ML032050199
| ML032050199 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/14/2003 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HP/0/B/1009/026, Rev 5, SH/0/B/2005/001, Rev 2 | |
| Download: ML032050199 (72) | |
Text
P Duke drpowere A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd.
CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax July 14, 2003 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Corporation Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 Emergency Plan Implementing Procedures Please find enclosed for NRC Staff use and review the following Emergency Plan Implementing Procedures:
HP/O/B/1009/026, On-Shift Offsite Dose Projections (Rev. 005)
SH/0/B/2005/001, Emergency Response Offsite Dose Projections (Rev. 002)
Procedure SH/0/B/2005/001 has a restricted change that will be made into a permanent revision within 30-60 days.
These revisions are being submitted in accordance with 10CFR 50.54(q) and do not decrease the effectiveness of the Emergency Plan Implementing Procedures or the Emergency Plan.
By copy of this letter, two copies of the above documents are being provided to the NRC, Region II.
If there are any questions, please call Tom Beadle at 803-831-4027.
D. M. Jamil Attachments
,64'5 www. duke-energy. corn
S
- v U.S. Nuclear Regulatory Commission July 14, 2003 Page 2 xc (w/attachments):
L. A. Reyes U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 (w/o attachments):
R. E. Martin NRR Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, DC 20555-0001 E. F. Guthrie Senior Resident Inspector (CNS)
U.S. Nuclear Regulatory Commission Catawba Nuclear Site
Page 1 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE RP/O/A/5000/001 RP/0/A/5000/002 RPIO/A/5000/003 RP/O/A/5000/004 RP/O/A/5000/005 RP/0/A/5000/06 RP/O/A/5000/006 A RP/0/A/5000/006 B RP/O/A/5000/006 C RP/O/A15000/007 RP/0/A15000108 RP/O/BI5000/008 RP/O/A/5000/009 RP/OA/5000/O 10 RP/O/A/50(K)/ I I RP/O/B/5000/1 2 RP/O/B/5000/ 13 RP/O/B15000/ 14 RP/0/A/51
/X0 I 5 RP/0/B/5(HKt).!16 RP/O/B/5000/ 17 TITLE Classification of Emergency (Rev. 015)
Notification of Unusual Event (Rev. 036)
Alert (Rev. 039)
Site Area Emergency (Rev. 041)
General Emergency (Rev. 041)
Deleted Notifications to States and Counties from the Control Room (Rev. 015)
Notifications to States and Counties from the Technical Support Center (Rev. 015)
Deleted Natural Disaster and Earthquake (Rev. 021)
Deleted Spill Response (Rev. 021)
Collision/Explosion (Rev. 007)
Conducting A Site Assembly or Preparing the Site for an Evacuation (Rev. 016)
Deleted Deleted NRC Notification Requirements (Rev. 029)
Deleted Core Damage Assessment (Rev. 005)
Deleted Deleted July 14, 2003
Page 2 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE RP/O/A/5000/01 8 RP/O/B/5000/019 RP/OIA/5000/020 RP/O/A/5000I021 RP/OIB/5000/022 RP/IOB/5000/023 RP/O/A150001024 RP/IOB/5000/025 RP/01B/5000/026 RP/O/B15000/028 TITLE Emergency Worker Dose Extension (1/15/96)
Deleted Technical Support Center (TSC) Activation Procedure (Rev. 017)
Deleted Evacuation Coordinator Procedure (Rev. 004)
Deleted OSC Activation Procedure (Rev. 01 1)
Recovery and Reentry Procedure (Rev. 003)
Site Response to Security Events (Rev. 005)
Communications and Community Relations EnergyQuest Emergency Response Plan (Rev. 001)
July 14, 2003
Page 3 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE HP/O/B/1000/006 HP/01B/1009/001 HP/I/B/1009/003 HP/0/1B/1009/004 HP101/B1009/005 HPO/B/1009/006 BPIO/B/1009/007 HP/O/B/1009/008 HP/O/B/1009/009 HP/0/B/1009/014 HP/0/B/ 1009/016 HP/O/B/1 009/017 HP/l/B/1009/017 HP/2/B/ 1009/017 HP/O/B/ 1()9/018 HP/O/B/I0()9/019 HP/OIBI 1009/024 TITLE Emergency Equipment Functional Check and Inventory (Rev. 055)
Radiation Protection Recovery Plan (Rev. 008)
Radiation Protection Response Following a Primary to Secondary Leak (Rev. 008)
Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 028)
Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 016)
Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 008)
In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 019)
Contamination Control of Injured Individuals (Rev. 015)
Guidelines for Accident and Emergency Response (Rev. 039)
Radiation Protection Actions Following an Uncontrolled Release of Radioactive Material (Rev. 008)
Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev. 01 1)
Deleted Deleted Deleted Deleted Emergency Radio System Operation. Maintenance and Communication (Rev. 010)
Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)
July 14, 2003
Page 4 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE HP/O/B/1009/025 HP/O/B/1009/026 SHF0/B/2005/001 SH0/IB/2005/002 OP/0/A/6200/021 SR/I/B/2000/001 SR/O/B/2000/002 SR/O/B/2000/003 SR/O/B/2000/004 TITLE Deleted On-Shift Offsite Dose Projections (Rev. 005)
Emergency Response Offsite Dose Projections (Rev. 002) (Restricted Change)
Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev. 002)
Deleted Standard Procedure for Public Affairs Response to the Emergency Operations Facility (Rev. 004)
Standard Procedure for EOF Services (Rev. 002)
Activation of the Emergency Operations Facility (Rev. 009)
Notification to States and Counties from the Emergency Operations Facility (Rev. 005)
July 14, 2003
ao2)
Duke Power Company (I) ID No.
It rIomnoos926 PROCEDURE PROCESS RECORD Revision No.
005 PREPARATION (2)
Station Catawba Nuclear Station (3)
Procedure Title On-Shirt Olfsite Dose Proiections (4)
Prepared By 6
_2 Datc 7- /
-c.3 (5)
Requires NSD 228 Applicability Doination? If Applicability Determination is required, attach NSD 228 documentation.
El Yes (New procedure or revision with major changes)
O No (Revision with minor changes)
O No (To incorporate previously approved changes)
(6)
Reviewed By (QR)
Date 7110
&CO03 Cross-Disciplinary Review By (QR NA Datc 1/0-Z"Z Reactivity Mgmt. Review By (QR) NAf3 Date 7/iO/h2oO3 Mgmt. Involvement Review By (Ops. Supt.)
NA.Af Date 7/l6/ZO03 (7)
Additional Reviews Reviewed By Date Reviewed By Date (8)
Temporary Approval (if necessary)
By (OSMQR)
Date
_,~1 By (QR)
Date (9)
Approved By C
e Date 7-1A O-PERFORMANCE (Compare with control copy every 14 calendardays while work is being performed.)
(10)
Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (I I)
Date(s) Performed wVork Order Number (WO#1)
COMPLETION (12)
Procedure Completion Verification:
O Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA. as appropriate?
O Yes 0 NA Required enclosures attached?
O Yes 0 NA Data sheets attached. completed, dated, and signed?
O Yes 0 NA Charts. graphs, etc. attached. dated, identified. and marked?
O Yes 0 NA Procedure requirenents met?
Verified By
_ate (1 3)
Procedure Compietionl Approved Dlate (14)
Remarks (A fac/t additiornal pages, ift e esarr)
Duke Power Company Catawba Nuclear Station On-Shift Offsite Dose Projections Reference Use I Procedure No.
HP/01B/10091026 Revision No.
005 Electronic Reference No.
CP00945J
HP/IOB/1009/026 Page 2 of 13 On-Shift Offsite Dose Projections
- 1. Purpose The purpose of this procedure is to provide on-shift Radiation Protection (RP) personnel instruction for using the Raddose 5 Dose Assessment Software (DAS) computer program to project downwind offsite dose to the public and provide guidance for completing offsite dose sections on an Emergency Notification.
- 2. References 2.1 RP/O/A/5000001 Classification Of Emergency 2.2 EPA 400-R-92-001 Manual of Protective Action Guides and Protective Actions for a
Nuclear Incidents 2.3 Earth Tech RADDOSE 5 Operator's Manual 2.4 PIP # C-03-03436 - Unit Vent Flow Computer Point Not Indicating Properly
- 3. Limits and Precautions None
- 4. Procedure 4.1 Procedure use 4.1.1 Obtain a Working Copy of this procedure.
4.1.2 Use this procedure during emergency conditions, including exercises and drills.
Perform dose assessment when Operations Shift Manager (OSM) or On-Shift Emergency Coordinator notifies RP to perform this procedure due to declaration of a site Emergency Action Level (EAL) classification.
Perform on-shift dose assessment prior to availability of Emergency Response Organization (ERO) dose assessor i the TccliciCal Support Cenrcr (TSC) or Emergency Operations Facility (EOF).
HP10/3B/1009/026 Page 3 of 13 NOTE:
This procedure may be performed in sectional parts to evaluate and assess offsite dose from gaseous radioactive releases that may occur.
This procedure describes information for using Raddose 5 (Earth Tech Raddose 5 Operator's Manual) in an abridged form where steps are performed for a single offsite dose projection. IF multiple offsite dose projections are required, reports can be obtained by repeating procedure steps.
CAUTION:
Catawba Engineering has determined that the Unit Vent Flow Monitor may not indicate properly for flow rates < 9.75E+4 ft3/min (PIP # C-03-03436).
Until this problem is fully resolved, Raddose-5 Automatic Version will NOT function properly (PIP # C-03-03436).
4.1.3 Go to Section 4.3 (DO NOT USE SECTION 4.2).
4.2 Raddose-5 Automatic Version 4.2.1 Obtain infonnation from Unit OSM as to Accident Type, Reactor Status, Release Information and current Emergency Classification per Enclosure 5.1 (Catawba Release Pathway Evaluation).
4.2.2 Select "RADDOSE" icon.
Select appropriate unit icon for CNS.
4.2.3 Select Mode of Operation as "Automatic".
4.2.4 IF data is NOT available OR Automatic Mode does not continue, perform any or all of the following:
Close current application window Select "Cancel" on current application window Exit Raddosc-5 Go to step 4.3.1.
4.2.5 Sclect ")rill Mode" or "Accident Mode" as appropriate lar tile situation.
HP/0/B/10091026 Page 4 of 13 NOTE:
IF the reactor did NOT trip and shutdown is in progress, THEN current date and time is the same as "Reactor Trip Date" and "Reactor Trip Time". IF start of offsite release is NOT known, THEN current date and time is the same as "Release Date" and "Release Time".
4.2.6 Input "Reactor Trip Date/Release Date" and "Reactor Trip TimetRelease Time" per Enclosure 5. 1.
4.2.7 Enter operator's initials.
4.2.8 IF all data input is correct, select "Accept".
4.2.9 IF any data requires correction, select "Cancel".
Select "Begin New Incident" Select "Yes" to "This erases all previous data..." question.
- Go to Step 4.2.6.
4.2.10 Select appropriate Accident Type for use with Automatic Mode.
- SG Tube Rupture 4.2.11 Select "Enter/Edit Meteorological Data" button.
4.2.12 IF all data automatically input via OILS PI (SDS), select "Accept".
4.2.13 IF all data is NOT automatically input via OILS PI (SDS), select "Cancel".
Select "Go to Start-Up Menu".
Select "Exit Raddose V".
- Go to Step 4.3.3.
4.2.14 Select "Enter/Edit Source Tern Data" (automatically populating fields from PI data server).
4.2.15 lIF all data is automatically input via OILS III (SI)S), select "Accept".
HP/0/B11009/026 Page 5 of 13 4.2.16 IF all data is NOT automatically input via OILS PI (SDS), select "Cancel".
Select "Go to Start-Up Menu".
e Select "Exit Raddose V".
Go to Step 4.3.3.
4.2.17 Select "Emergency Classification".
4.2.18 Select appropriate current classification.
4.2.19 Select "Continue".
4.2.20 Select "Start Auto Mode w/ Auto Reports" 4.2.21 IF you want to continue, select "Yes".
4.2.22 IF you want to return to previous screen, select "No".
NOTE:
Raddose-5 ("Automatic Mode Status Screen") will immediately generate a dose assessment report for te first step. The program will automatically wait 15 minutes and generate a report for the second and subsequent steps.
4.2.23 Create at least one copy of each dose assessment report for filing.
4.2.24 Provide data from Enclosure 5.5 (Emergency Notification), page 2 and 3 to OSM via the Emergency Notification Forn, page 1.
- Continue production of offsite dose projections as OSM requests.
4.2.25 IF OSM requests additional Raddose-5 offsite dose projections, continue with Automatic Mode.
Evaluate any increasing or adverse trends on additional dose projections.
