed.
6.3 All data sheets, particulate filters and silver zeolite cartridges have been returned to the location defined by the HPC/DAC or RAC.
l 7.0 ATTACHMENIS 7.1 Dose Rate & Air Sample Data Log 7.2 Radiological Field Monitoring Kit Location and Contents 7.3 Ludlum 2218 Switch / Meter Locations l
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RADIOLOGICAL FIELD MONITORING KIT LOCATION AND CONTENTS Kit Locations Operational Support Center 3 Kits Kit Contents Item Number Particulate air sample filter 1 bx Silver zeolite sample cartridge 10 ea Portable radio 1 ea Stopwatch 1 ea Clipboard 1 ea Writing pen 1 ea Flashlight 1 ea Battery, D-cell 2 ea Writing pad 1 ea Sample bag 12 ea Survey maps Dose rate meter (RO-2 or R0-2A) 1 ea Air sampler, battery-powered 1 ea Gamma analyzer, Ludlum 2218 and, 1 ea NaI Detector w/ cable Shielded sample holder 1 ea EP-2-060 Revision 1 12 Attachment 7.2 (lofl) i I.
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WATERFORD 3 SES PLANT OPERATING MANDAL !
M l OUISIANA POWER & LIGHT
'Mit[T1NSY EP-2-050 PCM VOLUME 18 REVISION 1 PCM SECTION 2 APPROVAL DATE: May 2,19 83 EFFECTIVE DATE: Fuel Lead 0
EMERGENCY PLAN IMPLEMENTING PROCEDURE OFF-SITE DOSE ASSESSMENT (MANUAL) 4 Lpat.W-3 RECORDS CONTROLUED COPY NO.} ' ^
PORC Meeting N f3 -19 4 Reviewed: f _- r, a -
RC Chqir-Approv d: Lf\ 0) JtNA Plant Manager-Nuclear m
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WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST !
Procedure No. EP-2 --oso Title Off-5/IE ME /9S32s5rr? ANT [lYM NUM-) l Effective Date (if different from approval date) ca-niet. 1. n er c -
A. Change No. l B. Revision No. l .
C. Deletion A//4 REASON FOR CHANCE. RE7TSTON. OP DRETTON Esec,e /g 2:w N':). 3 W ' N / U N M bty?('st f k m ft'/ f' fY W REQUIRED SIGNATURES Originaton~ Am SA mm> Date Y/O <P 3 il Technical Review
'N M Date' WM 3AFETT EVALUATION Does this change, revision, or deletion: TES NO
- 1. Change the facility as described in the F3AR7 X
- 2. Change the procedures as described in the F3AR7 M
- 3. Conduct tests / experiments not described in the F3AR7 A *
- 4. Create a condition or conduct an operation which ex- A coeda, or could result in exceeding, the limits in l
Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 3 t Ev 1 tion hecklist.
Safety Evaluation -
. < e/ Dato
- Group /Dep't. Head Review M 2 mum Date d'/B/f 3 94
~
Temporary Approvale Date (NO3)
Temporary Approvals Date QC Review IVA AWEAM Date d-3-f2 PORC Review \ d b b Data b-IS-% b Meeting No. f3-Jl Plant ManagerhNuclear Aphroval b M w D ~ Dato W'O /E3
- Temporary approval must be followed by Plant Manager-Nuclear approval i within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G e
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Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) Revision 1
~
TABLE OF CONTENTS
.4 1.0 PURPOSE ,
2.0 REFERENCES
30 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Dose Projections Based or Plant Monitoring Data (22 pages) ]
72 Dose Projections Based or. Field Monitoring Data (7 pages) 7.3 Dose Projections Based on Known Isotopic Release Data (6 pages) g 74 Dose Projections Based on FSAR Accident Data (4 pages) 7.5 Meteorological Data (18 pages) e LIST OF EFFECTIVE PAGES Title Revision 1 1-62 Revision 1
< &I1 c. Q l c M r3 1
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WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. S~A SSO Title _ OW-Si/e Ihre Assessmerrt k!lante!
EffectiveDate8t/r/ bad (if different from approval date)
(*am el s ta 1. B. or C A. Change No.
i B. Revision No. /
l C. Deletion N/A REASON FOR CHANCE. REVTSTOM. OR DFLFTTON A lt* h A ?l h s O M a f ka f3 !? AMN RKOUTMFD STCM17UWF1 Originator- M Date / /
Technical Review "
4 9 bb Date 4-89-3 3 i
SAFETT EVALUATION Does this change, revision, or deletion: TE3 NO
- 1. Change the facility as described in the FSAR7 _ 1
- 2. Change the procedures as described in the FSAR7- X
- 3. Conduct tests / experiments not described in the F3AR7 X *
- 4. Create a condition or conduct sn operation which ex- A coeda, or could result in exceeding, the limits in .
Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safe Evaluation checklist.
Safety Evaluation k i Date N ~#Y ~U Group /Dep't. Head Review bA Q Date W c -/ V- G Temporary Approvale Date (NO3)
- Temporary Approvale Date QC Review s MA Gfd , l^ - Date d 9 -- P ?
PORC Review M ~ Date MM Meeting No. Y3-/ M PlantMankr$uclearApprova1 ' NM W Date AdA "Y
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) Revision 1 TABLE OF CONTENTS 1.0 PURPOSE ,
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 70 ATTACHMENTS 7.1 Dose Projections Baned on Plant Monitoring Data (22 pages) 72 Dose Prajections Based on Field Monitoring Data (7 pages) 7.3 Dose Projections Based on Known Isotopic Release Data (6 pages) 7.4 Dose Projections Based on FSAR Accident-Data (4 pages) 7.5 Meteorological Data (18 pages)
LIST OF EFFECTIVE PAGES Title Revision 1 1-62 Revision 1 i
i 1
_ _ ~. . - . _ _ _ ,__ . _ - __
Emergency Plan Implementing Procedure EP-2-050 Off-Site Oose Assessment (Manual) Retision 1 1.0 PURPOSE Provide methcds for determining projected off-site doses following a major accidental release of radioactive material; fer purposes of re:ommending off-site protective actions; and for long-term continuous updating of the off-site doses in the event the computer-based system (CEPADAS) is not available.
2.0 REFERENCES
2.1 EP-2-051, Offsite Dose Assessment (Computerized) 2.2 Meteorology and Atomic Energy - 1968, D.H. Slade USAEC Report TID 241090 2.3 U.S. NRC Regulatory Guide 1.23, Revision 1 - Meterological Programs in Support of Nuclear Power Plants 2.4 U.S. NRC Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I, Rev. 1, October 1977 2.5 U.S. NRC Regulatory Guide 1.145, Revision 1, Atmospheric Dispersion Models for Potential Accident Consequent Assessments at Nuclear Power Plants 30 RESPONSIBILITIES The Radiological Assessment Coordinator / Dose Assessment Coordinator is responsible for ensuring this procedure and all calculations are performed in accordance with this procedure.
4.0 INITIATING CONDITIONS 4.1 Any of the following emergencies has been declared:
Alert Site Area Emergency General Emergency 2
l l
Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) Revision 1 and a release of radioactive material to the atmosphere has occurred or has the potential to occur.
4.2 As determined by the Radiological Assessment Coordinator / Dose Assessment Coordinator or the Emergency Coordinator.
5.0 PROCEDURE NOTE This procedure is arranged in attachments, each describing a specific method of assessing of f-site dose. The specific attachment (s) which is (are) to be utilized in performing dose assessment shall be based upon availability of plant operating data and radiological field data. Only if no plant or field data is available, should Attachment 7.4, Dese Projections Based on FSAR Accident Data, be used. Each attachment is described below.
5.1 Attachment 7 1 - Dose Projections Based on Plant Monitoring Data.
This attachment is used to rapidly assess the maximum off-site doses to determine if off-site Protective Action Guides will be exceeded and if recommendations for protective actions should be made. It is the fastest means of manually calculating projections and should be followed up by further detailed calculations, especially those that may be based on actual field data.
5.2 Attachment 7 2 - Dose Projections Based on Field Monitoring Data.
This attcchment provides methods of p,erforming dose projections based on actual measurements by off-site monitoring teams.
5.3 Attachment 7.3 - Dose Projections Based on Known Isotopic Release Rate. This attachment provides methods of calculating off-site doses when isotopic analysis of the release path exists.
3
Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) Revision 1 5.4 Attachment 7 4 - Dose Projections Based on FSAR Accident Data. This attachment provides methods of calculating off-site doses based on nine types of accidents analyzed in the FSAR. Dose projections utilizing this technique should be used only if there is insuf-ficient information to utilize the procedures identified in At-tachment 7 1, 7 2 or 7 3.
5.5 Attachment 7.5 - Meteorological Data. This attachment provides the method for obtaining meteorological data needed to perform dose i l
projections. The attachment provides the method for using overlays I to determine dispersion factors.
NOTE An adequate supply of all forms for each attachment is maintained in the TSC and EOF (primary anc backup) for the Radiological Assessment Coordinator / Dose Assessment Coordir.ator's use. l 4
6.0 FINAL CONDITIONS 6.1 Releases of radioactive material to the atmosphere have been terminated or decreased below the EAL for an alert category or:
6.2 Releases are controlled and a long term monitoring program has been established.
4
l, .
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i Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) Revision 1 i
7.0 ATTACHMENTS 71 Dose Projections Based on Plant Monitoring Data 72 Dose Projections Based on Field Monitoring Data
- 7.3 Dose Projections Based on Known Isotopic Release Data i
- 7.4 Dose Projections Based on FSAR Accident Data l 75 Meteorological Data I
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DOSE PROJECTIONS BASED ON PLANT MONITORING DATA 1.0 PURPOSE This attachment provides the methods for quickly calculating projected off-site doses in order to determine the need for protective actions.
