ML030860718

Emergency Plan Implementing Procedures, Including Revision 4 to HP/0/B/1009/026, On-Shift Offsite Dose Projections & Revision 2 to SH/0/B/2005/001, Emergency Response Offsite Dose Projections.

ML030860718
Person / Time
Site:	Catawba
Issue date:	03/20/2003
From:	Gordon Peterson Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML030860718 (68)

Text

Duke GARY R. PETERSON Vice President Power Catawba Nuclear Station A Duke Energy Company Duke Power CN01 VP / 4800 Concord Rd York, SC 29745 803 831 4251 803 831 3221 fax grpeters@duke-energy com March 20, 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 Procedure:

HP/0/B/1009/026, On-Shift Offsite Dose Projections (Rev. 4)

SH/0/B/2005/001, Emergency Response Offsite Dose Projections (Rev. 2)

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.

Very truly you s, ary erson Attachments W&15 www duke-energy corn

U.S. Nuclear Regulatory Commission March 20, 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 H12 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 TITLE RP/0A/5000/001 Classification of Emergency (Rev. 015)

RP/O/A/5000/002 Notification of Unusual Event (Rev. 036)

RP/O/A15000/003 Alert (Rev. 039)

RP/OIA/5000/004 Site Area Emergency (Rev. 041)

RPIO/A/5000/005 General Emergency (Rev. 041)

RPIO/AI5000106 Deleted RP/0/A/5000/006 A Notifications to States and Counties from the Control Room (Rev. 014)

RP/O/A/50001006 B Notifications to States and Counties from the Technical Support Center (Rev. 014)

RPIOIA/5000/006 C Deleted

"~'- RP/O/AI5000/007 Natural Disaster and Earthquake (Rev. 021)

RP/O/A/5000/08 Deleted RP/O/B/5000/008 Spill Response (Rev. 020)

RP/O/A15000/009 Collision/Explosion (Rev. 006)

RP/O/A/5000/010 Conducting A Site Assembly or Preparing the Site for an Evacuation (Rev. 016)

RP/O/A15000/11 Deleted RP/0fB15000/12 Deleted RP/0/B/5000/013 NRC Notification Requirements (Rev. 029)

RP/O/B/5000/14 Deleted RPIO/A150001015 Core Damage Assessment (Rev. 005)

RP/OJB/5000/016 Deleted RP/0/B/5000/17 Deleted March 12, 2003

Page 2 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE TITLE RP/0A/5000/018 Emergency Worker Dose Extension (1/15/96)

RPIO/BI/5000/019 Deleted RP/O/A/5000/020 Technical Support Center (TSC) Activation Procedure (Rev. 017)

RP/O/AI50001021 Deleted RP/O/B/5000/022 Evacuation Coordinator Procedure (Rev. 004)

RP/OJB/5000/023 Deleted RP/O/A/5000/024 OSC Activation Procedure (Rev. 010)

RP/OJB/5000/025 Recovery and Reentry Procedure (Rev. 003)

"RP/IOB/5000/026 Site Response to Security Events (Rev. 004)

RP/I0B/5000/028 Communications and Community Relations EnergyQuest Emergency Response Plan (Rev. 001)

March 12,2003

Page 3 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE HP/OJB/1000/006 Emergency Equipment Functional Check and Inventory (Rev. 054)

HP/0/B/1009/001 Radiation Protection Recovery Plan (Rev. 008)

HP/0/B/ 1009/003 Radiation Protection Response Following a Primary to Secondary Leak (Rev. 008)

HP/O/BII009/004 Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 028)

HP/0/B1009/005 Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 016)

HP/OJB3/ 009/006 Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 008)

HP/0/B1I 009/007 In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 019)

HPOJB/1 009/008 Contamination Control of Injured Individuals (Rev. 015)

HP/OlB/ I009/009 Guidelines for Accident and Emergency Response (Rev. 039)