4.2.26 IF no further on-shift dose assessment is required, select "Quit Automatic Mode".
- Select "Yes" to "Are you sure you wvant to exit Automatic operating mode?"
Exit Raddose-V per Section 4.4.
HP/O/B/1009/026 Page 6 of 13 4.2.27 IF notified by Unit OSM that Accident Type has changed, select "Quit Automatic Mode".
Select "Yes" to "Are you sure you want to exit Automatic operating mode?"
Select "Go to Start-Up Menu".
- Select "Begin New Incident".
- Select "Yes" in box with "This erases all previous data".
- Go to step 4.2.6.
4.3 Raddose-5 Manual Data Collection 4.3.1 Use Enclosure 5.1 (Catawba Release Pathway Evaluation) for recording initial information about current site conditions.
- Obtain affected unit and reactor status information from Operations Shift Manager or designee.
4.3.2 Use Operator Aided Computer (OAC) Satellite Display System (SDS) to obtain information about site meteorological and radiological conditions.
4.3.3 IF additional information is necessary, use the following enclosures:
- Enclosure 5.2 (Catawba Meteorology for Manual Inputs) for meteorological data
- .3 (Catawba Unit Vent Data for Manual Inputs) for release througi a unit vent
- .4 (Catawba Steam Release Data for Manual Inputs) for steam generator tube rupture or steam line release.
4.3.4 Select "RADDOSE" icon.
Sclect icon for affected unit at CNS.
NOTE:
This section of the procedure is for Normal Modc" operation of Raddosc.
4.3.5 Sclect "Nornial".
4.3.6 Select ")riill Mode" or "Accident Mode". as tplpropriale to lFl() response.
1-IO/B/1009/026 Page 7 of 13 4.3.7 Select "Manual" at next prompt to manually enter all data.
A. Select "Begin New Incident".\\x B. Click "YES" at pop up box prompt, "This erases all previous data."
C. Use information from Enclosure 5.1 at "Accident Scenario Definition menu" to enter the following:
NOTE:
IF the reactor did NOT trip and shutdown is in progress, THEN current date and time is the same as "Reactor Trip Date" and "Reactor Trip Time". IF start of offsite release is NOT known, THEN current date and time is the same as "Release Date" and "Release Time".
Reactor trip date Reactor trip time Release date Release time Raddose 5 operator's initials D. Ensure all data is correct.
IF any data is incorrect, select field with mouse to enter correct data.
NOTE:
IF "Cancel" is selected to exit screen, no data will be saved.
E.
Select "Accept" to progress to "Main Menu"; or select "Cancel" to exit screen.
4.3.8 At "Main Menu" select "Enter/Edit Meteorological Data".
Select "OK" on "No Automatic meteorological data available. Enter data nianually".
HP/O/B/1009/026 Page 8 of 13 A. Enter the following meteorological data:
- Wind speed
- Wind direction
- Mixing height - (computer generated value)
- Delta temperature Air temperature Precipitation B. Ensure all data is correct.
IF any data is incorrect, select field with mouse to enter correct data.
NOTE:
IF "Cancel" is selected to exit screen, no data will be saved.
C. Select "Accept" to return to "Main Menu" or select "Cancel" to exit screen.
4.3.9 At "Main Menu" select "Enter/Edit Source Term Data".
- Click "OK" on "No Automatic monitor data is available. Enter data manually".
NOTE:
"Accident Type" is option selected by user for each time step path based on accident for affected Unit or Unit 2.
4.3.10 Under "Accident Type", click on "None" field to select LOCA or SGTR.
4.3.11 IF LOCA is selected, use infornation from Enclosure 5.1 for affected Unit Vent release Path 1.
A. For "NG Method", click on field to select EMF.
- 13.
Select Unit Venl EMF36L.
NOTEI:
A pop-up box "Unit Vent Release Pathway Data" will he displayed and the user must select conditions for Unit Vent filter sUttus uasin; illf'olation Obt illCl fromi Operatiolls.
('.
Select ilter Status" ol "Unit V'en( Release 1Ii0vWy )ZIal" sCrlell.
HP/0/B11009/026 Page 9 of 13 II D. Select "Ice Condenser" status.
E. Select "Hold-Up Time" status.
F. Select "Spray Status".
G. Select "OK".
H. Enter EMF monitor reading.
NOTE:
IF Unit Vent Flow Monitor is inoperable OR Unit Vent Flow Rate indication is
< 1.00E+5 ft3/min, 1.90E+5 ft3/min shall be used for Unit Vent "Flow Rate" (PIP # C-03-03436).
I.
Enter Unit Vent "Flow Rate".
J.
Repeat steps 4.3.11 A. trough 4.3.11 1. for the unaffected Unit Vent release Path 2.
K. [F appropriate, enter accident type and required data for additional release path within the same time step.
L. IF any data is incorrect, select field with mouse to enter correct data.
NOTE:
IF "Cancel" is selected to exit screen, no data will be saved.
M. Select "Accept" to return program to "Main Menu" or "Cancel" to exit screen.
4.3.12 IF SGTR is selected, use information from Enclosure 5.1 for affected Unit release Path 1:
A. For "NG Method", click on field to select EMF.
B. Select Unit Vent EMF36L.
NOTE:
A pop-up box "Steam Line Release Pathway Data" is displayed Ethecre the user must choose conditions for Steam Generator rclease being Partitioned or Not-Partitioned; using information obtained from Operations.
C'.
Silect "Partiuioncd" or "Not laritioned". and then "OK".
1).
nter lMI "Monitor Readint".
1,,
1.,ter re-aws flowx rale1.
HPIO/B/1009/026 Page 10 of 13 F.
Repeat steps 4.3.12 A. through 4.3.12 E for the unaffected Unit Vent release Path 2.
G. For NG Method", Path 3 for affected Unit, select affected Steam Generator EMF.
H. Select "Partitioned" or 'Not Partitioned", and then 'OK".
I.
Enter EMF "Monitor Reading".
J.
Enter release flow rate.
K. IF appropriate, enter accident type and required data for additional release path within the same time step.
L.
IF any data is incorrect, select field with mouse to enter correct data.
I NOTE:
IF "Cancel" is selected to exit screen, no data will be saved.
1 M. Select "Accept" to return program to "Main Menu" or "Cancel" to exit screen.
4.3.13 Select "Emergency Classification".
4.3.14 Select appropriate Classification.
4.3.15 Select "Accept".
4.3.16 Select "Continue".
4.3.17 Select "Perforn Calculations" at "Main Menu".
NOTE:
The program displays a pop-up box "Please wait...calculating Step # - Loop over Puffs -
number of puffs = "; and calculates the offsite dose for the current time step. The final output is a Real-Time Mode display of the plume path with Maximum Dose Rates (mremtlhr) on 10-Mile Emergency Planning Zone (EPZ) map.
A. Select "Contintie" on 10-Mile ElPZ Map to go o "Output MCnu".
NOTE':
A pop-up box is prcscntcd "plcase wait, writing spreadsheet data file" where inal display 1 is the zeal-riime Mode Output Mcnu.
J It.
Select "(Continue CalculatiOms" to relturn to Main Ment".
(.
\\ "ltaIn Memi" select "'01hr1i FhwecaSt".
HP10/B1/10091026 Page 11 of 13 l NOTE:
A pop-up box is presented "Please wait, writing spreadsheet data file" where final display is the Real-Time Mode Output Menu.
D. Select "Continue Calculations" to return to "Main Menu".
E.
At "Main Menu" select "Perform Forecast".
NOTE:
The program displays a Forecast Mode dialogue box where the user must select options for current conditions that the program uses for Line #10 and #13 on Enclosure 5.5.
(Emergency Notification).
F. Select one of the following for "Emergency Release Status":
None Potential Is Occurring Has Occurred G. Ensure "New" is selected for "Status of Projected Offsite Dose".
H. Click on Forecast Period (hours) box to enter release duration.
IF release duration is unknown, enter default time of one (1) hour.
Ensure data selections are correct.
- 1. Select "OK" to proceed.
I.
Select "OK" at pop-up box; "Note: Forecast will use meteorological and source term data from Step #. Continue?"
NOTE:
A pop-up box with "Forecast for Pcriod ending in # hours -Number Puffs =" is displayed while he program calculates offsite dose. Final screen display is plume path on 10-Mile EPZ map witl dose results in mrem.
K. Slect "('ontinuc" at EP'Z plume map to proccd to "Output Mcnu"
- 1. Select "No" at pop-up box I)o you want to save PAZs idelified in Io ccst Mode otr evacutioln'?"
HP/IOB/10091026 Page 12 of 13 NOTE:
The program displays pop-up box "Please wait, writing data spreadsheet file" and then returns to the Output Menu in the Forecast Mode.
M. Select "Go to Report Menu" at "Output Menu".
NOTE:
User can select printing options when the program displays a pop-up box for computer print Setup parameters. The program has option for number of copies to print and user can make selection to change desktop computer settings for printers.
N. Obtain the following Raddose-5 reports by selecting individual menu options:
NOTE:
User must select "OK", "Cancel" or "Setup" following each report option "pop up box".
"Print Green Form + Summary Form" "Print Summary Forn", for additional summary reports
- 0. Select "Return to Output Menu" to exit "Report Options Menu".
P.
At the "Output Menu" in Forecast Mode select "Return to Main Menu".
Q. Select "OK" at pop-up box "You just completed a Forecast. Remember to check the meteorological and source term data for current information."
R. Go to Step 4.3.8 to continue report generation as required from "Main Menu" screen.
4.4 Exit Raddosc-V 4.4.1 IF at "Output Menu" select "Return to Main Menu".
4.4.2 IF at "Main Menu" select "Go to Start-Up Menu".
4.4.3 Select "Exit Raddose-V" at "Start-up Menu".
4.5 rurnover 4.5.1 Provide all pertinent dose assessment documcuts to TSC )ose Assessors after T.S('
eiergcicy lResponse Organization (EIRO) is activared.
HPI/BI310091026 Page 13 of 13 4.6 Record retention 4.6.1 Retain the following:
Reports generated during event Working Copy of procedure Other miscellaneous logs and notes
- 5. Enclosures 5.1 Catawba Release Pathway Evaluation 5.2 Catawba Meteorology for Manual Inputs 5.3 Catawba Unit Vent Data for Manual Inputs 5.4 Catawba Steam Release Data for Manual Inputs 5.5 Emergency Notification
.1 Catawba Release Pathway Evaluation HP/0/B/1009/026 Page 1 of 3 Obtain information from Operations for affected Unit and record data for Raddose-5 INITIAL DATA ENTRY:
(Automatic &
Manual)
.1 Circlc selected options Automatic: Affected Unit? U-I or U-2 Accident Type? LOCA or SG Tube Rupture SGTR Emergency Classification? NOUE Alert SAE GE Did Reactor trip? Yes No Date/Time of Reactor Trip? (
PJ_:
)
Mo yyl hr mn IF te Reactor did NOT trip and shutdown is in progress, THEN current date and time is the same as ReactorTrip Date and "ReactorTrip Tine'.
I
)
Mo yy/ hr: mn IF Operations does not know or provide a release time, then use current date & time.
(
I_: )
Mo yy/ hr: mn
= ~ ~ ~ ~ ~ ~
-=
= =-
=
=
_ _ = = = =
=
Manual: Affected Unit? U-I or U-2 Accident Type? LOCA or SG Tube Rupture SGTR Emergency Classification? NOUE Alert SAE GE Did Reactor trip? Yes No Datefime of Reactor Trip? (/
Mo dd yy hr: rtn IF the Reactor did NOT trip and shutdown is in progress, THEN current date and time is the same as "Reactor Trip Date" and "Reactor Trip Tirme".
(
Mo yy/ hr mn IF Operations does not know or provide a release time, then use current date & time.
I
- J)
Mo dd yy hr: mn Is affected Unit Vcnt release filtered by Unit Vent VENA filter fans?
ON OFF Ice Condenser Status?: "No Recirculation" "Recirculation" or No Ice" I-lold-Up?: " <=24 Hours" or " > 24 Hours" Spray Status?: ON OFF Is unaffeced Unit Vent release filtered by Unit Vent VEIVA filter fans? ON OFF Ice Condenser Status?: "No Recirculation" Recirculation" or "No Ice" liold-Up?: " <=24 Hours" or " > 24 Hours" Spray Status?: ON OFF IF a SGI'R release. what is the afctled steam generator? (A B C D) for steam line EMF(
)
IF' a SGIR release (kcurred. is tlc :afteewd S/C isolated! YCs No Are alected SIG secondary sile "1 " tulss covered with water AN) is release Pailitiotted?