2.0 PROCEDURE 2.1 Determination of whole body and child thyroid doses at specific off-site locations is performed using the attached work sheets.
2.2 Determination of accident type.
2.2.1 Based on information communicated by the emergency coordinator, select the form for the most appropriate accident type and log the exposure duration in Column 5.
NOTE The exposure duration (for all except main steam line break) should be assumed as two hours unless plant information provides an accurate, dependable prediction of release duration.
Attachment .1, Page 5 - Fuel Handling Accident Attachment . Page 6 - Waste Gas System Failure Attachment . Page f ~- Liguid Waste System Failure i!!" R$*si : , hPage10-S.GlbifeRupturefa[Sbh*egure Attachment . ,
1 9 bOC
. Tu Major Fuel Failure Attachment . , Page 11 - S.G. Tube Rupture,, <1, Failed Fuel MAIN STEAM RELEASE = MSR Attachment 7.1, Page 12 - MSR, Major Fuel Failure, Steam Line Break Attachment . Page 13 - MSR Ma;or Fuel Failure, Relief Valve Attachment . Page 14 - MSR Ma; or Fuel Failure Atmos. Dump Attachment Page 15 MSR Ma or Fuel Failure, Emer. Feed Pump Tur ine; ,
kkk$cN$!nk . hake h ~ Nbk <l $k !N N he$$$ fha $vh I Attachment . Page 18 - MSR <1% ailed Fuel Atmos. Dumo Attachment . Page 19 - MSR <1% ailed Fuel Emergency Feed Pump Turbine EP-2-050 Revision 1 6 Attachment 7.1 (/ of/8)
DOSE PROJECTIONS BASED ON PLANT MONITORING DATA NOTE It is possible that two release paths and two forms are applicable. If this occurs, the projected doses and release rates from each form should be added together.
2.3 Record the date and time on the selected forms.
2.4 Record the following meteorological data:
NOTE Data from both the primary and backup meteorological towers is available on the CRT in the Control Room. Data from the backup tower should be used only if the required information is not available from the primary tower. Figure 1 of Atta chment- 7.1 provides a descripti n of the meteorological data to be available in the Control Room. If data from neitner tower is available, follow the procedure outlined in Attachment 7.5.
2.4.1 Record the 10 meter wind speed in mph in Column 3 of the selected form. Multiply meters /sec times 2.24 to obtain miles / hour.
2.4.2 Record the wind direction in whole degrees from which the wind is blowing in section 7 of the selected form.
2.4.3 Record the delta T (60 m - 10 m) in degrees centigrade ( C) in section 8 of the selected form.
2.4.4 Based on the delta T, select the proper Xu/Q values from the Xu/Q table and record them in Column 2.
I 2.5 Record the proper radiation monitor reading in Column A.
EP-2-050 Revision 1 7 Attachment 7.1 (2sof224 ;
L DOSE PROJECTIONS BASED ON PLANT MONITORING DATA NOTE The gas channel should be used for the lowest range monitor that is on scale. The Main Condenser Evacuation System (MCES) Monitor is not normally used since any significant radioactivity will divert the MCES to the plant stack; use the plant stack monitor.
2.0 Record the flow rate in efm in Column C. See Attachment 7.1, Table 1, page 20, to determine efm to use in Column C.
I 2.7 Multiply A x B x C and record the product in Column D as noble gas l release rate.
2.8 Multiply D x E and record the product in Column F. If more than one release path exists, sum Column F to use for dose calculations.
2.9 Multiply D x G and record the product in Column H, as iodine release rate.
2.10 Multiply H x I and record the product in Column J. If more than one release path exists, sum Column H to use for dose calculations.
2,11 Enter the value from Column F in Column 1 in each row designated for noble gas (NG).
2.12 Enter the value from Column J in Column 1 in each row designated for Iodine (I).
2.13 Complete the calculations below for each row.
2.13.1 Multiply 1 x 2 and divide by 3. Record the result in Column 4 as the dose rate (mrem /hr) for whole body and for a child's thyroid.
2.13.2 Multiply 4 x 5 and record the product in column 6 as projected dose in mrem.
2.14 When there is a significant change in the monitor reading (1 20%);
wind speed (2 50%); wind direction (different sector) or factor of EP-2-050 Revision 1 8 Attachment 7 1 (jfot22J
DOSE PROJECTIONS BASED ON PLANT MONITORING DATA five (5) in dispersion factor, the dose projections should be revised on another sheet.
l 2.15 The data recorded on each sheet should be appropriately entered on the Dose Assessment Status Boards located in the TSC and EOF.
2.16 It should also be entered at the appropriate locations on the 10 mile Emergency Planning area maps locatr,d in the TSC and EOF.
30 ATTACHMENTS 3.1 Worksheets - Dose Projections Based on Plant Data (15 pages)
- 3.2 Table 1 - System Flow Rates (2 pages) 3.3 Figure 1, Example of Meteorological Data Available in the Control
! Room (1 page) 9 9
EP-2-050 Revision 1 9 Attachment 7.1 (for/2)
1 Dale / Time Pilot last name S10 nature
@ @ O O @ 0 Dose Rate 0
lodine /
0 Release Rale W @
Dose Rate N FLDW Release Hate DOSE DOSE MONITOR @t)'!?
CotNERSION FACTOR gTbu (hlh . FACTOR Tx'8 Gas io (DxGfltec FACTOR b$
PRM-IRE-5032(LO I 4.72E-04 PRM-IRE-5032(MI )) 6.70E-04 3.02 E4 6.45 E-6 1.55 E9 PRM-IRE-5032(HI i 1.00E-03 3.02 E4 6_f.5 E-% 1 ss v4 PRM-IRE-5107Aor 3 4.72E-04
_PRM-IRE-0100.1S 4.72E-04 PRM-IRE-0100.2S 4.72E-04 1.55 E9 6.70E-04 3.02 E4 6.45 E-0 PRM-IRE-0110(M.I ))
PRM-I RE-0110 (111 l 1.00E-03 0 0 @ @ @
(D Projected Dose Rate Wind Dose Rate Exposure Xu Duration LDCATION Factor o Speed mR/hr Dose = (2)x@ (mnem)
@kgj;hF mph @x@+@ (Hours) mRemWhole Body (EAB)
EAB-Noth Gas mnemY$id (EAB)
EAB-iodine mrem Wloie Body (2 m )
2nse -Noth Gas mrem iAh (2mi) 2 mm -iodine mrem WIolo Body (5 mi) 6 mh -Noth Gas mnem ij/oid (5 mi) s mise -iodine __
mrem Whole Body (10mi) 10,nm-Not>Ie Gas mnent @!bi (10mi) 10 mile -iodine
, @ Xuo Table _
EAB 2 miles 5 miles 10 miles
%@.Q s.t.
7.1 (-H
< -1.0 A U (-5) 1.3 (-0) 7.1 (-H
@ Wind Direction From
-1.0 to -0.9 8 5Al5) 4.5 (-0) 7.7 (-7) 7.1 (-7)
~"'"*" "' " "' '~"'"' "'~"
1 FUEL HANDLING -0.8 to -0.3 D .'8 H) 1 3.7 (-5) 1.11-5) 4.2(6) 2aui 8.5( 5> 2
- S) wi-Si ACCIDENT -0.3 io =
- 0.8 to +2.2 E
F 4.4 (-4) 1.31-4) 5.0 (-51 2 A l-5)
S
- 2.2 0 7.3 (4) 2.4(-41 1.1 ( 41 5 4(-51 EP-2-050 Revision 1 10 Att.achment 7.1 (5 of 22)
/ Dots / Time -
Pilot last name Siunature 6 O O O O G U (D @
Dose Rate gITOR FIDW Rosease Rate Dose Hale lodine / Helease Rate DOSE
! MONITOR RE[P)%
CotWERSiON FACIOR hh $fnxC)
DOSE FACTOR fo*ki gas (DxGfitoc FACTOR N PRM-IRE-0110 (IE) 4.72 E-04 PRH-IRE-0110(HID) 5.85 E-04 j PRM-IRE-0110(III) 5.81 E-04 i
4.86 E604 4.08 E-07 9.67 E408 PRM-IRE-0100.lS 4.72 E-04 PRM-IRE-OLQQ,2,9 AJ2_E-04 _
- 0) @ @ @ @ 6 Wind Dose Rate Exposure Projected Dose Rate Xu Duration Dose = @)=6 (mnem) lDCATION Factor o Speed mR/hr i
mpli (Hours) l @gMJ @a@+G mnem Wide Body (EAB)
(:AB-NoNe Gas (EAB) mnem V$
EAB-usine mnem wide Body (2 mi) 2 mise -NoNe Gas mnem j% (2mi) a mise -wiine mnom Wide, Dody(5 mi) a mise -Noue Gas mnom$1a (5mi) l . a mii. -iodine mnem vada Body (10mi) to mise-Noue Gas mnom $1 (10mi)
! no mise-iodine
@ Xu/O Table l 10 miles DJg.Td s.t. EAB 2 miles 5 miles
,'
- 1.3 06) 7.1(-7) 7.1 (-7)
A 1.105)
@ Wind Direction From <.t0 0 5.405) 4.5 06) 7.7 (-7) 7.1 (-7)
-1.0 to -0.9
~"'a*" "' '""' 2" ' """'
! WASTE GAS -0.8 to 0 3 0 1.8 ( 41 3.705) 1.1 (-5) ~-
4.2(61
-~ , o 05>
o.505, i SYSTEM FAILURE .o.3 io .o.. e 2.004>
4.4 ( 4) 1.3 04) 2.3eSi 5.0051 2.4 051
- 0 8 to *2.2 F l
> t 2.2 G 7.3 (4) 2.4 04) 1.l (-4) 5405) i EP-2-050 Revision 1 17 Attachment 7.1 (6 of 22)
1 0112/ Time .