HPIO/B/10091014 Radiation Protection Actions Following an Uncontrolled Release of Radioactive Material (Rev. 008)

HPOJBI/1009/016 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev. 011)

HPIOI/B/1009/017 Deleted HPIIl/B/1009/017 Deleted HP/21B/1009/017 Deleted HPO/OB/ I009/018 Deleted HPIOIBII009/019 Emergency Radio System Operation, Maintenance and Communication (Rev. 010)

HP/OI/B1009/024 Implementing Procedure for Estimating Food Chain Doses Under Post Accident Conditions (Rev. 002)

March 12, 2003

Page 4 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE HPIO/B/i 009/025 Deleted HP/0!B/1 009/026 On-Shift Offsite Dose Projections (Rev. 004)

SH/01B/2005/001 Emergency Response Offsite Dose Projections (Rev. 002)

SHI0/B/2005/002 Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev. 002)

OP/0/A/6200/021 Deleted SR/0/B/2000/001 Standard Procedure for Public Affairs Response to the Emergency Operations Facility (Rev. 003)

SR/0/B/2000/002 Standard Procedure for EOF Services (Rev. 002)

SR/0/B/2000/003 Activation of the Emergency Operations Facility (Rev. 009)

SR/0/B/2000/004 Notification to States and Counties from the Emergency Operations Facility (Rev. 005)

March 12, 2003

Duke Power Company (t) ID No IP10B110091026 PROCEDURE PROCESS RECORD Revision No 004

'REPARATION

2) Station Catawba Nuclear

3) Procedure Title On-Shift Offsite Dose Projections

/ . / 5

4) Prepared By -Date .//'3

5) Requires NSD 228 Applicability Determination If Aj plicability Determination is required, attach NSD 228 documentation M Yes (New procedure or revision with ma .anges) 0 No (Revision with minor changes) 0 No (To incorporate pre iouslya proved changes)

(6) Reviewed By (QR) *q'Date 5 ', ¢.kj*

Cross-Disciplinary Review By (QR) NA* Date Reactivity Mgmt. Review By (QR) NA A4 Date 3/S"03 Mgmt. Involvement Review By (Ops Supt.) NAUV- Date 3/ '

7) Additional Reviews Reviewed By Date Reviewed By Date

8) Temporary Approval (if necessary)

By (OSM/QR) Date

, ..Sy (QR) Date Approved By a- azi Date "'3-- 3

"?ERFORMANCE(Comparewith control copy every 14 calendardays while work is beingperformed.)

10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy_ Date II) Date(s) Performed Work Order Number (WOM)

COMPLETION

12) Procedure Completion Verification:

0 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 I0 NA Charts, graphs, etc. attached. dated, identified, and marked?

o Yes 0 NA Procedure requirements met?

Verified By Date

13) Procedure Completion Approved Date

14) Remarks (Attach additionalpages, if necessary)

Duke Power Company Procedure No.

Catawba Nuclear Station HP/O/B/1 009/026 Revision No.

On-Shift Offsite Dose Projections 004 Electronic Reference No.

Reference Use CP00945J

HP/O/B/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 RPIO/A/5000/001 Classification Of Emergency 2.2 EPA 400-R-92-001 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.3 Earth Tech RADDOSE 5 Operator's Manual

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 in the Technical Support Center (TSC) or Emergency Operations Facility (EOF).

HPIO/BIl009/026 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.

4.2 Raddose-5 Automatic Version 4.2.1 Obtain information 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 Raddose-5

"* Go to step 4.3.1.

4.2.5 Select "Drill Mode" or "Accident Mode" as appropriate for the situation.

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 Time/Release Time" per Enclosure 5.1.

4.2.7 Enter operator's initials.

t I

HPIOIBI1009/026 Page 4 of 13 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.

"* LOCA

"* 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 input, 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 Term Data" (automatically populating fields from PI data server).