Yes No Is,t r
a oi fitii alededeld steam cuoiet ato riatlh h 1ing released? Ye' s No
.1 Catawba Release Pathway Evaluation HP/O/B/10091026 Page 2 of 3 Release Duration Can radioactive release (steam or vet) pathway be isolated? Yes No Unknown (Manual What is the estimated stop time for the release?
ONLY)
Circle selected (IF release stop time is unknown, use default of Ihr.)
options Obtain from OAC SDS wind speed
(
) in mph - lower tower measurement preferred (Encl. 5.2);
wind direction
(
) in degrees from North - upper tower measurement (Manual ONLY)
Mixing height
( XXXXX ) in meters - calculated by program; Temperature D/T (
) D/ITinC AirTemperature
(
) in C0 Precipitation
(
) inches per quarter hour Obtain EMF STEP 1:
Monitor Reading and Accident Type: LOCA Vent or Steam release flow rate Unit 1 Vent AND Unit 2 Vent from OAC SDS NG Method (EMF36L-UV1L)
(EMF36L-UV2L)
(Encl. 5.3 &
Filter Status
( On Off
)
( On Off
)
5A); (Manual Monitor Reading (
) cpm
(
) cpm ONLY)
Vent Flow Rate
(
) cfm
(
) cfm Circle selected
=
options Accident Type: SGTR Unit 1 Vcnt AND Unit 2 Vent NG Method (EMF36L-UV1L)
(EMF36L-UV2L)
Filter Status
( On Off
)
( On Off
)
Monitor Reading (
) Cpm
(
) cpmn Vent Flow Rate
(
) cfm
(
) cin Unit I OR Unit 2 AffectedS/G
(
A, B, C, D
)
AffectedS/G (A,B,CD
)
NG Method(EMF) (
)
NG Method(EMF) (
)
Partitioned
(
Yes No
)
Partiti(ned
( Yes No )
Monitor Rclding(mRlhr) (
)
Monitor Reading(mnil/r)(
)
Steam R. (lbmlnr ma) (
)
Steam Re. (Ibrn/15 mill) (
)
.1 Catawba Release Pathway Evaluation HPIOfB/1009/026 Page 3 of 3 NOTE:
Use consistent Accident Type (LOCA or SGTR) for each Raddose 5 release path, for I
each fifteen minute time step.
Change the Accident Type only when reactor plant status indicates conditions that are degrading to a different type of accident.
- 1. Use Loss Of Coolant Accident (LOCA) Accident Type for assessment method for either Unit Vent(s) release path(s).
- LOCA - Loss of coolant (normal coolant) - leaks released into containment with fission products normally found in coolant and release pathway is through either Unit Vent After a valid increase or Trip 2 alarm on a Unit Vent radiation monitor select a vent EMF monitor Unit I or Unit 2 Vent EMF36 (low range in counts per minute)
- 2. Use S/G Tube Rupture (SGTR) Accident Type for primary to secondary system tube leak with relief valve open or steam line break and/or noble gas release through Unit Vent.
- SGTR - Steam generator tube rupture (nonnal coolant) - steam generator release accidents with fission products normally found in coolant where release pathway is any main steam line and/or power operated relief valve open After a monitor increase or valid Trip 2 alarm on any steam line radiation monitor select affected steam line and EMF radiation monitor Unit I EMF26 EMF27 EMF28 EMF29 (Steamline A, B, C, D) with reading in mR/hr Unit 2 EMFIO EMFI I EMF12 EMFI3 (Steamline A, B, C, D) with reading in mR/hr
.2 Catawba Meteorology for Manual Inputs HP/O/B/1009/026 Page 1 of 2
- 1. Access CNS Meteorological Tower data using OAC Satellite Display System (SDS) by entering GD ERORD5 (meteorological and EMF data), or GD EROENV (15 minute average data).
I NOTE:
Table below shall be used to record appropriate RADDOSE information.
I Step tep Wind Wind Mixing DT Stability Air Precipitation Number Time Speed Direction Height Temp.
Class Tern.
(inches in in (mph)
From 0"=N AT in last (lower preferred)
(upper preferd) in Co 15 minutes)
Computer Computer Computer Computer generated generated generated generated
,
- Use lower tower wind speed (WS) in miles per hour Use upper tower wind direction; in degrees from North where (N) = 00 Use upper tower wind speed (WS) if lower tower wind speed is not available Use lower tower wind direction if upper tower wind direction is not available
- 2.
I? CNS Meteorological Tower data is not available request meteorological information from Operations or obtain meteorological information by calling McGuire Nuclear Station Control Room (8-875-4262, 4263 or 4138).
F CNS meteorological tower temperature gradient D/T is unknown use the following default based on time of day, for stability classification, and complete the table below.
A. Between 1000 - 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />; assume AT = - 0.3 and Stability Class D B. Between 1600 - 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />; assume AT = + 1.3 and Stability Class F
- 3.
Obtain fifteen minute average meteorological data for Raddose-5.
Record information on Enclosure 5.1 Complete Enclosure 5.2 as necessary Temperature Gradient AT i (C0)
Stability Class AT0 * -0.97 A extremely unstable AT -0.97 < AT
-0.87 B moderately stable AT -0.87 < AT < -0.76 C slightly unstable AT -0.76 < AT 5 -0.25 D neutral AT-0.25 < AT <+0.76 E slightly stable AT+0.76 < AT *+2.04 F moderately sable AT +2.04 < A' Gc extremely stablc
.2 HP/O/B/1009/026 Catawba Meteorology for Manual Inputs Page 2 of 2
- 4.
Enter data in the Raddose-5 program.
Use MNS wind and temperature meteorological data if live time data is unavailable Use CNS default time of day D/T if data is unavailable wind speed in miles per hour (mph) wind direction; where wind direction is from North (N = 00)
- delta temperature gradient in degrees centigrade (AT = C0); where meteorological tower temperature is recorded for the low level sensor (1Om) with delta-temperature (AT) as the difference in the reading between the low and high sensor (60m)
- meteorological stability class is computer generated mean mixing height (in meters) is computer calculated using AT air temperature is in degrees centigrade (Temperature in C0) precipitation occurring (inches per fifteen minute period) 5.. Obtain most current meteorological conditions for Raddose-5.
Obtain most current wind direction and wind speed to determine downwind Protective Action Zones (PAZs) 3 Catawba Unit Vcnt Data for Manual Inputs HP10/1311009/026 Page 1 of 2
- 1. Determine type of accident, source term release pathway, and EMF noble gas monitor method; (e.g., normal reactor coolant activity, with reactor coolant leak inside containment, LOCA, with radioactive gas leakage to Annulus through Unit Vent, with all filters intact and vent radiation monitor EMF36L).
- 2.
Access OAC Satellite Display Systems (SDS) by entering GD ERORDS (meteorological and EMF data), or GD EROEMFI5 (15 minute EMF average data), or GD EROEMF (live time EMF display).
IF necessary, use top menu bar item GRAPHICS; select Ventilation and scroll to VE NTMENU; and use OK to open the display.
NOTE:
- 1. IF Unit Vent Flow Monitor is inoperable OR Unit Vent Flow Rate indication is
< 1.001E+5 ft3/min, 1.90E+5 ft3/min shall be used for Unit Vent "Flow Rate" (PIP # C-03-03436).
- 2. Table below shall be used to record appropriate RADDOSE information.
Step Step Path Accident Vent NG Monitor NG IUP Iodine Part Number Time Type Flow Method Reading Release Method Release Release LOCA or Rate in Et R
in cpm or Rate Rate Rate SGTR ft3/min Monitor mR/hr Ci/sec Ci/sec Ci/sec
\\1
>KCommuter Igenerated Computer I Computer generated generated Computer generated Computer generated Computer generated Computer generated 3 ________
1 _________
- Record information on Enclosure 5.1
- Complete Enclosure 5.3 as necessary Enter data in the Raddose-5 program
- 3.
Select LOCA accident type for affected unit vent release pathway:
LOCA - Loss of Coolant Accident (nornal coolant)
- 4.
Select affected Unit Vent Noble Gas method.
UVIL-Unit Vcntl I EMF-36L UV2L - Unit Vent 2 EMF-36L Other monitors available, but not specified for use in procedure:
UVIIt - Unit Vent I EMF-361-l
- UVl-ll - Unit Vent lEMF-54 UV21- - Unit Vcnt 2EMF-36-1 11V211t-i - Unit Vent 2EMF-54 t)sc on-scale EMI Freadings wvl'en vent EMI- [saililI)e pulpil) is not tripped or IEMI:I)ack;ge is not isolated; resulting fm loss of power aind/or 1EMI54 readiu(i
> 5 R/hr1-I ivlnacll (e.;.. Autiiyl Hlingl reledse) ;ande sel:ct liM: I' radiliout m()not tor echw tutu vent 3
Catawba Unit Vent Data for Manual Inputs HP/0/B1009/026 Page 2 of 2
- 5.
Select unit vent filtration reduction factors: Vent Filters On or Off, Ice Condenser Status - No Recirculation, Recirculation or No Ice, Hold Up time -
"<= 24 Hours or > 24 Hours and Spray Status - On or Off.
- 6.
Use RADDOSE 5 to calculate source term - vent release in Ci/sec.
Ci/sec is calculated by isotope spectrum based on accident type and time after reactor shutdown.
=
EMF x CF x AJ x FR x (E-6 Ci/jiCi x 160 min/sec x 28320 mft3)
Where:
=
release rate activity in Ci/sec EMF
=
Use EMF36L counts per minute (cpm), if reading lE+7 cpm and vent EMF sample pump is not tripped (UVIL, UV2L)
=
Use EMF36H cpm reading if EMF36L is offscale and EMF36H <IE+6 cpm and sample pump is not tripped (UVIH, UV2H)
=
Use EMF54 (RAir) reading if EMF36L and EMF36H are offscale, and/or vent EMF sample pump is tripped (UV IHH, UV2HH)
=
Unit Vent radiation monitor Noble Gas Correlation Factor Al
=
Adjustment Factors for Noble Gas, odines and Particulates for accident types FR
=
Unit Vent Flow Rate in ft3per minute; maximum vent flow < 1.90E+5 ft3/min
- 7.
IF release duration time is not known use a default time of (1) hour for Raddose 5 (Forecast mode) dose projection.
DO NOT save forecasted dose to PAZs
.4 Catawba Steam Release Data for Manual Inputs HP101B/1009/026 Page 1 of 2
- 1. Determine type of accident; source term release pathway and EMF NG gas monitor method; (e.g.,
steam generator (S/G) tube rupture, with normal reactor coolant activity, with steam line Power Operated Release Valve (PORV) open and steamline EMF radiation monitor).
- 2.
Access OAC Satellite Display Systems (SDS) display typing GD ERORDS (meteorological and EMF data), or EROEMF15 (15 minute EMF average data), or GD EROEMF (live time EMFdisplay), or GD EROSECND (live time display of secondary system data)
IF necessary, to view steam release information type GD EROSECND; use lower left SDS screen arrows t%4 to view affected steam line release information.
l NOTE:
Table below shall be used to record appropriate RADDOSE information.
Step Step Path Accident Steam NG Method EMF NG I/P Iodine Part Number Time Type Flow in Steamline Monitor Release Method Release Release last 15 EMF Reading Rate Rate Rate SGTR minutes Monitor in mR/hr Ci/sec Ci/sec Ci/sec Computer Computer Computcr Computer Computer computer Computer generated generated generated generated generated generated generated Record information on Enclosure 5.1 Complete Enclosure 5.4 as necessary Enter data in the Raddose-5 program
- 3.
Select Steam Generator Tube Rupture (SGTR) accident type for affected steamline release pathway:
- a.
Select affected Steamline Noble Gas method Unit I - EMF26 EMF27 EMF28 EMF29 (Steamline A, B, C, D reading in mR/hr)
Unit 2 - EMFIO EMF I EMF12 EMF13 (Steamline A, B, C, D reading in mR/hr)
.4 HP/0/1B/1009/026 Catawba Steam Release Data for Manual Page 2 of 2 Inputs
- I NOTE:
IF a steam generator is not overfilled with primary water and reading is determined to be within gage level indicator a partitioning effect for dose reduction for radio-iodine and particulates can be selected in Raddose-5.
- b.
Select SIG release reduction method:
- WHEN Unit 1 SIG tube break is below secondary side water level measured >0% Narrow Range water level indicator OR > 55% Wide Range water level select Partitioned.
IF Unit I SIG water level CAN NOT be determined OR is <0% Narrow Range water level indicator OR < 55% Wide Range water level OR the break is above the secondary side water level where reactor coolant is released by steam release directly to offsite environment, select Not Partitioned.