Psint last name S10 nature
@ @ O O @ O G U (D Dose nate GD nelease Flate Dose nate lodine / fielease nale DOSE FlDW MoNnOn CoNVEf1SION DOSE Nuo ** (DxOflbec FAC10n ((g7 MONITOR nE M FAcTon EM 'c%ey) FActon '*?ei o
PRM-IRE-0110 (ID) _ M 2E-04 s PRM-IRE-0110(HID) _6 J7E-04 PRM-1RE-0110 (HI) _ftd2E-04 1.78E409 3.33Ef04 1.99E-04 P RM-I RE-0100dS._. _1JRE-DL PRM-IRE-0100.2S 4,78E-04 I
0 0 @ @ O
- 0) Dose Rate Exposuro Dose Rate Xu Wind Projecte([x@ (mnemi i
LOCATION Factor o Speed pR/hr Duration Dose = @)
y)x@ +0 (Hours)
- @gM3 mph mnem Wtmle Body (EAB) i EAB-NoNo Gas ~
mnem Vfy% (EAB)
EAB-iodine mnem WIole Body (2 mi) 2 mile -Noble Gas mnemNy'doid l (2mi) 2 mue -iodine mnem Wlole Body (5 mi) .
6 ndle -Noble Gas mriemk old (5 mi) 5 mile -lodisse mnem Wlolo Bodv(10mi) to rnile-Noble Gas 10 mile -iodine m ne m h old (10mi) l i @ Xuh Table
%'jaTd st. EAB 2 miles 6 miles 10 miles
- 3.3 08) 7.i(.73 7.i (.73 i @ Wind Direction From < i.0 A i.i eSi D 5.405) 4.5 061 7.7 (-7) 7.1 (-7) 2 -1.0 to -0.9 _
' "' ~ " "'
~""' *"
i LIQUID WASTE -0.8 to -0.3 D 1.G Mi 3.7 E5) 1.1(-5) 4.2001 2.aesi i.o osi SYSTEM FAILURE -0.3 io .o.. e 2.oo4i 4.4 04)
..S oSi 1.3 (-41 5.005) 2.4 (-5)
- 0 8 to
- 2.2 F
> t 2.2 O 7.3 (4) 2.4 (-4) 1.1 04) 5405)
~
12 Attachment 7.1 (7 of 22)
EP-2-050 Revision 1 .
1 0:12/ Time Print last name Sionatuse O .O -@ @ @ G O pasaaaa Rate (O 60 h Rate FtDW Release Rate Dose Rate lodine / DOSE MONITOR %NG CONVERSION FACTOR hh BxC)
I[g*gw DOSE FACTOR TxN "un 88 (DxG M FACTOR N PRM-IRE-0110(LO) 3.92 E-04 PRM-IRE-011D(MID} 07 v_nt.
PRM-IRE-0110(lit) 3.65 E-04 3.42 E105 4.28 E-03 5.09 E108 ,
PRM-IRE-0100.ls 4.02 E-04 PRM-IRE-0100.25 4.02 E-04 0 @ @
(D 0 Dose Rate Exposure Projected Dose Rate Xu Wind Speed mR/hr Dtiration Dose = 6)a@ (mnem)
LJOCATION Factor o mph (Hours)
@ l,'&'" W,! @w@ +0 mrem Whole Body (EAB) i EAB-NoNe Gas (EAB) mrum V$i EAB-iodine mnen wwm Body (2mi) 2 mile -Noble Gas mnemNv'foid (2mi) l 2 nele -lodine mrem Whole Body (5 mi) 6 mile -NoNe Gas mRom YIdM (5mi) a mise -iodine mnem wide sody(10mi) 10 mile-taoble Gas mnem hyro6 (10mi) 10 mile -lodine
@ Xui) Table s.i. EAB 2 miles 5 miles 10 miles De'M.TJ A 1.1 (-5) 1.3(-6) 7.1 (4) 7.1 N)
- @ Wind Direction From <.10 B 5 A (-5) 4.5 (-61 7.7 (4) 7.1 (-7)
' -l.0 to -0.9 LOCA, MAJOR
~""'"**
-0.8 to 0.3 I D 1.8 (-4)
'- ' ~ ' '
3.7 (-5) 2 ' '
1.1(-51 4.2(8) i .0 i-Si
- FUEL FAILURE -o.3 io .0.8 ' "
e 2.eui 4.4 (-4) 8.Si.53 1.3 (-4) 2.3i.5>
5.0 ( 51 2.4 (-51 0.8 to +2.2 F j 7.3 (41 2.4 (-4) 1.1 (41 5 A (-5)
> t 2.2 G 13 Attachment 7.1 (8 of 22) j EP-2-050 Revision i i
1 Dal2/ Time .
Print last name Sionature
@ O O O @ 0 0 O (D GD D se Hate Release Ik.te Dose Hale lodine / Helease Hate Dose MONnon mRsm FlDW DOSE Gas (DxGflWx: __ FACTOR b7df p lTOR REptD/c@ FACTOR hM Ih*gDxC) c FAC100 hm'El th PRM-IRE-0110(ID) 4.72 E-04 PRM-I R R-Q1.lD(HID). 4 h2 E-GA PRM-IRE-0 LIQ (({I) 1 72 E-04 6.17 E104 1.04 E-04 1.65 E108
!. PRM-IRE-0100.ls 4.72 E-04 PRH-IRE-0100.2S 4.72 E-04 0 G @
(D 0 @
Dose Rate Exposure Projecteci
' Dose Rate Xu Wind Speed mR/hr Duration Dose - G)=@ (mnemi LOCATION Factor o mph (Hours)
@ l,'"," Rf". f @x@ +0 mHem Whole Dody(EAB)
EAB-NoNe Gas (EAB)
I mnem %hi EAB-iodine mRom WhcAo Dody (2 mi) 2 mile -NoNe Gas
' mnem 93h (2mi) 2 mile -kxtine mnem Wide Body (5 mi) a mile -NoNo Oas mnem @oks (5 mi) i 5 mile -lodine mnem Wts Body (10mi) 10 mile -NoNe Gas l mnem $1bi (10mi) to mile-lodine l @ Xwo Table s.l. EAB 2 miles 5 miles 10 miles DJiaTd f
- 7.1 (-7)
<.1.0 A 1.105) 1.3 06) 71 (-7)
- @ Wind Direction From
-1.0 to -0.9 D 54 (-5) 4.5 06) 7.7 (-7) 7.1 (-7) i
! LOCA <1% FAILED I -0.0 to -0.3 0 1 Hi-4) ~-
3.7 ES) 1.1 (-5) ~
4 206)
- FUEL -o 3 io .o.e i 2oa>
4.4 04) e.505>
1.304) 2.3eSi 5.0( 51 i o e5>
2 A F5)
- 0.8 to
- 2.2 F
> t 2.2 G 7.3 (41 2.4 (-4) 1.104) 5405)
EP-2-050 Revision 1 , 4 Attachment 7.1 (9 of 22) i
7
- DatI/TinD
~Psint last name slanature e 0 g=/ U W CD Do** Hale O
(D
- Do** Hala Helaa5a m nose on cornierision FAcyon ggg
'1880888 'la's
_ IggmC),
nose pAcjpg; {gigg y, gas _ (DmOflLiec FACIOn N l MONITOR 81MNG tet r-na Isti:lRE:0110(IA1__ 5.09 E608 PRH-IRE-Oll0(HID) 4.27 E-04 8.56 E-06 3.42 EIO' PEN-IRE-D110(ill) _ 3.65 E-04 Inti:1aE_a10011s* . 1.DZ_E:0L __
PRH-1RE-0100.28 4.02 E-04_ __
1 et R-na _,
8.56 E,-05 5.09 Et08 23"II:lRE DIMit . 3.42 E405
_.3,17 E _
PRil-1RE-0002(HID) I_ .