4.2.15 IF all data is input via PI, select "Accept".

4.2.16 IF all data is NOT input, select "Cancel".

"* Select "Go to Start-Up Menu".

"* 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".

009/026 HPIOIB/i Page 5 of 13 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 the 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 Form, 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 want to exit Automatic operating mode?"

"* Exit Raddose-V per Section 4.4.

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.

HP/O/B/1 009/026 Page 6 of 13 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

"* Enclosure 5.3 (Catawba Unit Vent Data for Manual Inputs) for release through a unit vent

"* Enclosure 5.4 (Catawba Steam Release Data for Manual Inputs) for steam generator tube rupture or steam line release.

4.3.4 Select "RADDOSE" icon.

0 Select icon for affected unit at CNS.

NOTE: This section of the procedure is for "Normal Mode" operation of Raddose.

4.3.5 Select "Normal".

4.3.6 Select "Drill Mode" or "Accident Mode", as appropriate to ERO response.

4.3.7 Select "Manual" at next prompt to manually enter all data.

A. Select "Begin New Incident".

B. Click "YES" at pop up box prompt, "This erases all previous data."

HP/0/B!/1009/026 Page 7 of 13 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 manually".

A. Enter the following meteorological data:

• Wind speed

• Wind direction

• Mixing height - (computer generated value) o Delta temperature

• Air temperature

• Precipitation

HPiOIBl1 0091026 Page 8 of 13 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 I 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 information from Enclosure 5.1 for affected Unit

/1 Vent release Path 1.

A. For "NG Method", click on field to select EMF.

B. Select Unit Vent EMF36L.

NOTE: A pop-up box "Unit Vent Release Pathway Data" will be displayed and the user must select conditions for Unit Vent filter status using information obtained from Operations.

C. Select "Filter Status" on "Unit Vent Release Pathway Data" screen.

D. Select "Ice Condenser" status.

E. Select "Hold-Up Time" status.

F. Select "Spray Status".

G. Select "OK".

H. Enter EMF monitor reading.

I. Enter Unit Vent "Flow Rate".

J. Repeat steps 4.3.11 A. through 4.3.11 1. for the unaffected Unit Vent release Path 2.

HP/OIll/ 009/026 Page 9 of 13 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.

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 where the user must choose conditions for Steam Generator release being Partitioned or Not-Partitioned; using information obtained from Operations.

C. Select "Partitioned" or "Not Partitioned", and then "OK".

D. Enter EMF "Monitor Reading".

E. Enter release flow rate.

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.

HP/0/13/1009/026 Page 10 of 13 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.

4.3.13 Select "Emergency Classification".

4.3.14 Select appropriate Classification.

4.3.15 Select "Accept".

4.3.16 Select "Continue".

4.3.17 Select "Perform 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 (mrem/hr) on 10-Mile Emergency Planning Zone (EPZ) map.

A. Select "Continue" on 10-Mile EPZ Map to go to "Output Menu".

NOTE: A pop-up box is presented "Please wait, writing spreadsheet data file" where final display is the Real-Time Mode Output Menu.

B. Select "Continue Calculations" to return to "Main Menu".

C. At "Main Menu" select "Perform Forecast".

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".

HPIOIB!1009/026 Page 11 of 13 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.

I. Select "OK" to proceed.

J. 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 Period ending in # hours -Number Puffs =" is displayed while the program calculates offsite dose. Final screen display is plume path on 10-Mile EPZ map with dose results in mrem.

K. Select "Continue" at EPZ plume map to proceed to "Output Menu" L. Select "No" at pop-up box "Do you want to save PAZs identified in Forecast Mode for evacuation?"

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".

HPIOIBl1 0091026 Page 12 of 13 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 Form", 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 Raddose-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 Turnover 4.5.1 Provide all pertinent dose assessment documents to TSC Dose Assessors after TSC Emergency Response Organization (ERO) is activated.