- WHEN Unit 2 S/G tube break is below secondary side water level measured >5% Narrow Range water level indicator OR > 45% Wide Range water level select Partitioned.
E IF Unit 2 S/G water level CAN NOT be determined OR is <5% Narrow Range water level indicator OR < 45% Wide Range water level OR the break is above the secondary side water level where reactor coolant is released by steam release directly to offsite environment, select Not Partitioned.
- 4.
Use Raddose-V to calculate source term - steam release in Ci/sec.
Ci/sec calculated by isotope spectrum based on accident type and time after reactor shutdown RR
=
EMF x CF x A x LR x (0.41ft3/lbm x 28320 mI/ft3 x IE-6 Ci/tCi x 1/3600/hr/s)
Where:
=
release rate activity in Ci/sec EMF =
radiation monitor reading in mR/hr (normally a 15 minute average reading)
=
steam line radiation monitor Correlation Factor AJ
=
Adjustment Factor (unit-less) based on accident type LR
=
Steam relcase rate from safety valve in pounds mass of steam released through each valve during valvc open period (bm/IS min.), wierc; default rlcasc ratc
= 5.235E4 Ibhm/ 15 imi.
- 5.
11 relecasc duiautionl (inie is not ko~n usc delfault (unec of (lI) hour for-Rladdose 5 (I-oreC;Ist mlOdC) t.
.ISE
- 1) IE ( I 1
)() N) save torecatsied dose t I'AZs
.5 HP/O/BI1009/026 Emergency Notification Page 1 of 6
- 1. Emergency Notification Form (example):
EMERGENCY NOliFCAflON
- 1.
THIS IS A DRILL (j] ACTUAL EMERGENCY N ItIAL 0 FOLLOW`UP MESSAGE NUMBER
- 2. SITE Cataa UNIT. _
REPORTED BY.
- 3. TRANSMITTAL TIMEIDATE:
I I
CONFIRMATION PHONE NUMBER (Eastern) mdy
- 4. AUTHENTICATION ( Required):
(Nurnber (Codeword)
- 5. EMERGENCY CLASSIFICATION:
NOIRCATlON OF UNUSUAL EVENT ff ALERT El SITE AREA EMERGENCY
[0 GENERA\\L EMERGENCY
- 6. [Z] Emergency Dedaration At:
] Termriation At:
TIMEtDATE
'Jt (it B. go to rn 16)
(Eastern) mm dd y
- 7. EMERGENCY DESCRIPTIONSRREMARKS:
- 8. PLANTCONDITION: MA IMPROVING a]
STABLE
[C DEGRADING
- 9. REACTOR STATUS:
SHUTDOWN:
TIMEIDATE:
- B J
50 POWER (Eastern) mm dd yy
- 10. EMERGENCY RELEASE(S):
[-A NONE (Go to Item 14)
Q POTENTIAL (Go to Item 14) i IS OCCURRING [o] HAS OCCURRED
-11.
TYPE OF RELEASE:
[]
ELEVATED
>3 GROUND LEVEL Ei] AIRBORNE:
STARTED:
00.0 STOPPED:
Time (Eastern)
Date Time (Eastern)
Date LIQUID:
STARTED:
JJ STOPPED:
J
/
Time (Eastem)
Date Time (Eastern)
Date
- 12. RELEASE MAGNITUDE:
3 Curies Per Sec [
Curies NORMAL OPERATING UMITS: 0 BELOW
] ABOVE A NOBLE GASES 0-[F+0 IODINES 00EX0E0 iWj PARTICULATES OOOfO LpJ OTHER
- 13.
ESTIMATE OF PROJECTED OFFSITE DOSE:
] NEW [
UNCHANGED PROJECTION TIME:
TEDE Thyroid COE (Eastern) mrem mrem ESTIMATED DURATION:
1 HRS.
SITE BOUNDARY OOOOO a.000E+
2 MILES 00017E4O O+/-OO+0 5 MILES O3O01+00 O OOr=OO 10 MILES 00017EO a
e OO+0
-14. METEOROLOGICAL DATA []
WIND DIRECTION (from) dea
[1 SPEED (mph)
MC STABILITYCLASS _
[
PRECIPITATION (type) i 5min
- 15.
RECOMMENDED PROTECTIVE ACTIONS:
f NO RECOMMENDED PROTECTIVE ACTIONS EVACUATE SHELTER IN-PLACE OTHER IG. APPROVED BY:__
TIMEtDATE:
J J
(Name)
(Title)
(Eastern) mm dd W
- i1 Items 8-t4 have notchanged, only items -7 and 15-16 are required to bo congsleo
- Information may not be available on Initial notificalion
.5 1HP/01B/10091026 Page 2 of 6 Emergency Notification
- 2. Dose Assessment Forecast Report ("Green Sheet") (example):
Catawba Nucktar StatiOn Unit N4o I Dose Assessmet RADOOSE-V Version 3.Oc Copyrlght 2002 Earth Tech CurretU Ote: MM=~00 Step if: I CuTnII rawe: 09-27 step Dote: a0 00Or' Cvw Step Thie: 0926
.9 ACCIDENT OESCAIPI10 Ceee.
EffM-o.Cy lse WOT bean dd-le~d neactor Shutdown:02420G3 0911 hri Accident Thie: 02042O(X 0911 IthS PATIMAY I Pcciert Typo:
- LOCA, Flew Rate:
1.3000.05 It'.3ftnn Noble Gas Megiod NIL (EMF361)
Monitor Reading:
2.1400.01 cpe, (P)
V e t P =
1 6 9 - 8_
RELEASE RATES:
HoWl Gas Rlelease Role rC4se):
2.21E4S5C~s Below Noffl Operainmg Units Ioinee Release Rate (C0'sec):
1863E49 Mls ParStcuate Release Rate (C&#sec):
2.50-It Cifs O..u -.T EO6(nsmn, Thp'Old COE.~ i.
(-di-)
AtuW
..t TOW ~
Mled F*i.C..
TOWS am5 68.26.05 L.36E04 1916.04 1.44E.04 8.776404 7.22E644 1.00 0.006.00 1256.04 1.3900.04 0.0000.00 2.IIE.4 2296.44 2.03 40006.00 3.W465 3.96E05 0.00E.00 0206465
£26E406 5.00 0.006.00 0.036.00 0.000.00 0.0000.00 0.00E0.00 0.00E.Go 10.00 0 00E.00 0.006.00 6000.00 0006.00 0006.00 0.000E.0
-~~~~~~~
~~~.
Wind Speed:
2.5 a"p (P)
Stab~ily Clas:
G (P)
Wind Direction:
rom 188.02 dog To 6.02 deg Evacuate:
None Shelter:
None 0 l~~ l.., e e C..
n h n l O e~~~~~~~e A M..
(......e.A
-t
)---
.(...es (iso..)
1606 Thrvild COE 1EDE 11.yel COE 0.oCh.31 eLSO 1336.4 LT1E.4 7g16.04 7.22E44 0.40644 1.0 1.396.4 12 16.04 1.39E 04 2.296104 3.37E944 1.00 7.92600S 159644 1.96600 5.26E05 1.SSE604 SAO0 0.0000.00 0.00E0.00 0.006.0 0.006.02 0.00E.00 10.0 5.006.00 0.0061.00 O0006.00 0006.00 0006E.00 TEOE:
2.07E4.07 PlurneE0E-6.5000404 Grounsd EDE:
7S5E+O6 COE Thyroid:
4.1 86400 lrEhalelion:
1316407 Noe < 100 OWee.
No< 1000 Rven No. 500 five.
No e 5000 neen' Site Area Emewgency:.
General Ernesgenicy:
.5 Emergency Notification HP/0/B/1009/026 Page 3 of 6 U,
- 2. Dose Assessment Forecast Report ("Green Sheet"):
r^G oose Lmits:
PM; feeded at Site Boundary?
PAG D0tano (ls):
I mm No WA Scem No
/WA MONTOR CORRECION FACTORS:
Thne Snce Tuep 4is) be Condene(
Sprays HoktUp rue Coat toak Rate Method Coot Leak Tpe Cont Pressur Coat Leak Rat.
Cont Bypass Fracon Fitters SG Partitioed Poo Scaxtbin Field Measurement Dtance DOvecion Fuel Assembly AOe jDays)
Patway I 000 No Pecic On 04 a-24 his
__a
-I
.5 HPIO/B/1009/026 Emergency Notification Page 4 of 6
- 3. Provide Control Room personnel completing an Emergency Notification Form the following information using Raddose-5 data from Dose Assessment Forecast Report ("Green Sheet").
NOTE:
Line # 5 - Emergency Action Level (EAL) classification is determined by OSM using RP/01AI5000/001 (Classification Of Emergency) if offsite dose exceeds Selected Licensee Commitment (SLC) limits.
Unusual Event - if gaseous or liquid radiological effluents exceed SLC limits Alert - is based on EMF readings that exceed SLC limits Site Area Emergency - is classified if site boundary dose rate exceeds Forecasted TEDE dose > 100 mrem; and/or Forecasted CDE Thyroid dose 2 500 mrem General Emergency - is classified if site boundary dose rate exceeds Forecasted TEDE dose 2 1 rem; and/or Forecasted CDE Thyroid dose Ž 5 rem Line # 10 - Emergency Release(s); use the following guidelines:
A.
None - no release of radioactivity generated by the event and no release expected.
B.
Potential Release - radioactivity generated during an event that has potential to be released but is not currently being released.
- Discretionary option for the Emergency Coordinator or the EOF Director.
C. Is Occurring - radioactivity generated during an event that is currently being released through any defined accident pathway, using any of the following indicators:
Either containment particulate, gaseous, iodine monitor readings indicate an increase in activity, OR Containment monitor readings indicate greater than 1.5 Rthr AND Either containment pressure is greater than 0.3 psig, 0R An actual containmcl brcacla is knowVn to CXiSt.
.5 HP/O/B/1009/026 Emergency Notification Page 5 of 6 Unit vent particulate, gaseous, iodine monitor readings indicate an increase in activity.
Condenser air ejector exhaust monitor or other alternate means indicate Steam Generator tube leakage.
Confirmed activity in the environment reported by Field Monitor Team(s).
Knowledge of the event and the impact on systems operation and resultant release paths.
D. Has Occurred - any radioactivity generated during an event that has been released previous to ERO activation that may require offsite agency notification.
Line # 11 - Type of Release Ground Level release and Airborne release with start time and stop time; if known.
Line # 12 - Release Magnitude in Curies per second (Ci/sec) released (from "RELEASE RATES:"
on Dose Assessment Report)
A.
Indicate Normal Operating Limits: above or below site boundary limits; where Technical Specification site boundary dose rate limit is; < 0.05 mrem/hr and Child Thyroid Dose rate limit is < 0.17 mremlhr; using the following guidelines:
- Release Below Normal Operating Limits is radioactivity released at any time during an event andlor radioactivity that may have been previously released that is not above site boundary normal operating limits.
Release Above Nornal Operating Limits is any radioactivity released during the event and/or any radioactivity previously released that is above normal site boundary operating limits.
B.
Quantity of each forrn of radioactive material released:
Noble Gases lodines
[articulates
.5 HP/O/B/1009/026 Emergency Notification Page 6 of 6 Line #13 - Estimate of Projected Offsite Dose (from "ACTUAL, FORECAST AND TOTAL (Forecast + Integrated) DOSES:" on Dose Assessment Report)
A.
New - used for initial forecast and when forecasted dose results are calculated for Emergency Notification B.
Unchanged - used when forecasted dose results are exactly the same as a previously issued Emergency Notification (for On-Shift Projections "New" is only selection).
C.
Projection Time - is "Step Time" from Dose Assessment Report D.
Estimated Duration - is duration of release in hours; (On -Shift dose assessment projection time using "Automatic Mode" defaults to one hour. In "Manual" if release time is known to be > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, input time in hours.)
E.
TEDE - projected offsite dose in mrem at; Site Boundary, 2 miles, 5 miles and 10 miles F.
CDE - projected offsite dose in mrem at; Site Boundary, 2 miles, 5 miles and 10 miles Line # 14 - Meteorological data A. Wind Direction - in degrees from North; where N = 00 B.
Wind speed - in miles per hour (mph)
C. Stability Class - (A,B,C,D,E,F or G)
D. Precipitation - (type; e.g., rain, sleet, snow) inches in the last fifteen minutes Line # 15 - Recommended Protective Actions (from "RECOMMENDED PROTECTIVE ACTIONS: Based on Radiological Conditions" on Dose Assessment Report)
A. No Recommended Protective Actions - recommended if EPZ projected dose for PAZs is < I rem TEDE or < 5 rem Adult Thyroid CDE.
B.