1.6s n-na l run-tar-noo2 rut) O G 0 -@ @
i W Wind - Doso Rato Exposure ProJoct Dose Rato Xu Duration Dose = =@(mnemi IDCATION , Factor o Speed j[ (Hours) k En5Ns7nj moli u l mnemmie now(EAB) g , adhun Yb (EAD)
- EAB-io<ma. mrkanwe now(2mi) 2 mile -Notde Gas nma j h amn we no4 ((2 Smi) mil l
8 a* -lo*=
mnem YMu (5mi) a mne -socsa* _ _
mrkan m unowfl0ml) 10 mile-Nuble Gas I
nnun di (10mi) 8 "* ~ 3 '8"*
@ Xuo Table 2 miles 6 miles 10 miles IM.Q s 1. EAB n.3 (.e> 75 (:7: 7 (-in
<. o . 4 .: (.si
@ Wind Direction From 771-7) 7. (-il l ,-
-1.0 to c e [ c.4 (-si 4.s(-al
~a" '" *
- 1 i S.G. TUBE ROPTURE -0.8 to 0.3 n 1.8 04l 31(-s) 1.st-5) 2.arsi 4.2 ( el i.oi si l
-0.3 io .o.. e 2.e04i ..s 0si MAJOR FUEL FAILURE 80 8 to *2.2 F 4.4 04) 1.3 04) s.0( 61 2.4 Esl i f.t 04) S 40$) l
> t 2.2 G 73(4) 2.4 041 At t ac' ,ent 7.1 (lo ot 22) lCh/1gs )
15 El'-2-050 Revision i l
1 Dit:/ Time , "
l
'Psint last name O
81onature (D @ 0 0 0 W CD Dose flate fielease flate Dose IL.le Imlino/ 61elease flate DOSE DOSE loil engigg
$ FActon @),3 %g G^* ID=oflhac rAcron [f,lf MONITOR QM FAcron %"M' _
rah-1pE-01to itni 3.22E-na tati: IRE =alla_(MID) 4.J2E 4.175-07 7.65El08
- 6.11E404 1
f9H-IRE-0}l9_lHI). M 2E-04 25tI81.0100.1R_.- A.22n n1 A N nA Etti-IRA:0100.2a _
fau-un nna1 A.22r nA 7.45Et08 6.11s404 4.17s-06 '
A. 22K=0&_.-
FRH-laE-0001_ittin) 4.72E-04 PRM-1RE-0002 (1111 G .@ G .. O
@ @ Exposure Project 1 Dose Rate Wind Doso Rato IJDCATION Factor Spood pn Duration (Hours)
Dose = )=6 (mnemi US l,g,a [gll',",,y mph (!rO+
mnemwide sody(EAB)
EAD-Noth oss .
mnnil&% (EAB) l EAB-Imane mn nwide Body.(2mi) 2 mile -Natile oss (2mi) mnemk fykg 2 mae -ImNos anun wide nodv(S mi) 6 ndle - Nolde Oas mnomy$oid (5 mi) a mine -baine maan wium Dody(10mi) i mnom [b, (10mi)
- mile 'l*8ae
@ Xu/O Tobio i 5 miles 10 miles l
- M.Q s t. EAD
,,, g.33 2 miles i.3 g..i y.i g.n 7. 1-n
-@ Wind Diroction From <. 3
! 7.1 (-Fi g
-1.0 to -o.9 D 54l6) 4.5(-81 7.7 (-7) f _
'*'~ '"' %
i a" 'a *
- A "'
S.G. TUBE RUPTURE -o a to 0.3 0 f.a (-41 3.7 l-61 1.11-6) 4.21el 9'^
- 2. ui ..si-si 2.3i-si i o -si l < l% Fnited Fuel .o.3 io .o.. E 2 4 (-6)
- o a1o.2.2 r 4.41-4) 1.3( 4) 6.01-61 ,
> i 2.2 0 7.3 (41 2.4 ( 41 1.1 HI 6 A(-51 P l
EP-2-050 Reviaion 1 M At t acluuent 1.1 (12 of 22)'[
] ll 2 4
s .
I Dals/Tkne -
Pshd last nana Sionature l @ O O O O 0 G U (D @
Dose Hate FIDW nelease Hale Dose Hate lodine / nelsase I w o DOSE MONnOR~ CotNEllSION DOSE oas kN' MONITOR RE,A@ FACT 011 M Ih"gw c
BxC) FAC100 [nN gIng (D M lbec FACTOR l
PRH-IRE-55004 5.55 E-06 5.1 E03 FRH-IRE-5500R 5.55 E-06 5.1 R03 1.42 E105 8.56 E-03 5.09 E108 O
I W G G Wind 1
Dose Rate Exposure Projecte(I Dose Rate Ju l_OCATION Factor o Speed inR/lif Duration Dose = (2)xG (mnemi
@ la; Ma,!
mph ()=@ + 0 (Hours)
' mRomWhole Body (EAB)
EAD-Noble ons N tiaur mnom W"h (EAB)
EAD-iodine a ma. -tude oss mnan mioio now(2mi) l 2 nee -sookw g mnomS}y'dgi (2mi) f '
ndlem'Wiole Dody(6 mif 6 mile -Noble ons I
mnom yMai (5mi) a mue -lodiae adhn Wiole. Baly(10 mi) to mue-Noble oas
' Y ndwn hou (10ml) i to ndle -lodirm
- @ Xu/O Table DJ)aQ . s.i. EAD 2 miles 6 miles to miles
@ Wind Direction Frobi <. i.o A u l-a 1.a til 7.: t-n 7.u-n i -1.0 10 -0.9 0 5 4 (-51 4.5(-61 7JI-71 7.11-71
- MAIN. STEAM ' -no m -a. ~i i.2ai i.= ( e 2me asi-n
~"""" " '""' '" "'~" "
STEAM LINE BREAK -0.3 to *0.8 E 2.0 H1 8.51-51 2.3(-51 1.0 (-M
- Major Fuel Failure m a m 2.2 T u ni i.a si ..o ai 2*a
> e 2.2 o 7.3 (41 2.4 (-41 1.1 HI 6 4(-5) 1 EP-2-050 Revision 1 . 17 ; ac o:v.::. I. i 1
(4T
/1 of 22)l ChrlH]1 [ 6/lO[S
/ Dal3/ Time Print last name Signatura
! @ O O FLOW U
Release Rate e e D se Rate o
iodine /
O Release Rale W GD Dose Rate MONITOR COtNERSION DOSE DOSE l
MONITOR ngrJP FAcTon MM @i$c) FAcion Tx'e{ %;io Gas (DxGf b FACTOR M' PRM-IRE-5500A 5.55E-06 l
l 3.42E105 8.56E-03 5.09E108 PRM-IRE-5500B 5,55E-06 l
HOTE: For steso released through HCES on stack,i so S.G. Tuk t Rupture 1 irm.
Q) O @ @ @ l G Dose Rate Wind Dose Rate Exposure Projected Xu LOCATION Factor a Speed mR/nr Duration Dose = @x@ (mnem)
@l*oElcggyu c r mph 0)<0 +0 (Hours) mrem Whole Body (EAB)
EAB-Noble ces EAB-iodine mnem ETha (EAB) mrem Whole Body.(2 nli) 2 mile -Noble Gas 2 mile -lodine mHem k. old (2mi) mriem'Whole Body (5 mi) 6 mile -Noble Gas 6 mise iodine mnen; I![y'k'oid (5 mi) mnem Wido Dody(10mi) to mile Noble Gas ~
IU 10 mile -todine mnem S[Ivmid (10mi)
@ Xu/O Table
%IM.Td si. EAD 2 miles 5 miles 10 miles
@ Wind Direction From <. I.0 A 1.1 (-5) 1.3 (-6) 7.1(-7) 7.1 (-7)
-1.0 to -0.9 3 5 A 8-51 4.5 I-0) 7.7 (-7) 7.1 (-7)
MAIN STEAM -ae ie -ao c t2ai i.a (-si 2.s mi aan)
~""'"~" " '""' "~"' "'~"' "'
RELIEF VALVE -0.3 to *0.8 E 2.6 (-4) 6.si s) 2.3(-6) 1.0(-s)
Major Fuel Failure 0 aio.2.2 T (4 ai i.3 ai s.oi-s, 24i-si
> t 2.2 G 7.3 (4 ) 2.4 (-4) 1.1 (-4) s 4(-s)
EP-2-050 Revision 1 18 Attachment 7.1 (13 of 22)
i 1 Dali/ Time Paint last name Si0 nature
@ @ O FlDW O
Reloase Rate O O Dose Rale O
lodine /
O Release Rate W @
Dose Rate MONITOR CONVERSION DOSE DOSE MONITOR R$%'f FACTOR fdTg (gp3 C) FACTOR [DIF) " 'h t (DxGFhec FACTOR b%lf PRM-IRE-5500A 5.55E-06 3.42E05 8.56E-0: 5.09E08 PRM-IRE-5500B 5.55E-06 For ateam release < l through I'CES or itack, uso S.G. Tul e Rupturt Form.
NOTE:
(D 0 @ @ @ G Dose Rate Wind Dose Rato Exposure Projected Xu LOCATION Facicr o Speed mR/hr Duration Doso = (e)=@ (mrem)
@l@ Ma F mph @@+0 (Hours) mrem Whole Body (EAB)
- EAB-Nob.e Gas EAB-iodine mnem WS (EAB) mrem Whole Dody (2 mi) i 2 mile -Noble Gas mnem jjfoia 2 mise -iodine '
(2 mi) 5 mile -Noble Gas miiom'Whole Dody(5 mi) 5 mie -iodine mrem %%id (5 mi) 10 mile-Noble Gas mRom Whole Dod'(10mi) y
,10 mile -iodine mnom @how; (10mi)
@ Xui) Table Dg'g.Q a s.t. EAB 2 miles 5 miles 10 miles
@ Wind Direction From < - 1.0 A 1.1 (-5) 1.3 00) 7.1(-7) 7.1 (-7)
-1.0 to -0.9 0 5.4 05) 4.5 (-6) 7.7 (-7) t.1 (-7) iam 2a a 3">
MAIN STEAM -o" lo +a
-0.8 to -o.3 1
D
'2")
1.8 04) 3.705) 1.1(-51 4.2 ( 6)
ATMOS. DUMP VALVE .o.3 ,o.o., e 2.o ai o.505, 2.3(.5, , .o e5,
- 81 + 2.2 F 4.4 041 1.3 04) 5.0( 51 2.4 (-5)
Major Fuel Failure .