4.6 Record retention 4.6.1 Retain the following:

• Reports generated during event

• Working Copy of procedure Other miscellaneous logs and notes

HP/O/B/1009/026 Page 13 of 13

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

Enclosure 5.1 HPIOIB/I 0091026 Catawba Release Pathway Evaluation Page 1 of 3 Automatic: Affected Unit? U-I or U-2 Obtain Accident Type? LOCA or SG Tube Rupture SGTR information from Emergency Classification? NOUE Alert SAE GE Operations for affected Unit Did Reactor trip? Yes No Date/Tiime of Reactor Trip? ( I.:

and record data Mo yy/ hr. mn for Raddose-5 INITIAL IF the Reactor did NOT trip and shutdown is in progress, THEN current date and time is the same DATA as "Reactor Trip Date" and "Reactor Trip Time". (: )-.

ENTRY: Mo yy/ hr.mn (Automatic & IF Operations does not know or provide a release time, then use current date & time.

Manual) Moyy/ hr.mn Circle selected Manual: Affected Unit? U-i or U-2 options Accident Type? LOCA or SG Tube Rupture SGTR Emergency Classification? NOUE Alert SAE GE Did Reactor trip? Yes No Date/Time of Reactor Trip? ( I  :

Modd yy hr:mn 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". (. .

Moyy/ hr.ma IF Operations does not know or provide a release time, then use current date & time.

Modd yy hr:rmn Is affected Unit Vent release filtered by Unit Vent VE/VA filter fans? ON OFF Ice Condenser Status?: "No Recirculation" "Recirculation" or "No Ice" Hold-Up?: "<=24 Hours" or "> 24 Hours" Spray Status?: ON OFF Is unaffected Unit Vent release filtered by Unit Vent VE/VA filter fans? ON OFF Ice Condenser Status?: "No Recirculation" "Recirculation" or "No Ice" Hold-Up?: "<=24 Hours" or "> 24 Hours" Spray Status?: ON OFF IF a SG'TR release, what is the affected steam generator?. (A B C D) for steam line EMF ( )

IF a SGTR release occurred, is the affected S/G isolated? Yes No Are affected S/G secondary side "U" tubes covered with water AND is release Partitioned? Yes No Is steam from affected steam generators currently being released? Yes No

Enclosure 5.1 HP/OlI11l0091026 Catawba Release Pathway Evaluation Page 2 of 3 Release Duration Can radioactive release (steam or vent) pathway be isolated? Yes No Unknown (Manual What is the estimated stop time for the release?

ONLY)

Circle selected ILF release stop time is unknown, use default of lhr.)

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/T in C0 Air Temperature ( ) inC° 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 )

5.4); (Manual Monitor Reading ( ) cpm ( ) cpm ONLY) Vent Flow Rate ( ) cfm ( ) cem Circle selected options Accident Type: SGTR Unit 1 Vent AND Unit 2 Vent NG Method (EMF36,-UV1L) (EMF36L-UV2L)

Filter Status ( On Off ) ( On Off )

Monitor Reading ( ) cpm ( ) cpm Vent Flow Rate ( ) clm ( ) cfm Unit 1 OR Unit 2 Affected S/G ( A, B, C, D ) Affected S/G (A, B,C,D NG Method(EMF) ( ) NG Method(EMF) ( )

Partitioned ( Yes No ) Partitioned ( Yes No )

Monitor Reading(mR/hr) ( ) Monitor Reading(mR/hr) ( )

Steam Rel. (ibm/15 min) ( ) Steam Rel. (Ibm/ 15mn) ( )

i

Enclosure 5.1 HP/0I/B/1009/026 Catawba Release Pathway Evaluation Page 3 of 3 NOTE: e Use consistent Accident Type (LOCA or SGTR) for each Raddose 5 release path, for each fifteen minute time step.