Evacuate - recommended for affected PAZs if the projected dose is 2 1 rem TEDE or 5 rem Adult Thyroid CDE; and recommend Shelter in Place for all other PAZs.
VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE Nuclear Policy Manual - Volume 2 I APPENDIX F. 703. PROCEDURE CHANGE PROCESS RECORD (R04-03)
Duke Power Company I
PROCEDURE CHANGE PROCESS RECORD (1)
ID No. S10lBt2005/00I NSD 703 I
Revision No. 002 Change No. B Pefman t/Restricted to Catawba Station: Catawba Nuclear Station Procedure
Title:
Emergency Response Offsite Dose Projections (4)
Section(s) of Procedure Affected:
(5)
Requires NSD 228 Applicability Determination? If Applicability Determination is required, attachNSD 228 documentation.
F]
Yes (Major procedure change) 0 No (Minor procedure change)
(6)
Description of Change: (Attach additionalpages, fnecessary.)
This change is applicable to Catawba Nuclear Station only. Added an alternate method for determining the Unit Vent Flow when the Unit Vent flow is less than 97,500 CFM. See attached sheet (7)
Reason for Change:
Catawba Engineering has determined that the Unit Vent Flow Monitor may not be accurate for flow rates less than 97,500 CFM.
This change implements an alternate method for determining the Unit Vent Flow rate when the Unit Vent flow is less than 97,500 CFM.
(8)
Prepared By (9)
Reviewed By (QR)
Cross-Disciplinary Review By 6
(Lrll (QR)
NA Reactivity Mgmt. Review By___
(QR)
NA Mgmt. Involvement Review By (Ops. Supt) NA ZW7 (10)
Additional Reviews Reviewed By Reviewed By
( 1)
Temporary Approval (ifnecessary)
By (OSM/QR)
By O
(QR)
(12)
Approved By CuY 7
Date -/--z>3 Date 7- /I-O3 Date 7 05 Date 7-/ I-9' Date 7- /I
,O Date Date Date Date Date 7-/o-3 REVISION 24
'ERIFY HARD COPY AGAINST WEBl SITE IMMEDIATELY PRIOR TO EACH USE 51
SILIO/BI2005/001, Emergency Offsite Dose Projections Restricted Major Change B This change is applicable to Catawba Only.
Change Summary:
- .4, Unit Vent Source Term Release, Page 2 of 4, was changed as follows:
Added NOTE before Step (e):
NOTE: Catawba Engineering has determined that the Unit Vent Flow Rate Monitor may NOT be accurate for flow rates less than 97,500 CFM Added New Step (e):
For Catawba Only: IF the Unit Vent Flow Monitor indicates a flow rate less than 97,500 CFM, use Enclosure 5.7 to determine the Unit Vent Flow.
Added New Enclosure 5.7, Catawba Unit Vent Flow Calculation Worksheet See attachment.
(
(
C Change B SHO/B/2005/001 Page 1 of 1.7 Catawba Unit Vent Flow Calculation Worksheet 5.7.1 Determine the status (On or Off) of each fan in list below.
5.7.2 IF the Fan is ON", place the Expected Flow (CFM) value into the Flow column of this worksheet.
5.7.3 IF the Fan is "OFF", place "0" CFM into the Flow column of this worksheet.
5.7.4 Total the values in the Flow column to calculate the Calculated Unit Vent Flow.
Unit 1 / Unit 2 (circle one)
Expected Flow Fan Status Flow (CM)
(Circle one)
(CFM)
Aux. Building Ventilation (VA)
Auxiliary Building Ventilation (VA) Filtered Exhaust Fan A 12,500 (On / Off)
Auxiliary Building Ventilation (VA) Filtered Exhaust Fan B 12,500 (On / Off)
Auxiliary Building Ventilation (VA) Unfiltered Exhaust Fan A 20,350 (On / Off)
Auxiliary Building Ventilation (VA) Unfiltered Exhaust Fan B 20,350 (On / Off)
Fuel Pool Ventilation (VF)
Fuel Pool Ventilation (VF) "A" Train Exhaust Fans (Al & A2) 33,130 (On / Off)
Fuel Pool Ventilation (VF) "B" Train Exhaust Fans (BI & B2) 33,130 (On / Off)
Annulus Ventilation (VE)
Annulus Ventilation (VE) Fan A 750 (On / Of)
Annulus Ventilation (VE) Fan B 750 (On / Off Containment Air Release and Addition (VQ)
VQ Fans (assume fans ARE running) 300 (On)
Calculated Total Vent Flow:
NOTE: A Spreadsheet may be used in place of this enclosure.
(R04-01)
Duke Power Company PROCEDURE PROCESS RECORD FOR STANDARD PROCEDURES (1) ID No. SHIOI)32005/001 Revision No.
002 PREPARATION (2)
Procedure
Title:
Emergency Response Offsite Dose Projections (3)
(4)
(5)
(6)
(7)
(8)
(9)
(10)
Prepared By
\\')/~~~~~
N Date 17 ?-303 Applicable To:
ONS MNS___________
Technical A
Advisor
__A
~
Requires O Yes 0 No Ye Yes No NSD 228 Applicability YES = New procedure or reissue with major changes Determination NO = Reissue with minor changes OR to incorporate previously approved changes Review (QR)
By By :/'
By_
Date Da_________Dt Date___Z_o Cross-Disciplinary By__
By 4
ey
- ,7k Review (OR)
NA Date NA Date NA Date Z-113:
Reactivity Mgmt.
By_
By By Review (OR)
NA Date NAWDateg&27/ 6' NA Date R/h7/O3 Mgmt. Involvement By By By Review (Ops. Supt.) N NA Date_______ NAG.Date 2;z7/03 NA CdDate /2?/o?
Additional By (QA)
By (QA)
By (QA)
Reviews Date Date Date By By_____
By DateDate 33 3 Date 3L//O 3 Approved By__
By 3-/03 Date Date 63'-o 3 Da Use Level Reference Use PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(11) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (12) Date(s) Performed Work Order Number (WO#)
COMPLETION (13) Procedure Completion Verification o Yes 0 NA Check lists or blanks properly initialed, signed, dated, or filled in NA, as appropriate?
O Yes 0 NA Required endosures attached?
O Yes 0 NA Data sheets attached, completed, dated. and signed?
o Yes 0 NA Charts. graphs, etc., attached and properly dated, identified, and marked?
0 Yes 0 NA Procedure requirements met?
Verified By (14) Procedure Completion Approved (15) Remarks (attadc additional pages, ~Yecessa'y)
Date Date
Duke Power Company Catawba and McGuire Nuclear Stations Emergency Response Offsite Dose Projections Reference Use Procedure No.
SH/O/B/2005/o1 Revision No.
002 Electronic Reference No.
MP007OPF
SH/O/l3/2005001 Page 2 of 16 Emergency Response Offsite Dose Projections
- 1. Purpose
\\
To provide instruction to Emergency Response Organization (ERO) dose assessors for determining source term and calculating the projected offsite dose to the public using Raddose 5 (Earth Tech 'm Windows© based computer program); and to provide dose assessment guidance for completion of Emergency Notification form.
NOTE:
This procedure is an Emergency Plan Implementing Procedure (EPIP) to be used for Catawba and McGuire Nuclear Stations. Emergency Planning must be notified of any changes to this procedure.
a~~~~~~~~~~
2.
References 2.1 Earth Tech Raddose 5 Operator's Manual, Detailed Design Manul, System Design Specification, Verification and Validation Report Vol 1 and 2 2.2 Station specific procedures for alternate method of determining Reactor Building dose rate:
CNS - HP/IOB110091006 MNS - HP10/B/10091002 Alternative Method for Determining Dose Rate Within the Reactor Building Alternative Method for Determining Dose Rate Within the Reactor Building 2.3 Station specific procedure for abnormal unit vent sampling:
MNS - HPIO/B/10091006 Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions 2.4 EPA 400-R-92-001 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.5 Letter from F.G. Hudson, September 20, 1985, Re: Release Rate Information for McGuire and Catawba Nuclear Stations (File: GS-750.25, NUC-0306) 2.6 Letter from H.B. Tucker, November 30, 1989, Re: Follow-up on McGuire Alert (March 7 - 8, 1989) Critique Action Items 2.7 U.S. Nuclear Regulatory Commission Response Technical Manual (RTM-93)
SH1/O32005/001 Page 3 of 16 2.8 Station specific procedures for classification of emergencies:
CNS - RPIOIA/5000001 Classification of Emergency MNS - RP/IoA/5700/000 X Classification of Emergency
- 3. Limits and Precautions 3.1 Use this procedure during abnormal or emergency conditions (including exercises and drills).
3.2 This procedure may be performed in sections or parts, using steps in any sequential order, to evaluate and/or assess offsite radiological conditions.
- 4. Procedure 4.1 Use Raddose 5 program to calculate Total Effective Dose Equivalent (TEDE) exposure, Committed Dose Equivalent (CDE) Thyroid exposure, and Effective Dose Equivalent (EDE) exposure in ten mile Emergency Planning Zone (EPZ).
Provide information for offsite dose exposure and projected offsite dose rate results, from any radioactive material(s) released offsite, to ERO Management.
4.2 Access the Raddose 5 software.
4.2.1 Click on the Raddose 5 icon.
4.2.2 A dialog box should appear stating Note: this workstation is configured as (EOF or TSC)". Click on "OK" to access the DAS (Dose Assessment Software) Desktop.
4.2.3 IF the dialog box above does NOT appear, change the DAS configuration as follows:
4.2.3.1 At the DAS Desktop, click on "FILE".
4.2.3.2 Click on "DAS Configuration".
4.2.3.3 Click on appropriate Work Station Type (EOF or TSC) and Mode (Production or Training).
4.2.3.4 Restart Raddose 5 for changes to take affect.
4.2.4 Select the appropriate Station and Unit from the DAS Desktop.
SH/0/3l20051001 Page 4 of 16 NOTE:
This procedure is for "Normal Mode" operation of Raddose only. The "Automatic Mode" contains limited choices and default assumptions. The 'Automatic Mode" is used for on-shift dose assessment only.
4.2.5 Select "Normal Mode" at the Dialog Box.
4.2.6 Select "Accident Mode" or "Drill Mode" as appropriate.
4.2.7 Select "PI Server" or "Manual" as appropriate.
Select "PI Server" for program query of fifteen minute average data from Operator Aided Computer (OAC).
Select "Manual" for keyboard entry of data.
4.2.8 IF this is the initial dose assessment calculation, select "Begin New Incident".
4.2.8.1 Enter information (e.g., reactor trip date, reactor trip time, release date and release time).
IF the reactor did not trip, and shutdown is in progress, THEN use current time in the blank for reactor trip time.
CAUTION:
IF the automatic transfer of Raddose data into the Electronic Emergency Notification Form is going to be used, per the "Save Green Form Data To Ini File" Function, it is j
important that the release time entered is the time of the actual release. This time is transferred to the Electronic Emergency Notification Form.
j Enter release time (estimated or known).
Enter operator initials and use the mouse to accept and/or cancel.
4.2.9 IF this is a continuation of a previous incident, AND IF previous TSC or EOF files are valid, select 'Continue Previous Incident".
4.2.9.1 Select "Local Data" to continue previous dose assessment calculation that was previously performed on the current workstation.
SH/O/B/2005/001 Page 5 of 16 4.2.9.2 Select "Network Data" to continue previous dose assessmenit calculation that was previously performed at another facility.
4.3 Select "Enter/Edit Meteorological Data" from program selection.
4.3.1 IF "Manual" was selected in Step 4.2.7, select "OK" to Raddose pop-up message: "No automatic meteorological data available. Enter data manually."
4.3.2 Input data for current meteorological conditions.
Use actual site meteorology for assessment of a release until it is appropriate to use forecasted data provided by a meteorologist 4.3.3 IF site meteorology cannot be obtained from meteorological tower systems, refer to Enclosure 5.1 (Meteorology) for alternate methods for obtaining meteorological data.
4.3.4 Enter meteorological data, or "Requery" for automatic meteorological input.
4.3.4.1 IF manual meteorological data entries are required use Enclosure 5.1 (Meteorology) as necessary.
- Enter lower wind speed in miles per hour (mph).
Enter upper wind direction; where wind direction is from North (N=O degrees).
Enter Delta temperature gradient (AT) in degrees centigrade (AT = 0C).
Enter air temperature in degrees centigrade (Temperature in 0C).
- Enter precipitation occurring (inches per fifteen minute period).
Mean mixing height (in meters) is computer selected from a table of seasonal afternoon mixing heights for each station.
SH/l1B/2005/001 Page 6 of 16 Manually overwrite meteorological data or "Requery" fr data that is acceptable.