>
- 2.2 G 7.3 (4) 2.4 04) 1.104) 5.4 (-5)
El'-2-050 Revision 1 21 Attachment 7.1 (14 of 22)
I Dits/ Time Print last name S10 nature
@ @ O O @ 0 Dose Rate G
lodine /
U Helease Rale (D @
Dose Rate MONITOR COtNERslON FlDW Release Rate DOSE DOSE Gas MONITOR QQRipG FACTOR giqu (gp C) FACTOR Y)p3 ino (DxGfltec FACTOR [$'
PRM-IRE-5500A 5.55E-06 3.42E05 8.56E-0: 5.09E08 PRM-IRE-5500B 5.55E-06 (0 0 0 @ @ 6 Dose Rate Wind Dose Rate Exposure Projected Xu LOCATION Factor o Speed mR/hr Duration Dose - @x@ (mRom)
@lEcDF mph @@+G (Hours) mrem Whole Body (EAB)
EAB-NoNe Gas EAB-iodine - mnem9fyb (EAB) mRom Wholo Dody.(2 mi) 2 miie -NoNe Gas 2 mise -sodine
mrem yMai (2mi) s mite -Noue Gas m!iem'winio Body (S mi) 5 mite -lodine mRemShYoid(5 mi) mRom WIolo Body (10mi) 10 mile Noble Gas to mile -iodine mRom ShyYoks (10mi)
@ XuA) Table 98'M.T m?, di. EAD 2 miles 5 miles 10 miles (2) Wind Direction From <- 1.0 A 1.l l s) 1.3 (-6) U (-7) 7.1(-7)
-1.0 to -0.9 0 54 (-s) 4.5 (-6) 7.7 (-7) 7.1 (-7)
! MAIN STEAM -aa m-as ~I i.2 i-4 i i.a i-s> 2 si ei o.ai-7)
~""'" "
EFWP TURBINE .o;3 ,o l', "o'l:#'
4, o;'sl: " 3';.'s', - -
L'l"s',
T
~
Major Fuel Failure + 8 'o .2.2 4u.o i.3(-43 sus 2.4i-si
>
- 2.2 G 7.3 (41 2.4 (-4) 1.1 (-4) 5Als)
EP-2-050 Itevision 1 20 At t acinuen t 7.1 (15 of 22)
/ DitalTime q Print last name Sionaturn
@ O O O O O O O Release Raie (D GD Dose Rate MONITOR mggg FLOW Release Rate DOSE Dose Raio lodine / DOSE MONITOR RE@)$K) FACTOR QTg "0 (pi34c) FACTOR g,'g3 Tif * (DxGjClhec FACTOR N PRM-IRE-5500A 9.44E-05 6.17E104 4.17E-04 7.65E408 I
PRM-IRE-55008 9.44E-05 i .
@ O O @ @ O Dose Rate Wind Dose Rate Exposure Projected Xu LOCATION Factor o Speed mR/hr Duration Dose 6)x@ (mnem)
@ l,"o"n'i d"4F mph @a@ +G (Hours) mnem Whole Body (EAB)
EAB-Noble Gas g
, EAB -iodin. IE H m mrem V% (EAB) mrem Wide Body (2mi) 2 mise -Noble Gas
) 2 mise -iodine a '
mrem j }$i (2mi) 5 mile -Noble Gas mrem' Wide Dody(5 mi) 5 mise -iodine mnem S!")oid (5 mi) 10 mise-Noble Gas mrem Wide Body (10mi) d' mnem NyYoid (10mi)
! 10 mise -iodine l @ Xui) Table Wg.Td s.t. EAB 2 miles 5 miles 10 miles
@ Wind Direction From <. i.o 3 i., (.51 1.3 (-on 7.1(-7i 7.i(-7)
-i.0 to -0.o D 5.4 (-Si 4.5 (-Bi 7.7 (-7 7.1 (-7i
~~
i ain Bam -0.9 io -0.8 c i.2 (-4i i.3 i Si 2.5 (-si o.3(-7
-0.8 to -0.3 D 1.8(-43 3.7 (-5) 1.1(-51 4.2 ( 61
-0.3 to *0.8 E 2.6 (-4) 8.5 (-Si 2.3(-5) 1 0 (-53
< l% Failed Fuel 0.a io .2.2 7 4.u4i i.3 t43 5*5 2.4 (-Si
> t 2.2 O 7.3 (4) 2.4 (-4) 1.1 ( 4i 5405) l EP-2-050 Revision 1 21 Attachment 7.1 (l[ of 22)
/ Dita / Time Psht last name signatura
@ @ O O O (8 'O O (D GD MONITOR FlDW Release Hate Dose Hale lodine / Helaase Rale DOSE Dose Rate DOSE MONITOR n%$@
CONVERslON FAcTon JJ %*3axc) FAcTon f,'e3 "Tiio H 6"* (DxGblliec FACTOR N ,
PRM-IRE-5500A 9.44E-05
~.17E404 6 4.17E-04 7.65E08 PRM-IRE-5500B 9.44E-05 NOTE: For steena released throuah MC ES or s tack, use ' S.G. Tube Rupture form.
(D 0 @ @ @
Exposure Dose Rate Xu Wind Dose Rato Project
- LOCATION Factor o Speed mR/hr Duration Dose = dx@ (mnem)
@ l,'*" En",m""n ! mph @@ +0 (Hours)
' mrem Whole Body (EAB)
EAB-NoNo Gas EAB-iodine mnemVfy'dmid (EAB) i
~
mnem WIole Body.(2 mi) 2 mise -NoNe Gas mnem j jdmid
~
i 2 mae -iodine '
(2mi) mrem'Whole Body (5 mi) 5 mile -Noble Gas 5 mile -iodine mnem Sfijoid (5 mi) mrem Whole Body (10mi) 10 mile-Noble Gas (10mi) io mile -lodine m uo m k old
@ Xu,0 Table
- Delg.Td s i. EAB 2 miles 5 miles 10 miles
@ Wind Direction From ,. t.o A i.: Es) 1.3 tal 7.i(-71 7.i (-7)
-i.o to -0.0 0 s.4 05) 4.s Fe) 7.7 (-7) 7.s (-7)
Main Steam -o.O io.o.e 1 i.2m i.3 esi 3105) 2.si ei i.i(-51 o.3en 4.2( el g -0.8 Io -o.3
-o.3 to *o.8 D
E i.8 o4) 2.8e4) 0 5e6) 2.3tS) s.005)
<l % Failed Fuel o a io.2.2 T 4.4 o4i i.3 m s.oosi 2.4 esi l; > e 2.2 G 7.3 (4) 2.4 e4) s.: (-4) 5.405)
-j EP-2-050 Revision 1 22 Attachment 7.1 (l'/ of 22) i
i j
/ Dits/ Time
. Prial last name Sic, nature
@ O O O O O O O Helease Rato (D
Dose Raie FLDW Hosease Hale Dose Hate lodine / DOSE MON! TOR CNHSION DOSE MONITOR neap /tf FAcTOn MTku
'$iu"fI FACTOR YE] O8 (Oxofk FACTOR h@
PRM-IRE-5500A 9.44E-05 6.17E104 4.17E-04 7.65El08 PRM-IRE-55008 9.44E-05 NOTE: For atsam released thre ugh HCES or stack, use S.G. Tube Rupture Fo rm m e o e @ o Dose Rate Wirxl Dose Rate Exposure Projected Xu i LOCATION Factor o Speed mR/hr Duration Dose = (4)x@ (mnem)
)
$ ,% M a F mph @@+0 (Hours) mnem Whole Body (EAB)
- EAB-NotAs Gas
! EAB-iodine mnem V$b (EAB) mHom Wide Body (2 mi) 1 2 mise -Noble Gas ,
2 mile -Bodine
_ mnem S foia (2mi) mnom' Wide Body (5 mi) 5 mile -Nobie Gas s mise -iodine mnomY!$oid (5 mi) mrem Wido Dody(10mi) 10 mise-Noble Gas -
30 mise - kxiine mncmk!Noid (10mi) i
@ Xu/O Table 6 miles 10 miles
)
- M.Td s.t. EAB 2 miles 7.1(-7) 7.1(-7)
@ Wind Direction From < . l .0 A 1.1 (-5) 1.3 ( 6) l -1.0 to -0.9 5 A (-5) 4.5 (-6) 7.7 (-7) 7.1 (-7) c 2.S ai Om l Main Steam ae m -0 a 0.8 to 4.3 D i.2ai 1.8 (-4) i.3 (-Si 3.7 (-5) 1.1 (-5) 4.2 ( 6)
}
> Atmos. Dump Valve -0.3 10*0.8 E 2.6 (-4) 6.5( 5) 2.3(-5) 1.0 (-5) o a io.2.2 4.4 i-4i i .3 (.4i 5.0i.5i 24(-5) l <l% Failed Fuel F G 7.3 (4) 2.4 (-4) 1.1 (41 5.4 (-5)
> t 2.2 EP-2-050 Revison 1 23 -
Attachement 7.1 (18 of 22)
/ Dal2/ Time Print last name Signatura
@ O O O O O O O (D @
Dose Rate FLDW Release Rate Dose Rate lodine / Release Rate DOSE MONITOR NRSION DOSE MONITOR READ),NG FACTOR h^ph IA*DxC) pjg FACTOR $x'p3 gjas (DxGflhec FACTOR b$ __
m PRM-IRE-5500A 9.44E-05 _
6.17Ef04 1.04E-04 7.65E08 PRM-IRE-5500B 9.44E-05 l
(D 0 @ @ @ G 8 Dose Rate Wind Dose Rate Exposure Projected Xu LOCATION Factor o Speed mR/ly Duration Dose = (/)x@ (mrem)
F mph @x@ +0 (Hours) i
@l=f4f"m""na mRom Wiele Body (EAB)
- EAB-Noue Gas mnem Wyb (EAB) l EAB-iodine mnem Wtole Be#(2 mi) 2 mile -NoWe Gas (2mi) 2 mise -iodine ' '
mnem i]!ldrou mrem Wlole Body (5 mi) 5 mile -NoWe Gas l mnem ifyYoid (5 rai) s mise -iodine mnem WIole Body (10mi)
)
10 mile-Noble Gas mnom kIfy70u (10mi) 10 mile -iodine l @ Xui) Table DJM.TJ, al. EAB 2 miles 5 miles 10 miles
- 7.1 (-7) U (-7)
@ Wind Direction From < .1.0 A U (-5) 1.3 (-6)
-1.0 to -0.9 B 5 A FS) 4.5 06) 7.7 (-7) 7.1 (-7) 4 Main Steam e io e I"
i.2ai i.3 c5>
2 6( ai a a">
EFWP Turbine
' -0.3 to *0.8 E 2.604)
- 6.5( 5) 2.3FS) 1.0 05) 0.8io.2.2 4.4 o4i i.3 04i 5.oosi 24 esi
<l% Failed Fuel > t 2.2 e
O 7.3 (4) 2.4 (-4) 1.1 ( 41 5405)
EP-2-050 Revision 1 , 24 Attachment 7.1 (19 of 22) 4
SYSTEM FLOW RATES TABLE 1
- 1. The stack flow rate will vary as follows:
Normal RAB - 91,400 cfm Normal RAB + Containment Purge - 106,400 cfm SIAS - RAB and Shield Building ventilation may vary from 3,500 to 26,000 cfm
- 2. The FHB ventilation varies from 28,260 to 8,000 cfm Emergency Flow rate.