0 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 (normal 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 1 EMF26 EMF27 EMF28 EMF29 (Steamline A, B, C, D) with reading in mR/hr

• Unit 2 EMFIO EMFI 1 EMFI2 EMFI3 (Steamline A, B, C, D) with reading in mR/hr

Enclosure 5.2 HP/O/B/1009/026 Catawba Meteorology for Manual Inputs Page I 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).

NOTE: Table below shall be used to record appropriate RADDOSE information.

"* 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. IF 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).

• IF 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' in (C0 ) Stability Class AT" < -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 < -0.25 D neutral AT-0.25 < AT <+0.76 E slightly stable AT+0.76 < AT <+2.04 F moderately stable AT +2.04 < AT G extremely stable

Enclosure 5.2 HP/0/1B/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 = C°); where meteorological tower temperature is recorded for the low level sensor (10m) 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)

Enclosure 5.3 HP1OIB/10091026 Catawba Unit Vent Data for Manual Inputs Page I 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 ERORD5 (meteorological and EMF data), or GD EROEMF15 (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 VENTMENU; and use OK to open the display.

NOTE: Table below shall be used to record appropriate RADDOSE information. I I

• 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 (normal coolant)

4. Select affected Unit Vent Noble Gas method.

0 UVIL- Unit Vent I EMF-36L UV2L - Unit Vent 2 EMF-36L Other monitors available, but not specified for use in procedure:

"* UVIH - Unit Vent I EMF-36H UV2H - Unit Vent 2EMF-36H

"* UVIHH -Unit Vent IEMF-54 UV2HH - Unit Vent 2EMF-54

"* Use on-scale EMF readings when vent EMF sample pump is not tripped or EMF package is not isolated; resulting from loss of power and/or EMF54 reading > 5 R/hr

"* Evaluate (e.g., Auxiliary Building release) and select EMF radiation monitor for each unit vent.

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.

Enclosure 5.3 HP/0/B/1009/026 Catawba Unit Vent Data for Manual Inputs Page 2 of 2

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.

RR = EMF x CF x AJ x FR x (1E-6Ci/tCi x 1/60min/sec x 28320 ml/ft3 )

Where:

RR = release rate activity in Ci/sec EMF = Use EMF36L counts per minute (cpm), if reading <1E+7 cpm and vent EMF sample pump is not tripped (UVIL, UV2L)

EMF = Use EMF36H cpm reading if EMF36L is offscale and EMF36H <1E+6 cpm and sample pump is not tripped (UVIH, UV2h)

EMF = Use EMF54 (R/hr) reading if EMF36L and EMF36H are offscale, and/or vent EMF sample pump is tripped (UV1HH, UV2HH)

CF = Unit Vent radiation monitor Noble Gas Correlation Factor AJ = Adjustment Factors for Noble Gas, Iodines and Particulates for accident types FR = Unit vent flow rate in ft3 per 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.

0 DO NOT save forecasted dose to PAZs

Enclosure 5.4 HPIOIB/I 009/026 Catawba Steam Release Data for Manual Page 1 of 2 Inputs

1. Determine type of accident; source term release pathway and EMF NG gas monitor method; (e.g.,

steam generator (SIG) 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 ERORD5 (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 4A, to view affected steam line release information.

I I NOTE: Table below shall be used to record appropriate RADDOSE information. I

• 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 1 - EMF26 EMF27 EMF28 EMF29 (Steamline A, B, C, D reading in mR/hr)

"* Unit 2 - EMFI0 EMFI 1 EMFI2 EMFI3 (Steamline A, B, C, D reading in mR/hr)

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 S/G release reduction method:

• WHEN Unit I SIG tube break is below secondary side water level measured >0% Narrow Range water level indicator OR > 55% Wide Range water level select Partitioned.

Enclosure 5.4 HP10/BI1009/026 Catawba Steam Release Data for Manual Page 2 of 2 Inputs "IFUnit I S/G 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.