4.3.5 Select the appropriate button for the meteorological data acceptance.
4.3.5.1 IF all of the meteorological data entered or retrieved is correct, click on "Accept".
4.3.5.2 IF new automatic data retrieval is needed, click on "Requery".
4.3.5.3 IF a new time step is needed, click on "Add New Step".
4.3.5.4 IF the meteorological data input needs to be aborted, click on "Cancel" to return to the main menu.
4.4 Select "Enter/Edit Source Term Data".
4.4.1 IF "Manual" was selected in Step 4.2.7, select "OK" to pop-up message: "No automatic monitor data available. Enter data manually."
4.4.2 Select the appropriate Accident Type from the list below.
Consult with ERO personnel (e.g., TSC Operations Engineering and/or EOF Accident Assessment) as necessary.
IF the Containment High Range Monitor is greater than 117 R/hr, the "gap release" accident types (LOCAG, SGTRG, and LOCOG) should be considered.
IF the Containment High Range Monitor is greater than the values in the Table in Step 4.5.2, the "melt release" accident types (LOCAM, SGTRM, and LOCOM) should be considered.
"LOCA" - Loss of coolant (normal coolant) - leaks released into containment with those fission products normally found in coolant.
"LOCAG" - Loss of coolant gap release - coolant leaks into containment of fission products in the fuel pin gap after fuel cladding has failed (e.g.,
core being uncovered, fuel pin heat up, and/or if mechanical fuel pin damage has occurred).
'LOCAM" - Loss of coolant core melt - coolant leaks released into containment of fission products expected to be released from a corc that is partially melted after being uncovered for some period of time.
SH/0/132005001 Page 7 of 16 "SGTR - Steam generator tube rupture (normal coolant) - steam generator release accidents with those fission products normally found in coolant.
"SGTRG - Steam generator tube rupture gap release - steam generator tube release accidents that release fission products in the fuel pin gap after fuel cladding has failed (e.g., core uncovery or fuel pin heat up and/or after mechanical fuel pin damage has occurred).
"SGTRM" - Steam generator tube rupture core melt - steam generator tube release accidents that release fission products expected to be released from a core that is partially melted after being uncovered for some period of time.
"LOCO" - LOCA outside containment (normal coolant) - leaks released directly from containment to outside environment (e.g., Annulus or Auxiliary Building) with fission products normally found in reactor coolant.
"LOCOG" - LOCA outside containment gap release - leaks released directly from containment to outside environment (e.g., Annulus or Auxiliary Building) with fission products in the fuel pin gap after fuel cladding has failed (e.g., core uncovery or fuel pin heat up and/or after mechanical fuel pin damage has occurred).
"LOCOM" - LOCA outside containment core melt - leaks released directly from containment to outside environment (e.g., Annulus or Auxiliary Building) with fission products expected to be released from a core that is partially melted after being uncovered for some period of time.
"FUEL" - Fuel handling gap release - fuel pin fission products released from fuel during refueling, or Spent Fuel Pool accident.
Use consistent Accident Type and identify release path(s) for each fifteen minute time step; changing Accident Type only when reactor and/or plant status indicate conditions degrading to a different accident.
4.4.3 Choose the appropriate NG Method based on the release pathway:
4.4.3.1 IF a steam release is occurring or suspected, refer to Enclosurc 5.2 (Steam Source Term Release) for NG Method selection.
4.4.3.2 IF a containment release is occurring or suspected, refer to.3 (Containment Source Term Release) for NG Method selection.
SH0B/2005001 Page 8 of 16 4.4.3.3 IF a unit vent release is occurring or suspected, refer to Enclosure 5.4 (Unit Vent Source Term Release) for NG Method selection.
4.4.4 Sel&;t the appropriate button for the Source Term Data acceptance.
4.4.4.1 IF all of the Source Term Data entered or retrieved is correct, click on "Accept".
4.4.4.2 IF new automatic data retrieval is needed, click on "Requery".
4.4.4.3 IF a new time step is needed, click on "Add New Step".
4.4.4.4 IF the Source Term Data input needs to be aborted, click on "Cancel" to return to the Main Menu.
4.5 Select "Emergency Classification" from the Raddose 5 itain menu.
NOTE:
This menu item is used to select the Current Emergency Classification in a drill or accident. Do NOT select a classification based on radiological conditions only.
4.5.1 Select the current Emergency Classification (Unusual Event, Alert, Site Area Emergency, General Emergency) from the menu.
4.5.2 IF General Emergency is chosen, respond to dialog box question: "Is the Fission Product inventory inside containment greater than gap activity?"
I IF the Containment High Range Monitor is greater than the values in the table below, answer the question "Yes".
High Range Containment Monitor Reading Time After Shutdown (hours)
(EMF 51 AlB or EMF 53 A/B) 0-2 864 R/Hr 2-4 624 RAHr 4-8 450 R/Hr
>8 265 R/Hr 4.6 Select "Perform Calculations" to calculate Real Time Mode dose results which are displayed on ten-mile map.
4.6.1 Select "Continue" from map display to go to the Real Time Mode Output Menu.
SH//OIB12005001 Page 9 of 16 4.6.2 Select applicable real-time mode output options:
4.6.2.1 IF forecasted doses and an Emergency Notification Form is needed at this time, select "Continue Calculations".
4.6.2.2 Other menu items may be selected as follows:
'Display Grid Receptor Doses" is used to display the Grid Receptor doses.
"Display Plume Arrival Times" is used to display red-time plume arrival times.
'Display 2-Mile Map" is used to see real-time Plume EDE and Adult Thyroid dose rates within two miles of the site.
"Display 10-Mile Map" is used to see real-time Plume EDE and Adult Thyroid dose rates within ten miles of the site.
"Display 50-Mile Map" is used to see real-time Plume EDE and adult thyroid dose rates within 50 miles of the site.
Review GenEmergency PAZ PARs" to display the PAZs that are recommended to be evacuated.
Display Point-of-Interest Doses" is used to see real-time dose rates at any point of interest. This choice may be used to display dose rates beyond the 10-mile radius of the site.
Display 50-Mile Deposition Data is used to display the 50-mile deposition data.
Display Survey Point Receptors" is used to see real-time dose rates and accumulated doses for predetermined sample points.
"Go To Report Menu" is used if output of real-time is desired.
The real-time mode report menu choices are:
View Reports" may be selected to view all of'(he real-tine reports
SilO/Br2005oo/0 Page 10 of 16 View Protective Action Zones" may be selected to view the Wind Direction/Affected Zone table.
- "Print Summary Form" nhay be selected to print the real-time summary report.
NOTE:
The real-time mode RQ Report is available from the "Print Reports and Maps" selection.
This report is used to display the "EPA RQ Fraction" released for each nuclide and a "Sum of the Ratios" for all of the nuclides released Print Reports and Maps" may be selected to print any combination of the available real-time mode reports.
4.7 Select "Perform Forecast" to calculate TEDE and CDE dose rates (mrem/hr), and forecasted dose (mrem), for the release duration in Forecast Mode.
4.7.1 IF General Emergency was chosen in Step 4.5.1, the following screen prompt will appear. "General Emergency Classification is chosen. Is the Fission Product-inventory inside Containment greater than gap activity?'
- Answer this prompt as the same as was done in Step 4.5.2.
4.7.2 Select the appropriate Emergency Release Status (e.g., None, Potential, Is Occurring, Has Occurred), using the following logic:
4.7.2.1 "None - no release of radioactivity generated by the event and no release expected.
4.7.2.2 "Potential' - radioactivity generated during an event that has potential to be released but is not currently being released.
- Discretionary option for the Emergency Coordinator or the EOF Director.
SH/OB/2005/001 Page I Iof 16 4.7.2.3 "Is Occurring" - radioactivity generated during an event that is currently being released through any defined accident pathway, using any of the following indicators:
EITHER containment particulate, gaseous, iodine monitor readings indicate an increase in activity, OR Containment monitor readings indicate greater than 1.5 R/hr, AND EITHER containment pressure is greater than 0.3 psig, OR An actual containment breach is known to exist.
Unit vent particulate, gaseous, iodine monitor readings indicate an increase in activity.
Condenser air ejector exhaust monitor or other alternate means indicate Steam Generator tube leakage.
Confirmed activity in the environment reported by Field Monitoring Team(s).
Knowledge of the event and the impact on systems operation and resultant release paths.
4.7.2.4 "Has Occurred" - any radioactivity generated during an event that has been released previous to ERO activation that may require offsite agency notification.
4.7.3 Select the appropriate Status of Projected Offsite Dose (e.g., New or Unchanged).
NOTE:
0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> is the lower limit allowed as a forecast period and the forecast period must be in increments of.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
4.7.4 Enter a Forecast Period (in hours).
4.7.5 IF all inputs are correct, select "OK".
SHIO/B/2005/001 Page 12 of 16 4.7.6 Select "OK" to the screen prompt "Note: Forecast will use the meteorological and source term data from Step 1. Continue?"
NOTE:
Forecast Mode doses are calculated using the most current time step and are displayed on ten mile EPZ map.
4.7.7 IF General Emergency was selected in Step 4.5, THEN select "Both PARs" to display the General Emergency Protective Action Recommendations, and the Dose Protective Action Recommendations.
4.7.8 Select "Continue" from map display to go to the Forecast Mode Output Menu.
4.7.9 At the popup dialog box item "Do you want to save PAZs identified in forecast mode for evacuation?", select "Yes" 4.7.10 Select "Go To Report Menu' to go to the Forecast Mode Report Options Menu and access the Raddose 5 Green Form.
NOTE:
Refer to Step 4.6.2.2 for a description of the other choices on this menu. However, it should be noted that all outputs will consist of forecasted data instead of real-time data.
4.7.11 Select "Print Green Form + Summary Form" to print the Emergency Notification Form (green sheet) and the Summary Report.
4.7.12 Select "Save Green Form Data to Ini File" to transfer the Raddose data to the Electronic Notification Form application.
4.7.13 Other menu items may be selected as follows:
"View Green Form" is used to display the Green Form report.
"View Reports" is used to view all reports.
"Print Green Form" is used to print the Green Form report.
"Print Summary Form" is used to print the Summary Form report.
"Print Reports and Maps" is used to select any combination of the available reports.
4.7.14 Select Return to Output Menu" when done with Forecast Mode reports.
4.7.15 Select "Continue Calculations" to return to the main menu in real-time mnode.
SII/IOB/2005/001 Page 13 of 16 4.7.16 Select "OK" to the Raddose prompt: "You have just completed a forecast.
Remember to check the meteorological and source term data for current information".
4.8 Refer to Enclosure 5.5 (Radiological Emergency Action Levels) and evaluate the Emergency Action Levels (EALs) based on radiological conditions.
4.8.1 Provide EAL radiological assessment classifications to ERO Management in the TSC and/or EOF.
4.9 IF desired, obtain the Self Reading Dosimeter Correction Factor (SRDCF) from the Real-Time Summary Report.
NOTE:
Raddose 5 calculates Effective Dose Equivalent (EDE) exposure and provides Self Reading Dosimeter (SRD) correction factor (SRDcF).
TEDE SRDcFr =
EDE SRDcF
=
=
Total Effective Dose Equivalent EDE
=
Effective Dose Equivalent NOTE:
The SRDCF value is based on accident specific source term nuclide(s) and is a calculation of TEDE to EDE ratio at site boundary.
SRDcF is provided to offsite Emergency Workers during an accident, after a declared General Emergency, and when a release is occurring.
SRDcF is used as a multiplier of Emergency Worker SRD readings for EPA 400 Manual Of Protective Action Guides And Protective Actions For Nuclear Incidents, "Early Phase' Emergency Worker TEDE estimate.
Provide the SRDcF the Field Monitoring Coordinator and the OSC.
4.10 IF manual completion of the Emergency Notification Form is to be used, provide the Radiological Assessment Manager (RAM), Lead TSC Dose Assessor and/or ERO personnel the following information for each of the Emergency Notification Form line items:
SH/O/B2005/OOI Page 14 of 16 4.10.1 Obtain "Green Form Report" (example shown on Enclosure 5.6).
4.10.2 line # 10 - Emergency Release(s); use the guidance in Step 4.7.2.
4.10.3 Line # 11 - Type of Release; check Ground Level release and record Airborne or Liquid release with start time and stop time; if known.
4.10.4 Line # 12 - Release Magnitude in Ci/Sec released.
NOTE:
The Normal Operating Limit in the Technical Specifications are: EDE 5.OE-2 mRem/hr, Child Thyroid 1.711 E-l mRem/hr.
4.10.4.1 Select "Above" or "Below" to indicate if the release is above or below the Normal Operating Limits.
Release Below Normal Operating Limits is radioactivity released at any time during an event and/or radioactivity that may have been previously released that is NOT above site boundary normal operating limits.