Actual flow rates should be obcained from Control Room data.
- 3. Main Steam Releases
- a. Atmospheric Dump Valves (ADV's) ,
A flow rate of 7.87 E3 cfm (two valves) or 3 99 E3 cfm (one valve) should be used in Column C. If an ADV is partially open, the flow is determined by lbm flow rate x (3.99 E3 cfm) = cfm 1 E6 lom/nr
- b. Stuck-open S.G. Saf ety ( Relief) Valve A flow rate of 9.08 E3 cfm per safety valve should be used for Column C. It is unlikely that more than one valve will be stuck.
1 valve = 9.08 E3 cfm 2 valves = 2(9.08 E3) cfm and so on If the value is stuck partially open, use the flow rate from Control Room and ratio the efm as follows:
lbm flow rate (9.08 E3 cfm) = cfm 1 36 Eo lbm/nr
- c. Emergency FU Pump Turbine Release The Emerg. FW Pump releases 188.8 cfm; use this number in Column -
C.
EP-2-050 Revision 1 25 Attachment 7.1 (Z#ofA1)
SYSTEM FLOW RATES
- d. Main Steam Line Break The Main Steam Line Break will not give a continuing release rate but will empty the S.G. in less than two minutes (assuming feedwater is stopped). Subsequently the only releases will be the amount of primary to secondary leakage. The Engineering Technical Assessment Group must be consulted for a flow rate for the primary to secondary leakage rate.
For Main Steam Line Break:
- 1) Record the' Main Steam Line Monitor reading prior to the break (conversion facto.- will not be valid after break).
- 2) Use 8.1 El efm for flow rate.
- 3) Use 2 min (1190- houri for release duration.
- 4) After initial release (2 min),' request Engineering Technical Assessment Group to provide flow rate of release due to ,
primary-to-secondary release and calculate release based on Reactor Coolant Concentration (let-down monitor, grab-samples, etc.).
EP-2-050 Revision 1 26 Attachment 7.1 CZlof)Gd
DOSE PROJECTIONS BASED ON PLANT MONITORING DATA
.1 FIGURE 1 WATERFORD 3 POINT GROUP SGENVIRO 03/16/83 12:00:00 NO. OF POINTS : 14 12:00:00 A48500 PRI METR TWR 33 FT WIND SPEED 3 58 M/S 12:00:00 A48510 PRI METR TWR 33 FT WIND DIR 240.0 DEG l
j 12:00:00 A48504 PRI METR TWR DIF TEMP PRI -0 95 DEG C j 12:00:00 A48502 PRI METR TVR 199 FT WIND SPEED 4.08 M/S 230.0 1?:00:00 A48512 PRI METR TWR 199 FT WIND DIR DEG 12:00:00 A48507 PRI METR TWR 33 FT AIR TEMP 20.60 DEG C
- 12:00:00 A48505 PRI METR T'.iR DIF TEMP SEC -0 95 DEG C l 12:00:00 A48513 PRIMARY METR TWR PRECIPITATION S 0.000 IN/HR .
12:00:00 A48501 BKUP METR TWR 33 FT WIND SPEED 2.12 M/S 4
12:00:00 A48511 BKUP METR TWR 33 FT WIND DIR 240.0 DEG 12:00:00 A48506 BACKUP METR TWR DIF TEMP -0.55 DEG C 12:00:00 A48503 PRI METR TWR 199 FT SIGMA THETA 19.5 DEG 12:00:00 A48508 PRI METR TWR 33 FT SIGMA THETA 21.0 DEG 12:00:00 A48509 BKUP METR 33 FT SIGMA THETA 20.8 DEG
)
i l,
1 i
EP-2-050 Revision 1 27 Attachment 7.1 &loS$$)
DOSE PROJECTIONS BASED ON FIELD MONITORING DATA 1.0 PU R POSE This attachment provides the methods for obtaining field monitoring team data, recording that data and utilizing field monitoring data for projecting doses at other off-site locations.
2.0 REFERENCES
2.1 Field monitoring will be performed in accordance with EP-2-060.
Data will be radioed by the monitoring team to the Health Physics Coordinator at the TSC or the Radiological Assessment Coordinator at the EOF when activated.
2.1.1 Record field monitoring data on the data sheet.
2.1.2 Calculate the Net Count Rate at each location by:
Total Sample Counts /5 - Total Background Counts /2 = Net Count Rate (cpm)
Record on the data sheet.
2.1.3 Record the D/C f acte r for the instrument used, on the data' sheet.
2.1.4 Determine the child thyroid dose by using the Child Thyroid Dose Rate Worksheet. Record the dose rate on the Calculation Worksheet, Block B.
NOTE The factor 1.85 E9 includes the child thyroid j
inhalation dose factor from Reg. Guide 1.109, l
Rev. 1, dated October 1977, Table E-9, and a child breathing rate of 7.04 liters per minute and appropriate unit conversions. The Dose Equivalent Iodine (D.E.I.) Factor incorporates the dose from other iodine isotopes not accounted for in the field measurement of air samples.
EP-2-050 Revision 1 28 Attachment 7.2(lof7)
DOSE PROJECTIONS BASED ON FIELD MONITORING DATA NOTE l The D.E.I. should be based on a conservative assumption of two hours.
2.2 Determination of whole body or child thyroid dose at other locations is performed using the Dose Projection Worksheet.
2.2.1 Complete the information at the top of the worksheet, including wind speed, wind direction, date and time.
2.2.2 Record the location for which monitoring data is available.
2.2.3 Record the whole, body dose rate (closed window reading from the data sheet) and/or child thyroid dose rate at that location in Blocks A and B.
2.2.4 Record the X/Q for that location in Block C. The X/Q can be determined from Attachment 7.5. .f NOTE For projections to be valid, the meteorological conditions must be nearly constant during the transit time from release point to monitoring point.
43 2.2.5 To determine the projected whole body dose at any other location:
l 2.2.S.1 Record the location.
2.2.5.2 Record the X/Q for that location in Block D.
2.2.5.3 Determine the dose rate by multiplying the known dose rate by the X/Q at the location of interest or concern and dividing the X/Q for the location of the known dose rate (Block A x D -h C) .
Record in Block E.
EP-2-050 Revision 1 29 Attachment 7.2(Zof7)
DOSE PROJECTIONS BASED ON FIELD MONITORING DATA 2.2.5.4 Record the anticipated or projected exposure in hours in Block F< (Use two hours unless specific data is available.)
2.2.5.5 Determine the projected whole body dose by multiplying the whole body dose rate by the release duration (Block E x F).
2.2.6 To determine the projected child thyroid dose at any other loca-tion:
2.2.6.1 Record the location.
2.2.6.2 Record the X/Q for that location in Block H.
2.2.6.3 Determine the dose rate by multiplying the known dose rate by the X/Q at the location of interest and dividing by the X/Q for the location of the known dose rate (Block B x H *-C). Record in block I.
( 2.2.6.4 Record the anticipated or projected exposure in hours in Block J. (Use two hours unless specific data ,is available.)
2.2.6.5 Determine the projected child thyroid d se by multiplying the projected child thyroid dose rate by the release duration (Block I x J). Record in Block K. -
2.2 7 Each worksheet can be utilized to cr'2 ject doses at more than one location based on field monitoring *ata at only one location. If projections are to be based on field monitoring at other i
> b locations, separate worksheets should be used.
3.0 ATTACHMENTS 3.1 Data Sheet - Dose . ate and Air Sample Data Log 32 Child Thyroid Dose Rate Worksheet 3.3 Calculation Worksheet 3.4 Figure 1 - Dose Equivalent Iodine Correction Factor EP-2-050 Revision 1 , 30 Attachment 72($of7) ,
m
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DTn A Ni T LU m A AO D TC2 G O (
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D OT E LA T FR A m R N EO E LI S PT O MA D AR SU D M
)
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SD -
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CW - a.
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CilILD TilYROID DOSE RATE WORKSilEET .