"* IF Unit 2 SIG 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 AJ x LR x (0.41ft3 /lbm x 28320 ml/ft3 x 1E-6Ci/IpCix 1/3600/hr/s)

Where:

RR = release rate activity in Ci/sec EMF = radiation monitor reading in mR/hr (normally a 15 minute average reading)

CF = steam line radiation monitor Correlation Factor AJ = Adjustment Factor (unit-less) based on accident type LR = Steam release rate from safety valve in pounds mass of steam released through each valve during valve open period (bbm/l5 min.), where; default release rate

= 5.235134 Ibm/ 15 min.

5. IF release duration time is not known use default time of (1) hour for Raddose 5 (Forecast mode) dose projection.

• DO NOT save forecasted dose to PAZs

Enclosure 5.5 HPI0/B/1009/026 Emergency Notification Page 1 of 6

1. Emergency Notification Form (example):

EMERGENCY NOTIFICATION

1. E] THIS IS A DRILL [] ACTUAL EMERGENCY [] INITIAL [] FOLLOW-UP MESSAGE NUMBER __

2. SITE: Catawba UNr': REPORTED BY-,

3 TRANSMIT-iALTIME/DATE. I I CONFIRMATION PHONE NUMBER:____

(Eastern) m-Wddty

4. AUTHENTICATION (If Required):

(Number) (Codeword)

5. EMERGENCY CLASSIFICATION

[] NOTIFICATION OF UNUSUAL EVENT [f] ALERT [E] SITE AREA EMERGENCY [] GENERAL EMERGENCY

6. [] Emergency Dedaration At [f] Termination At TIME/DATE:- !_J__J (If B. go to Item 16)

(Eastern) mm dd yy

7. EMERGENCY DESCRIPTIONS/REMARKS:

6. PLANT.CONDmcON: [K] IMPROVING [E] STABLE [] DEGRADING

9. REACTOR STATUS: [E] SHUTDOWN: TIME/DATE: J%..J []

0 _ POWER (Eastern) mm dd yy

10. EMERGENCY RELEASE(S):

[F] NONE (Go to Item 14) [] POTENTIAL (Go to Item 14) [] IS OCCURRING [] HAS OCCURRED

11. TYPE OF RELEASE: [] ELEVATED 0 GROUND LEVEL RI AIRBORNE: STARTED: 00.00 STOPPED.

Time (Eastern) Date Time (Eastern) Date

[ UQUID.

L] STARTED. -- J j._ STOPPED-.

"Tmne (Eastern) Date Time (Eastern) Date

-12. RELEASE MAGNITUDE: 0 Cudes Per Sec [] Cudes NORMAL OPERATING uMITS: 0 BELOW [] ABOVE AD NOBLE GASES fl.flQEjQ F13 IODINES v por00

[~J PARTICULATES 000.E+/-0 El OTHER

-13. ESTIMATE OF PROJECTED OFFSITE DOSE: [] NEW [] UNCHANGED PROJECTION TIME: __

TEDE T(Eastern) nwem mrem ESTIMATED DURATION: ..- 1 IRS.

SITE BOUNDARY 0abE+0 0D.E+00 2 MILES 00E+00 0,0E+0 5 MILES 0 0-+10 10 MILES DE+fl DOEf00

"-14. METEOROLOGICAL DATA [] WIND DIRECTION (from) g [] SPEED (mph) _

[] STABILITY CLASS - [] PRECIPITATION (type) k15mLIn

15. RECOMMENDED PROTECTIVE ACTIONS:

NO RECOMMENDED PROTECTIVE ACTIONS EVACUATE SHELTER IN-PLACE OTHER

16. APPROVED BY, TIME/DATE:__ __ ___

(Name) (Thle) (Eastern) mm dd yy

• ItItems 8-14 have not changed, only Items 1-7 and 15-16 are required to be completed

"" Information may no( be available on Initial notification

( C e

0 0- m 7.