Release Above Normal Operating limits is any radioactivity released during the event and/or any radioactivity previously released that is above normal site boundary operating limits.
4.10.4.2 Record value (in Ci/Sec) for each form of radioactive material released offsite.
Noble gases lodines Particulates
SHI/1312005/001 Page 15 of 16 4.10.5 Line # 13 - Record Estimate of Projected Offsite Dose as New' or "Unchanged":
Record projection time of forecast.
Record estimated duration of release. This value shall be the forecast period used in Step 4.7.4.
IF the release is below normal operating limits, as determined in Step 4.10.4.1, enter "Not Required" in the TEDE and CDE fields on the Emergency Notification Form.
IF the release is above normal operating limits, as determined in step 4.11.3.1, record the TEDE and CDE mrem forecasted dose at Site Boundary, 2 miles, 5 miles and at 10 miles.
4.10.6 Line #14 - Record meteorological data.
4.10.6.1 Wind Direction from North where 2N=O degrees 4.10.6.2 Wind Speed (miles per hour) 4.10.6.3 Stability Class 4.10.6.4 Precipitation (type) (in/15min) 4.10.7 Line #15 - Recommended PAZ protective actions as indicated on the "Green Form Reports (example displayed on Enclosure 5.6).
4.10.8 Provide Raddose 5 printouts and summary reports to Federal, State and County agencies supporting ERO activation, with approval by lead TSC dose Assessor or EOF RAM.
4.10.9 Retain logs, computer printouts and computer generated dose assessment files, whenever ERO is activated.
Exercise and Drill records are retained for Emergency Planning disposition.
SlifOfB12051001 Page 16 of 16
- 5. Enclosure 5.1 Meteorology 5.2 Steam Source Term Release 5.3 Containment Source Term Release 5.4 Unit Vent Source Term Release 5.5 Radiological Emergency Action Levels 5.6 Raddose 5 Green Form Report 5.7 Catawba Unit Vent Flow Calculation Worksheet
<-CHANGE B
.1 Meteorology SHO/B/2005/001 Page 1 of 2 5.1.1 Meteorological Tower OAC data is normally provided as 15 min. average.
Use lower tower wind speed (WS) in miles per hour Use upper tower wind speed (WS) if lower tower wind speed is not available Use upper tower wind direction; in degrees from North (N) = 00 Use lower tower wind direction if upper tower wind direction is not available: in degrees from North (N) = 00 5.1.2 IF Meteorological Tower is not available, obtain meteorological information from:
Duke meteorologist at 594-034110289 Unaffected plants control room:
CNS - Unit-I 8-831-5345 Unit-2 8-831-5344 MNS - Unit-I 8-875-4262 Unit-2 8-875-4263 National Weather Service (NWS) at 1-800-268-7785 Gastonia Automated Surface Observation System (ASOS) at 704-868-9034 5.1.3 IF meteorological tower temperature gradient (AT0) is unknown, use the following default values:
.1 Meteorology SHIO//2005/001 Page 2 of 2 5.1.4 Use the following tables to determine stability class when AT data is available:
I CNS (AT in 0C)
AnS (AT in C)
Stability Class
.4 4
A - Extremely Unstable B - Moderately Unstable C - Slightly Unstable D - Neutral E - Slightly Stable F - Moderately Stable G - Extremely Stable AT < -0.97
-0.97 < AT -0.87
-0.87 < AT < -0.76
-0.76 < AT < -025
-0.25 < AT < +0.76
+0.76 < AT * +2.04
+2.04 < AT AT * -0.95
-0.95 < AT * -0.86
-0.85 <AT * -0.76
-0.75 <ATS -0.26
-0.25 < AT * +0.74
+0.75< AT * +2.00
+2.00 < AT
.2 SHWO/B/2005/001 Steam Source Term Release Page 1 of 4 5.2.1 Determine type of accident, source term release path and EMF monitor method.
5.2.2
'Select an Accident Type for an affected release pathway:
SGTR" - steam generator tube rupture (normal coolant)
SGTRG" - steam generator tube rupture gap release SGTRM" - steam generator tube rupture core melt 5.2.3 Select the appropriate steam line EMF Noble Gas Method as follows:
IF steam line monitor data is available, use the following guidance for Noble Gas Method selection:
(a)
Review the steam line monitor data.
(b) Select appropriate steam line monitor: SG-A, SG-B, SG-C, or SG-D.
(c) Select Partitioned" or "Not Partitioned" using the guidance below:
(i)
IF the steam generator tube leak/break is below the secondary side water level AND the steai generator is NOT overfilled, select "Partitioned".
(ii) IF the steam generator leak/break is above the secondary side water level OR the steam generator is overfilled, select "Not Partitioned".
(d) Click on "OK".
(e) IF manual data entry was selected in Step 4.2.7, enter the monitor data and the flow rate.
- IF secondary side steam sample data is available, select GRABSL.
(a)
Enter the secondary side steam sample data.
(b)
When all data is entered, click on "OK".
(c)
Enter the Steam release rate in pounds mass per 15 minutes (LBM/I5min).
IF field team data is available, select BACKSL.
(a)
Enter the field team data.
(b)
Click on "OK" for Raddose to calculate the source term in Ci/sec.
.2 SHIOIB2005/001 Steam Source Term Release Page 2 of 4 NOTE:
Raddose 5 calculates the steam source term release rate for the SG-A, SG-B, SG-C, and SG-D methods as follows:
- Ci/sec is distributed by isotope spectrum based on accident type and time after reactor shutdown
- Raddose 5 calculates the steam source term as follows:
=
EMF x CF x AJ x LR x (0.41ft3Ilbm x 28320 ml/ft3 x 1E-6 CilijCi x 1/3600/hrls)
Where:
= release rate activity in Ci/sec CF
= steam line radiation monitor Correlation Factor EMF
= radiation monitor reading in mR/hr (normally a 15 minute average reading)
AJ
= Adjustment Factor (unit-less) based on accident types (SGTR, SGTRG, SGTRM)
LR
= Steam release rate from safety valve in pounds mass of steam released through each valve during valve open period (Ibm/15 min), where; default release rate = 5.235E4 Ibm/5 min NOTE:
Raddose 5 calculates steam source term for the GRABSL method as follows:
=
SL x LR x (0.41ft3/lbm x 28320 mi/ft3 x 1E-6 Ci/LCi x 1/3600/hr/s Where:
=
release rate activity in Ci/sec SL
=
secondary grab sample (gCi/ml)
LR
=
steam release rate from safety valves pounds mass of steam released through the respective valves during the valve open period (Ibm/hr) default release rate = 5.235E4 Ibm/15 min
.2 SH1O/B/2005/001 Steam Source Term Release Page 3 of 4 NOTE:
Raddose calculates the steam source term for the BACKSL method as follows:
=
Field Measurement Device Reading (mRlhr) x FM Device Correlation (jLCi/cc)/(miR/hr)XIQ(seclm 3) x (E-6 Ci/ItCi x 1E+6 cc/m3=1) 5.2.4 For Catawba only, use Step 5.2.5 source term assessment worksheet steam generator tube rupture coincident with loss of offsite power, when appropriate and'due to the following:
Loss of offsite power and steamline radiation monitor is unavailable Primary to secondary coolant leakage is occurring Steam source term release is occurring Steam generator sample cannot be obtained Computer program for calculating steam release is not available
.2 SHJ/OB/2005/001 Page 4 of 4 Steam Source Term Release 5.2.5 (Catawba Only) Source term assessment worksheet with steam generator tube rupture coincident with loss of offsite power for unavailable Steam Line Monitor EMF Unit_
Dose Projection based on:
I /
Time since trip:
hours mm dd yy hh mm EMF53 reading* Correction Factor** LRps dT Lbsmr***
1NOPEN Rlhrx __
x galx _
_ min x Ibmr x
R/hr min 2400 Ibm
- Note: If EMF53<5 Rthr, use 5 R/hr.
x
-- -sec.
x 3.785E-3 Ci ml x =
gCi gal Activity noble Gas Ci sec Activity nble Gas x
Iodine Ratio wNcA Activity LOCA Iodine 131 Equivalent
= __________Ci/sec Activity noble Gas x
odine Ratio cr mt Activity Lore Melt Iodine 131 Equivalent
=_________
_________Ci/sec Where:
LRps
=
Primary to secondary leak rate in gal/min.
dT
.=
Time that primary to secondary leakage has lasted from the start of the leak to the time of date that the projection is based on, in minutes.
Lbsmr
=
Mass of steam released from the PORV and/or code safety valves, in Ibm.
VOPEN
=
Time the valve(s) are open in hours.
3.785E-3
=
E-6 Ci/ICi x 3.785E3 ml/gal 2400
=
Mass of steam in the faulted steam generator; conservative valve is 2400 Ibm (mass of steam from S/G nozzle to MSIV)*** If Lbsmr > 2400 Ibm; use 2400 Ibm.
Time since Rx Trip EMF 53 Correction Factor Iodine Ratio LOCA Iodine Ratio Con Mel l
(hours)
- (CF)_
>0 7.74 E+3 1.52 E-3 4.23 E-3
>2 9.82 E+3 1.95 E-3 1.46 E-3
>4 9.96 E+3 2.24 E-3 2.21 E-2
>8 1.28 E+4 2.63 E-3 4-09 E-2 2 24 2.15 E+4 3.00 E-3 1.14E-l
> 48 3.69 E+4 3.05 E-3 1.78 E-l Emergency 0 or Drill 0 Prepared by:
.3 SHOIB/2005/001 Containment Source Term Release Page I of 3 5.3.1 Determine type of accident source term release path and EMF monitor method.
5.3.2 Select an Accident Type for an affected release pathway:
LOCA"-Loss of Coolant Accident (normal coolant)
LOCAG"-Loss of Coolant Accident gap release "LOCAM"-Loss of Coolant Accident core melt 5.3.3 Select containment Noble Gas Method as follows:
IF containment sample line is NOT isolated AND containment sample pump is NOT tripped, use the following guidance for Noble Gas Method selection:
(a) IF EMF 39(L) < 1E7 counts per minute (cpm), select "CONL".
(b) IF EMF 39(L) > 1E7 cpm AND EMF 39(H) < 1E6 cpm, select "CONH".
(c)
IF EMF 39(H) > 1E6 cpm, select "CONHH".
IF containment sample line is isolated OR containment sample pump is tripped, use the following guidance for Noble Gas Method selection:
(a) IF containment sample results are available, select "GRABC".
(b) IF containment sample results are NOT available, select "CONHH".
5.3.4 IF CONL, OR CONH, OR CONHH was selected in Step 5.3.3, Raddose displays the Containment Bypass Release Pathway screen. Choose the appropriate selections for.
(a)
Ice Condenser: "No Recirculation", Recirculation", or 'No Ice" (b)
Hold-Up: "<--24 Hours" or ">24 Hours" (c)
Spray Status: On" or Off (d)
Containment Leak Rate Method: "Containment Pressure and Hole Size" or
'Predefined/User Leak Rate' (e)
Enter or verify the Containment Pressure (g)
When all inputs on the Containment Bypass Release Pathway screen are correct, click on "OKE NOTE:
Containment source term can be calculated using containment EMF readings, containment samples, or field team data. Reference 2.2 can be used if no other data is available.
(h)
F Manual" was selected in Step 4.2.7, enter the monitor reading.
.3 Containment Source Term Release SHI101B120051001 Page 2 of 3 NOTE:
Raddose 5 calculates the containment source term for the CONL, CONH, AND CONHH methods as follows:
=
EMF x CF x AJ x BY x Ci/ILCi x 1/3600 hr/sec Where:
=
EMF =
EMF =
EMF =
=
AJ
=
BY
=
LR
=
release rate activity in Ci/sec EMF39(L) count per minute (cpm) and EMF39(L) < 1E+7 cpm; and containment sample line is not isolated and/or containment EMF sample pump is not tripped (CONL Method)
EMF39(H) cpm whenever EMF39(L) reading is > 1E+7 cpm (offscale) and EMF39(H) cpm < 1E+6 cpm and/or sample line is not isolated and sample pump is not tripped (CON-H Method)
EMF53A/B - CNS or EMF5 1 A/B - MNS R/hr reading whenever EMF39(H) is
>1E+6 cpm (offscale) orEMF39 sample line is isolated, or EMP containment sample pump is tripped (CONHH Method)
Containment Noble Gas monitor Correlation Factor Adjustment factors for Noble Gas; Iodine's and Particulates Containment Bypass Fraction - Fraction of containment leakage of gases from inside containment which bypasses the annulus and auxiliary building and passes directly to the environment where, (default value = 0.07)
Leak Rate of containment air to the annulus or environment (mllhr) based on one of the following methods:
(a)
Based on containment pressure and hole size corresponding to:
- 1. Normal Leakage - 0.3% per day at design pressure (15 psig)
- 2. Small Hole - 100% per day at design pressure (15 psig)
(b)
Pre-defined Leak Rate corresponding to:
- 1. Normal Leakage (0.3% per day)
- 2. Small Hole (100% per day)
- 3.