- SAMPLE A B C D E F a
- g. net V 1. f D.E.I.
Number Time D/C sasiple f{
' Location CPH Fac tor Conversion Child Thyroid Dose-S (from ( cu. ft. (Fig. 2) Factor Rate (arem/hr) y data) (from data )
- w 2.97E-02 N' #
l Multiply A x B', divide by C & multiply by D x E to get F:
(A x B/C) x D x E = mrem /hr.
The conversion factor converts DPM to uC1, cu. ft. to cc, and uCi/cc to mrem /hr.:
(4.55E-07 uCL/Dbd (3.53E-05 cu. f t./cc)(1.85E609 mredi/hr-cc/uci) . '
- 2.97E-02 arem/hr/DPH. ~
Elt-2-050 Revision 1
, 32 Attachment 7.2 (5 of 7 )
/,' ,. I
- '.i!
DOSE PROJECTIONS BASED ON FIEl.D.,HONITORING DATA Q
CALCULATION WORKSilEET Data 1.ocation: Date: , Time:
- 1. Field Monitoring and Meteorological Data (A) Uhole Body Dose Rate: mR/hr WiM S d- qd's (B) Child Tliyroid Dose Rute: mR/hr Wind Direction (C) X/Q: sec/m *(for Field Honitoring Data Location)
- 2. Projected Whole Body Dose DA E F G Location of X/Q (sec/m ) for Dose Rate . Exposure Duration Dose mrem Interest Location of Interest A x (Di C) llours ExF EAB
- 2. mlLES 5 mit,ES ,
10 M i t,G S
- 3. Projected Child Thyroid Dose HA I J K
' Location of X/Q (sec/m3) for Dose Rate Exposure Duration Child Thyroid Interest Locatton of Interest B x (11 I C) llours Dose IxJ mrem _
EAT 3 .
- 2. MI L E S S mlLES 10 WlltJ'S
- D and 11 are X/Qs for t he ' location of interest or concern and can be determined f rom Attachment 7.1 Dose
' Projections Based on Plant Honitoring Data and 7.5, Heteorological Data.
3 Calculated hyt EPd2-050 Revision.! . 33 Attachment 7.2 (4,or 7)
/
J ' ' " l8 FIGURE C
,5! . K ,[
COSE KUIVALINT ICDINE CRRICTICH FACTCR ,
a
, . I 3 %
w
( e
. l 9
N = I N
- - . g
\
e %. ,
,e I
.R
- e m
.m
.N m
.e n .
.a g .
. w
. W
- A
,e p.-- N i.
m:: -
8
%.m 1' *,
mN
.a F-N >=
. .e e ..
w ~
N
- . 's.e b .
s g a w t
= . s .e
- i. .
a w .a er
. .a
- P. 2 w.
. . w .. -
w a
- =
e m
' -= =,
g L
- s . . . . ,
l o
a o e a a
- e. S. . e. m. u.
== . - . .
Soww w<urom . .
/
e
, - --,, - - - - , , , . - , ,.n , --- -- , ,,----
DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE 1.0 PURPOSE This attachment provides the methods for calculating projected off-site doses when the concentration of the isotopes released is known and the flow rate is determined.
2.0 PROCEDURE 2.1 Determination of the whole body dose at any specific off-site loca-tion is performed using Worksheet 1.
2.1.1 Complete the information at the top of Worksheet 1, including the date, time, wind speed, and direction for the projection being calculated.
2.1.2 Record in Column B the concentration of each isotope being released based on sample analysis or other means of identifying the radionuclide composition of the release. Ensure that the concentrations are expressed in terms of uCi/cc.
2.1.3[MultiplytheconcentrationsrecordedinColumnBbythedose factor for that isotope (Column C) and record in Column D.
NOTE The dose factors are determined from Reg. Guide 1.109, Rev. 1, dated October 1977, Table B-1.
Conversion f actors of 1.14 x 10f to convert mrem-m 3 /pCi-yr to mrem-cc/pCi-hr; 472 to convert cfm to ec/sec; and 1 x 10' to convert cc to m3 are included in the dose factor.
i 2.1.4 Sum the results of Column D.
2.1.5 Record the specific location for which the projection is being made in Column E. Several locations may be used for the specific radionuclide mix as measured. Calculations will be accurate as long as the radionuclide concentrations remain constant.
2.1.6 Record the sum of Block D in Column F.
EP-2-050 Revision 1 35 Attachment 7.3(lord) i
DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE 2.1.7 Record the flow rate for the release path in Column G. Ensure that flow is recorded in cubic feet per minute (cfm).
2.1.8 Record the X/Q for the specific location in Column H. X/Q is detarmined in Attachment 7.5.
2.1.9 Multiply the sum of Block D, the flow rate and the X/Q (Column F x G x H) to determine the whole body dose rate at that location in terms of mrem /hr. Record the result in Column J. This result is the projected dose rate at the specific location identified and should be used to evaluate the need for protective action (s) snd to compare with field measurements.
2.1.10 If the release duration is known or can be projected, enter tne duration in hours in Column K.
2.1.11 Determine the projected dose by nuitiplying the dose rate at the specific location by the release duration (Column J x K).
. 2.2 Determination of the limiting thyroid dose at any specific off-site Y location is performed using Worksheet 2.
NOTE The limiting dose is to the child (5-10 yrs) thyroid and should be calculated first.
2.2.1 Complete the information at the top of Worksheet 2, including date, time, wind speed and direction for the projection being calculated.
2.2.2 Record in Column B the concentration of each iodine isotope being released, based on sample analysis or other means of identifying the radionuclide composition of the release. Ensure that the concentrations are expressed in terms of JLC1/cc.
2.2.3 Multiply the concentrations recorded in Column B by the dose factor for that isotope (Column C) and record in Column D.
EP-2-050 Revision 1 36 Attachment 7.3(2 Lor $)
- 1. . .
DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE NOTE The dose factors are determined from Reg. Guide 1.109, Rev. 1, dated October 1977, Table E-9, and a child breathing rate of 7.04 liters per minute. Conversion factors of 472 to convert cfm co ec/sec and 6 x 10 to convert liters /per minute to cc/hr are included in the dose factor.
2.2.4 Sum the results of Column D.
2.2.5 Record the specific location for which the projection is being made in Column E. Several locations may be used for the specific radionuclide mix as measured. Calculations will be accurate as long as the radionuclide concentrations remain constant.
2.2.6 Record the sum.of Block D in Column F.
2.2.7 Record the flow rate for the release path in Column F. Ensure that the flow rate is recorded in cubic feet per minute.
2.2.8 Record the X/Q for the specific location in Column H. X/Q is determined in Attachment 7.3 or 7.4.
2.2.9 Record the fraction of radiciodines being released through the charcoal filters. If the filter efficiency is unknown, use 0.05 as the release fraction.
NOTE If the flow path does hot include a filter system or the sample was obtained downstream of the filters, the release fraction is 1.
2.2.10 Multiply the sum of Block D, the flow rate, the X/Q and the release fraction (Column F x G x H x J) to determine the EP-2-050 Revision 1 37 Attachment 7.3 (3of 6) i
DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE projected thyroid dose per hour exposed in terms of mrem /hr exposed. Record the result in Column K.
2.2.11 If the release duration is known or can be projected, enter the duration in hours in Column L.
2.2.12 Determine the projected dose by multiplying the dose per hour ex-posed by the release duration (Column K x L). Record the projected child thyroid dose in Column M.
3.0 ATT'ACHMENTS 3.1 Projected Whole Body Dose Worksheet 1 3.2 Projected Thyroid Dose (Child Thyr'id) Worksheet 2 O
e EP-2-050 Revision 1 38 Attachment 7.3(i[or[p)
. PROJECTED WHOLE S0,0Y 00SE '
l WORKSHEET 1 l
-i
( ..
,' Wind Speed: mph Wind Direction: From: Date: Time: a.m./p.m.
, A . B. l C l 0
' Concentration Oose
. Isotope (uCi/ce) Factor BxC Kr-85m l l 63. l Kr-85 l l .624 l Kr-87 l 319. l i
Kr-88 l l 791. l Kr-89 l [ 893. l Xe-131m l 4.92 l Xe-133m -
l 13.5 l .
, Xe-133 l l 15.8 l .
Xe-135m l l 168. I
, ; Xe-135 l 97.4 Xe-137 l l 76.4
. Xe-138 l 475. l ,
l Block D = -
l E l F G H J K L Dose Rate Excosure Oose Flow Rate X/Q (mrem /hr) Duration (mrem) location Block 0 (CFM) (sec/m3 ) pxgxg '{hr) JxK m l 1
l -
l 2 Miles l
5 Miles
' 10. Mil'es '
l Calculated by: _
l EP-2-050 Revision l Attachment 7 3( [of d) 3Y .
, . _ _ _ . , _ _ _ . . , _ - - _ . _ . . , , _ _ - , , - . . , , _ . . , , . , _ , . . . _ . , . , . _ , _ _ ,,,,.,-,,m._,.
- PROJECTED THYROID DOSE (CHILD THYROID)
WORKSHEET 2 Wind Speed: mph
, Wind Direction: Frcm: Date: Time: a.m./p.m.