III 0

'PRIi 0 III P P P0 0 lip 0 d! I I 0 ill 10 0

CD I

.4 0

I I C II 0

z 0

0 Cd pppp I C C C, 4-.

U1 I I. 0 AA mull

§ A k t j C) pp p, I I 0 p cr 0

N)

Enclosure 5.5 HPI0/B/1009/026 Emergency Notification Page 3 of 6

2. Dose Assessment Forecast Report ("Green Sheet"):

PAG Dose Lkolts I fer 5 reml PAG Exoeeded at VWtBou.eaq Ho No0 PAG Distances (miles): WA WA MONITOR CORRECTION FACTORS:

Pat#way 1 T-ihe s.,ce Trip (Hrs) 00O Ice Condenser No Recv0 Sprays On Hold-Up Tirne -=24 hts Cont Leak Rate Method Cont Leak Type Coot Pressut Coot Leak Rate Cont Bypass Fraction Filters Yes SG Partboned Pool Scrib&i F'eld Measuwement Datoace Drection Fuel Assemby Ae (Days)

Enclosure 5.5 IIP/O/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/O/A/5000/001 (Classification Of Emergency) if offsite dose exceeds Selected Licensee Commitment (SLC) limits.

0 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 > 500 mrem

• General Emergency - is classified if site boundary dose rate exceeds Forecasted TEDE dose > 1 rem; and/or Forecasted CDE Thyroid dose > 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 R/hr AND Either containment pressure is greater than 0.3 psig, OR An actual containment breach is known to exist.

Enclosure 5.5 HP/0/B1I1009/026 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 #t 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 mrem/hr; using the following guidelines:

"* 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.

B. Quantity of each form of radioactive material released:

"* Noble Gases

"* Iodines

"* Particulates 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

Enclosure 5.5 HPIO/B/1009/026 "EmergencyNotification Page 6 of 6 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. Proiection 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 < 1 rem TEDE or < 5 rem Adult Thyroid CDE.

B. Evacuate - recommended for affected PAZs if the projected dose is > 1 rem TEDE or a 5 rem Adult Thyroid CDE; and recommend Shelter in Place for all other PAZs.

Duke Power Company (1) ID No. SI1101B20051001 (Ro4-0o)

PROCEDURE PROCESS RECORD Revision No. 002 FOR STANDARD PROCEDURES PREPARATION (2) Procedure

Title:

Emergency Response Offsite Dose Projections (3) Prepared By l- L/ - Date I- ?-0c-z)S (4) Applicable To: 0 ONS ýd MNS JCNS 1/7 (5) Technical Advisor IVA__________9_Y4 (6) Requires 0 Yes 0 No *' Yep [ No No SNSD 228 Applicability YES = New procedure or reissue with major changes - "

Determination NO = Reissue with minor changes OR to incorporate previously approved changes (7) Review (QR) By_ B By / LŽ2/ ZzZ Date Date 9-17. Date ,,Z7/'03 Cross-Disciplinary By By______ ByBy Review (QR) NA Date NA Date 2-12-OPj NA Date Z-1 'O Reactivity Mgmt. By__ By By Review (OR) NA Date NA D.' Date________

Mgmt Involvement By By_ By Review (Ops. Supt) NA.aN Date 21;Z;71,, NA I Date Z./,27*

• ,, (8) Additional By (QA) By (QA) By (QA)

Reviews Date Date Date By_ _ _ _ Byy~l.. *ý By Q $4&

Date Date 3 34',

.- Date  ;- //o 3 (9) Approved By By______________- By 3-:!---O -3 Date_ Date ..'--- "4--,3 Date____________

(10 ) 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 property 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?

ol Yes [] NA Charts, graphs. etc.. attached and property dated, identified, and marked?

0 Yes 0 NA Procedure requirements met?

Verified By - Date (14) Procedure Completion Approved Date (15) Remarks (attach adcikaa*pages.ifnecessay)

I Procedure No.