Large Hole (100% per hour) 3 SHO/1B/2005/001 Containment Source Term Release Page 3 of 3 NOTE:
Raddose 5 calculates the containment source term for the GRABC method as follows:
=
EMF x CF x AJ x BY x CiVCi x 1/3600 hrlsec Where:
CONg =
Containment grab sample (tLCi/ml)
All other parameters are the same as defined in the NOTE above.
Enclosure SA SH/B/2005/001 Unit Vent Source Term Release Page 1 of 4 5.4.1 Determine type of accident, source term release pathway, and EMF monitor method.
5.4.2 Enter an accident type for affected release pathway.
LOCA - Loss of Coolant Accident (normal coolant)
"LOCAG - Loss of Coolant Accident gap release LOCAM" - Loss of Coolant Accident core melt "LOCO" - LOCA outside of containment (normal coolant)
"LOCOG" - LOCA outside of containment gap release "LOCOM" - LOCA outside of containment core melt "SGTR" - Steam Generator Tube Rupture (normal coolant) with Condensate Stem Air Ejector(CSAE) pathway to unit vent "SGTRG" - Steam Generator Tube Rupture gap release Condensate Steam Air Ejector (CSAE) pathway to unit vent "SGTRM - Steam Generator Tube Rupture core melt Condensate Steam Air Ejector (CSAE) pathway to unit vent "FUEL" - Fuel handling gas release 5.4.3 Select the appropriate unit vent EMF Noble Gas Method as follows:
IF Unit Vent EMF Data is available, AND unit vent sample pump is NOT tripped, use the following guidance for Noble Gas Method selection:
(a)
IF EMF 36(L) < 1E7 counts per minute (cpm), select "UVIL" or "UV2L" as appropriate.
(b)
IF EMF 36(L) > 1E7 cpm AND EMF 36(H) S 1E6 cpm, select "UVIH" or "UV2H" as appropriate.
(c)
IF EMF 36(H) > E6 cpm, select "UJVIHH" or "UV2HH" as appropriate.
.4 Unit Vent Source Term Release SHI0/B/2005/0 1 Page 2 of 4 beibw hanSe
.44 A
(d)
Select the appropriate response for the Unit Vent Release Pathway Data screen as follows:
(i)
Filter Status - "On" or "Off" (ii) Ice Condenser. "No Recirculation", "Recirculation", or "No Ice" (iii) Hold-Up: "<= 24 Hours" or"> 24 Hours" (iv) Spray Status: "On" or "Off' IB)
(v)
When all inputs on the Unit Vent Release Pathway screen are correct, click on
.......1~
"OK"
) jjF "Manual" was selected in Step 4.2.7, enter the unit vent monitor reading
).e-Verify or enter the unit vent flow rate IF Unit Vent EMF Data is NOT available, use the following guidance for Noble Gas Method selection:
(a)
IF Unit Vent Isotopic Sample data is available, select "GRABVI" or "GRABV2" as appropriate.
(i)
Enter the grab sample data.
(ii) Click on "OK" for Raddose to calculate the source term in Ci/sec.
(b)
IF Field Team Data is available, select "UVI-BACK" or UV2-BACK" as appropriate.
(i)
Enter the field team data.
(ii)
Click on "OK" for Raddose to calculate the source term in Ci/sec.
(c)
IF Total Source Term calculations are available, select "DRCT1" or DRCT2" as appropriate.
(i)
Enter the Noble Gas, Iodine, and Particulate source term data.
(ii) Click on "OK" for Raddose to calculate the source term in Ci/sec.
Check unaffected unit vent monitor data.
IF appropriate, repeat Step 5.4.3 to include source term assessment for unaffected unit.
Change B NowrF:
Catawba Engineering has determined that the Unit Vent Flow Monitor may NOT be accurate for flow rates less than 97,500 CFM (e)
For Catawba ONLY. IF the Unit Vent Flow Monitor indicates a flow rate less than 97,500 CFM, use Enclosure 5.7 to determine the Unit Vent Flow.
.4 SHO/BM2005/001 Unit Vent Source Tenn Release Page 3 of 4 NOTE:
Raddose 5 calculates the unit vent source term for the UVIL UVIH, UVIHH, Uv2L, UV2H, AND UV2HH methods as follows:
Ci/sec is distributed by isotope spectrum based on accident type and time after reactor shutdown.
Raddose 5 calculates unit vent source term as follows:
=
EMF x CF x AJ x FR x E-6 Ci/gCi x 1/60 min/sec x 28320 ml/ft3 Where:
=
release rate activity in Cilsec EMF =
Use EMF36L counts per minute (cpm), if reading < 1E+7 cpm and vent EMF sample pump is not tripped (UVIL, UV2L)
=
Use EMF36H cpm reading if EM36L is offscale and EMF36H < 1E+6 cpm and sample pump is not tripped (UV1H, UV2H)
=
Use EMF54 - CNS, EMF36HH - MNS (R/hr) reading if EMF36L and EMF36H are offscale, and/or vent EMF sample pump is tripped (UVIHH, UV2HH CF
=
Unit Vent radiation monitor Noble Gas Correlation Factor AJ
=
Adjustment Factors for Noble Gas, odines and Particulates for accident types FR
=
Unit vent flow rate in ft3 per minute, (No default rate); vent flow rate is a manual Raddose 5 input if query data is unavailable
.4 Unit Vent Source Term Release SwYO/132005/001 Page 4 of 4 NOTE:
Raddose 5 calculates the unit vent source term for the GRABV1 and GRABV2 methods as follows:
RR UVg x FR x E-6 Ci/ltCi x 1/60 min/sec x 28320 m/ft3 Where:
=
release rate activity in Ci/sec UVg
=
unit vent grab sample (JiCi/ml)
FR
=
Unit vent flow rate in ft3 per minute; (No default rate); vent flow rate is a manual Raddose 5 input if queried data is unavailable
.1 NOTE:
Raddose 5 calculates the source term for the UVI-BACK, UV2-BACK method as follows:
=
Field Measurement Device Reading (mRlhr) x FM Device Correlation (jiCi/cc)/(mR/hr)/X/Q(sec/m 3) x (IE-6 Ci/ILCi x 1E+6 cc/m3=1)
.5 Radiological Emergency Action Levels SHIO/B/2005/00,1 Page I of I 5.5.1 Evaluate the Emergency Action Levels (EALs) based on radiological conditions in the affected site's EAL procedure:
CNS - RP/O/A/5000/001 Classification of Emergency MNS - RP/O/A/5700/000 Classification of Emergency
-.6 SH/OIBI2005/001 Page I of 2 Raddose 5 Green Form Report Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech Current Date: 12/0912002 Step #: 1 Current lime: 14:41 Step Date: 12/09/2002 Operator GTJ Step Time: 12:15
- FORECAST FOR 4 HOURS ACCIDENT DESCRIPTION:
General Emergency has NOT been declared Reactor Shutdown:12/09/2002 1200 hrs Accident Time: 12/09/2002 1200 hrs PATHWAY I 1.31E+05 Accident Type:
LOCA Flow Rate:
ftA3min 1.54E+00 R/hr Noble Gas Method UVI HH (EMF54)
Monitor Reading:
(P)
VentCF =
0.328 RELEASE RATES:
Noble Gas Release Rate (Ci/sec):
3.12E+01 GUs Above Normal Operating Limits Iodine Release Rate (Cisec):
4.61 E-02 Cis Particulate Release Rate (Ci/sec):
3.54E-03 CUs ACTUAL, FORECAST AND TOTAL (Forecast + Integrated) DOSES:
Distance TEDE (mrem)
Thyroid CDE (mrem)
(miles)
Actual Forecast Total Actual Forecast Total 0.50 1.67E+01 2.7E+02 2.84E+02 1.71 E+02 2.74E+03 2.91 E+03 1.00 7.71E+00 1.23E+02 1.31E+02 6.46E+01 1.03E403 1.10E403 2.00 3.36E+00 5.40E+01 5.74E+01 2.32E401 3.74E+02 3.97E.02 5.00 0.00E400 1.42E+01 1.42E401 0.00E400 9.41E401 9.41E401 10.00 0.00E+00 4.79E+00 4.79E+00 0.00E+00 2.81E+01 2.81E+01 METEOROLOGICAL DATA.
Wind Speed:
9.5 mph (P)
Stability Class:
D (P)
Wind Direction:
From 44.90 deg To 224.90 deg RECOMMENDED PROTECTIVE ACTIONS:
Evacuate:
Shelter:
.6 SHI/12005001 Page 2 of 2 Raddose 5 Green Form Report Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech Current Date: 12109/2002 Current lime: 14:41 Operator. GTJ Step #: 1 Step Date: 12/09/2002 Step Time: 12:15
- FORECAST FOR 4 HOURS ***
TOTAL (Forecast + Integrated) DOSES FROM 12109/2002 12:00 TO 16:15:
Distance Current Dose Rates (mrernthr)
Dose (mrem)
X/C Thyroid Thyroid (miles)
TEDE CDE TEDE CDE (sec/m3) 0.50 6.68E+01 6.85E+02 2.84E+02 2.91 E+03 3.55E-45 1.00 3.08E401 2.59E+02 1.31E+02 1.10E+03 1.34E-05 2.00 1.35E+01 9.35E401 5.74E+01 3.97E+02 4.85E-06 5.00 3.49E+00 235E+01 1.42E401 9.41E+01 1.22E-06 10.00 1.36E+00 8.03E+00 4.79E+00 -
2.81E+01 4.16Eb7 DOSE CONVERSION FACTORS:
mrem mA3/Ci hr TEDE:
2.15E+07 PlumeEDE:
8.65E+04 Ground EDE:
7.33E+06 CDE Thyroid:
4.18E+08 Inhalation:
1.41 E+07 EMERGENCY CLASS:
Total Effective Adult Dose Equivalent Thyroid Site Area Emergency:
Yes >= 100 mrem Yes >= 500 mrem General Emergency:
No < 1000 mrem No < 5000 mrem PAG Dose Umits:
1 rem 5 rem PAG Exceeded at Site Boundary?
No No PAG Distances (miles):
N/A NIA-MONITOR CORRECT1ON FACTORS:
Time Since Tfip (Hrs)
Ice Condenser Sprays Hold-Up lime Cont Leak Rate Method Cont Leak Type Cont Pressure Cont Leak Rate Cont Bypass Fraction Filters SG Partitioned Pool Scrubbing Field Measurement Distance Direction Fuel Assembly Age (Days)
Pathway 1 0.00 No Recirc On
<=24 hrs No
(
C C
Change B SII/O/B/2005/001 Page 1 of 1.7 Catawba Unit Vent Flow Calculation Worksheet 5.7.1 Determine the status (On or Off) of each fan in list below.
5.7.2 IF the Fan is "ON", place the Expected Flow (CFM) value into the Flow column of this worksheet.
5.7.3 IF the Fan is "OFF", place "0" CFM into the Flow column of this worksheet.
5.7.4 Total the values in the Flow column to calculate the Calculated Unit Vent Flow.
Unit 1 / Unit 2 (circle one)
Expected Flow Fan Status Flow (CFM)
(Circle one)
(CFM)
Aux. Building Ventilation (VA)
Auxiliary Building Ventilation (VA) Filtered Exhaust Fan A 12,500 (On / Off)
Auxiliary Building Ventilation (VA) Filtered Exhaust Fan B 12,500 (On / Off)
Auxiliary Building Ventilation (VA) Unfiltered Exhaust Fan A 20,350 (On / Of)
Auxiliary Building Ventilation (VA) Unfiltered Exhaust Fan B 20,350 (On / Off)
Fuel Pool Ventilation (VF)
Fuel Pool Ventilation (VF) "A" Train Exhaust Fans (Al & A2) 33,130 (On / Off)
Fuel Pool Ventilation (VF) "B" Train Exhaust Fans (BI & B2) 33,130 (On / Off)
Annulus Ventilation (VE)
Annulus Ventilation (VE) Fan A 750 (On / OfM Annulus Ventilation (VE) Fan B 750 (On / Off)
Containment Air Release and Addition (VQ)
VQ Fans (assume fans ARE running) 300 (On)
Calculated Total Vent Flow:
NOTE: A Spreadsheet may be used in place of this enclosure.