. CHILD THYROID A i B 'C l 0 Concentration Dose Isotope uCi/cc Factor 8xC I-131 l 8.75ES l I-132 l 1.04E4 l I-133 l 2.08E5 l I-134 l 2.74E3 l l I-135 h ll 4.27E4 - l
' Block 0 ~=-
(' , E F l G H ! J K L l M Dese Ra'te (prren/hr Exposure Dese Flow Rate X/Q Release exposed) Duration (mem)
Location Block D (CFM) (sec/m3 ) Fraction FxGxHxJ (br) ~ Xxt EAB l 2 Miles l l l 5 Miles l l l l i
10 Miles l -
! l' l.,
l I l Calculated by:
. 't l,
I
's -
EP-2-050 Revision l hp Attachment 7. (d ofgf)
~
e
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, . + , . , , , , , , , ,
DOSE PROJECTIONS BASED ON FSAR ACCIDENT DATA 1.0 PURPOSE This attachment provides a method for calculating the projected dose rate at the EAB. It is based upon nine accidents that were analyzed in the FSAR.
NOTE This technique should be used only when there is no plant or field monitoring data available.
7.t should be used only as a first approximation and quickly replaced as plant and/or field data t'ecomes available.
2.0 PROCEDURE ..
2.1 From the nine accidents identified on the worksheet, select the type of accident based on the actual occurrence (Attachment 7.4, page 3, FSAR Accident Assuuptions, provides background information for this selection and is used for additional data). If no selection is possible, choose the worst case accident.
2.2 Using the Short Form worksheet, develop the X/Q at the Exclusion Area Boundary (EAB) and record in the appropriate location on the FSAR Accidents worksheet. X/Q = Xu/Q from Column 2 divided by wind speed from Column 3 on worksheet.
2.3 Multiply the X/Q by the appropriate dose factor (includes correction factor) for that accident (whole body and/or child thyroid) to obtain the projected dose at the EAB and record.
l l 2.4 Additional worksheets are to be used to calculate doses at other distances using the appropriate dispersion (X/Q) factors.
3.0 _ ATTACHMENT 3 .1 FSAR Accident Assumptions EP-2-050 Revision 1 41 Attachment 7.4(/or/f)
FSAR ACCIDENTS - DOSE PROJECTIONS WORKSHEET Wind Direction:
Date: - Time: -
Dose Factor Dose Rem Whole Body Whcle Body ACCIDENT
- X/Q* Child Thyroid Child Thyroid Main Steam Line Break x 2.55 E-2 7.lo E1 Inadvertent Steam Dump 1.02-E1 6 73 E3 CEA Ejection Accident x 8.71- E9 2.47 Eb Letdown Line Break x 2.7 9- E1 d.30 E3 S/G Tube Rupture x 4.o1 4.bb El Waste Gas System Leak x Loss of Coolant Accident x 6 E2 2 73 E3 .
Liquid Waste Release x 1.91-2.54 E2 Fuel Handling Accident x 8.55 3 64 El
- For Exclusion Area Boundary, 914 m. Calculated by:- -
EP-2-050 Revision 1 42 Attachment 7.4 (jEofj[)
l l
4 6
_ _ _ .- _ _ - - _ . - ~ _. . . , -
FSAR ACCIDENT ASSUMPTIONS This attachment provides the basic assumptions and radiological consequences (Design Basis) for the incidents that are not expected to occur but are postulated because their consequences would include the potential for the release of significant amounts of radioactive material. This attachment is to be used when instrumentation used for assessment is off-scale or inoperable.
Identify the type of incident which has occurred from the nine incidents defined in this attachment. If no identification is possible, use the most restrictive accident which cannot be reasonably excluded.
The information given below should be used in ratioing and adjusting assumed FS4R values with any known actual values in the event of an incident at Waterford 3 Steam Electric Station.
IDENTIFICATION AND RADIOLOGICAL CONSEQUENCE ASSUMPTIONS
- 1. Main Steam Line Break This incident is defined with a simultaneous loss of off-site power.
Steam is vented directly to the atmosphere.
- 2. Inadvertent Steam Dump For an inadvertent opening of a steam generator atmospheric dump valve with a concurrent single f ailure of an active component and loss of off-cite power, the activity released from the Steam Generators is immediately vented to the atmosphere.
- 3. Control Element Assembly (CEA) Ejection Accident this accident assumes a loss of off-site power at the time or turbine trip and a 6.5 pCi/s I-131 dose equivalent for the primary system (activity in the coolant systems prior to the accident).
- 4. Primary Sample or Letdown Line Break For primary sample or letdown line break incidents, a two-inch schedule 160 pipe is analyzed. A rupture outside the containment causes a release to the Reactor Auxiliary Building (RAB).
EP-2-050 Revision 1 43 Attachment 7.4(2[ofM)
FSAR ACCIDENT ASSUMPTIONS
- 5. Steam Generator Tube Rupture (SGTR)
This accident assumes a loss of off-site power and allows transport of reactor coolant into the main steam system. Release is via the Steam Generator safety valves and atmospheric dumps.
- 6. Loss of Coolant Accident (LOCA)
An LOCA provides a release path to the environment via containment leakage pathways.
- 7. Radioactive Waste Gas System Leak or Failure
~1his incident assumes an unexpected and uncontrolled release to the atmosphere of radioactive xenon and krypton fission gases.
- 8. Liquid Waste System Leak A Liquid Waste System leak or failure results in a release to the atmosphere and a release of all liquids in the Boron Management System (BMS) and Waste Management System (WMS). to the Reactor Aux-iliary Building (RAB). Off-site doses will occur as a consequence of released noble gases and iodines assumed to volatilize from the spilled liquids.
- 9. Fuel Handling Accident a fuel handling accident is the most restrictive accident defined in the FSAR.
J l
EP-2-050 Revision 1 44 Attachment 7.4 ( of h )
METEOROLOGICAL DATA 1.0 PURPOSE This attachment provides two alternative methods or obtaining meteorological data required to perform dose projection calculations. It should be used when data from either the primary or backup meteorologica.'. tower is not available on the CRT in the Control Room or in the Computer Room.
2.0 PROCEDURE 2.1 The alternative methods for obtaining meteorological data are:
2.1.1 Dispatch an individual to the primary meteorological tower to record the following data from the analog recorders at the tower location:
Instruct the individual at the tower to turn the digital selector switch to the desired parameter, record the digital readout and report the value.
Delta T (60 m - 10 m) ----
x (2.78 *C) = - - *C Wind Speed (10 m) - x (2.24 mph /mps) =- mph (mps is meters per seconds; mph is miles per hour)
Wind Direction (10 m) ------ -
NOTE If primary tower data is not available, instruct individual to go to ba. 9 tower.
2.1.2 Contact the National Weather Service (NWS) by commercial telephone at (504) 522-7330.
Obtain the following information from the NWS:
I Weather forecast for next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> EP-2-050 Revision 1 45 Attachment 7.5(/of/h)
l METEOROLOGICAL DATA Temperature lapse rate = -- ---- -
Wind Speed =
Wind Direction = -
2.1.3 Determine the appropriate Pasquill stability class from the following table based on data obtained in section 2.1 above.
Class Delta- T- (60 r - 10 m) C A - Very Unstable <-1.0 B - Moderately Unstable -1.0 to -0.9 C - Slightly Unstable -0.9 to -0.8 D - Neutral -0.8 to -0.3 E - Slightly Stable -0.3 to 0.8 F - Moderately Stable 0.8 to 2.2 G - Very Stable >2.2 Stability Index -
2.2 The two alternative methods for determining the dispersion f actor (X/Q) are:
2.2.1 Meteorological dispersion tables based en Pasquill stability class, wind speed and downwind distance. These tables are used as follows:
Select the desired downwind distance in miles for which the X/Q value is to be calculated:
' Downwind distance = -------- miles Select the appropriate X/Q from the tables given on pages S-18 based on wind speed, desired downwind distance and staLility class (from Attachment 7.1, section 2.4). If the wind speed and,'o.-
distance falls between two values on tne tables, use the distance with the higher X/Q value. Record below.
EP-2-050 Revision 1 46 Attachment 7.5 (,2bof/$)
METEOROLOGICAL DATA Downwind Stability Wind Time Distance Class Seeed- (moh) XZS (sec/m T To determine X/Q at locations away from the center line of the plume, use the Emergency Planning Zone (EPZ) Isopleth Overlays described in step 2.2.2 below.
2.2.2 Estimates of atmospheric dispersion values can be obtained using isopleth overlays based on the atmospheric stability class and wind speed.
NOTE Isopleth overlays have been developed for stability Class B (unstable), D (neutral), and F (stable) only. Isopleth overlays are located with other emergency response-dose assessment equipment.
Using the stability index from section 2.2 above, select:
Isopleth for class B for Stability Class A, B or C Isopleth for class D for Stability Class D Isopleth for class F for Stability Class E, F or G Select the appropriate overlay based on the atmospheric stability class (B, D, F).
l Align the center axis of the isopleth plot with the centerpoint l
(plant) of the Emergency Planning map.
l Orient the overlay such that the projection occurs in the downwind direction. (Wind direction recorded as from 270 West should orient the overlay in a 90 East direction.)
EP-2-050 Revision 1 47 Attachment 7.5(3Iof/f)
1 l
l METEOROLOGICAL DATA 1
Once aligned, locate all critical locations. Choose the nearest X/Q line toward the centerline from each critical location.
From the table on the overlay, use the appropriate wind speed (from section 2.1) and Xu/Q line number to obtain X/Q and record below. Repeat for all critical locations.
Location Wind Speed X/Q The above X/Q values can be used for calculating dose projections in procedure Attachments 7.2 (Dose Projections Based on Field Monitoring Data), 7.3 (Dose Projections Based on Known Isotopic Release Data) and 7.4, (Dose Projections Based on FSAR Accident Data).
I i.
I EP-2-050 Revision 1 48 Attachment 7.5(f!ol/[)
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