Duke Power Company Catawba and McGuire Nuclear Stations SI/O/B/2005/001 Revision No.

002 Emergency Response Offsite Dose Projections Electronic Reference No.

Reference Use MP0070PF t

I

SH/101/2005/00o 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 "rM 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.

2. References 2.1 Earth Tech Raddose 5 Operator's Manual, Detailed Design Manual, 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/O1Bl10091006 Alternative Method for Determining Dose Rate Within the Reactor Building MNS - HPIOBlO/10091002 Alternative Method for Determining Dose Rate Within the Reactor Building 2.3 Station specific procedure for abnormal unit vent sampling:

MNS - HP/O/B/1009/006 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) i

SHIO/BI20051001 Page 3 of 16 2.8 Station specific procedures for classification of emergencies:

CNS - RP/O/A/50001001 Classification of Emergency MNS - RP/O/A/5700/000 Classification of Emergency

3. .imtmils 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/O/B/2005/001 Page 4 of 16 NOTE: This procedure is for "Normal Mode" operation of Raddose only. The "Automatic Mode" contains limited choices and default assumptions. Ile "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 important that the release time entered is the time of the actual release. This time is transferred to the Electronic Emergency Notification Form.

"* 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/0/B/2005/001 Page 5 of 16

,12.9.2 Select "Network Data" to continue previous dose assessment calculation that was previously performed at another facility.

"* Select "TSC" to retrieve previous dose calculation that was performed at the TSC.

"* Select "EOF" to retrieve previous dose calculation that was performed at the EOF.

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 = °C).

"* Enter air temperature in degrees centigrade (Temperature in

°C).

"* 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.

srhOf//2005/001 Page 6 of 16 Manually overwrite meteorological data or "Requery" for 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 core that is partially melted after being uncovered for some period of time.

S-IO/BI2005/001 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 pini 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 Enclosure 5.2 (Steam Source Term Release) for NG Method selection.

4.4.3.2 IF a containment release is occurring or suspected, refer to Enclosure 5.3 (Containment Source Term Release) for NG Method selection.

SHIO/B/2005/001 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 Select 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 main 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?"

• IF the Containment High Range Monitor is greater than the values in the table below, answer the question "Yes".

High Range Containme-nt Monitor Reading Time After Shutdown (hours) (EMF 51 A/B or EMF 53 A/B) 0-2 864 R/Hr 2-4 624 R/Hr 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/0n1/200os/001 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 real-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 the real-time reports

SH/0I3/2005/0o 1 Page 10 of 16

- "View Protective Action Zones" may be selected to view the Wind Direction/Affected Zone table.

- "Print Summary Form" may 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.

suJ fI2005/oo001 Page 11 of 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".

sH/0/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, TItEN 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 offorecasted 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 mode.

sH/0113120051001 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 SRDCF - EDE EDE SRDcF = SRD correction factor TEDE = 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.

SRDcp 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:

sH0OnB/20o5/001 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-1 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 0 Particulates

sHIOIBI2005/001 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 N=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 Report" (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.

slIO/B/2005/oo1 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

Enclosure 5.1 SI/0/B/2005/001 Meteorology 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 594-0341/0289 "o 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 (AT") is unknown, use the following default values:

Enclosure 5.1 swI011320051001 Meteorology Page 2 of 2 5.1.4 Use the following tables to determine stability class when AT data is available:

Enclosure 5.2 SHO//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 steam 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/15min).

0 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.

Enclosure 5.2 sw0O/B2005/001 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:

3 RR = EMF x CF x AJ x LR x (0.41ft3 /lbm x 28320 ml/ft x 1E-6 CiIlCi x l13600Ihris)

Where:

RR = 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 lbm/15 min NOTE: Raddose 5 calculates steam source term for the GRABSL method as follows:

RR = SL, x LR x (0.41ft 3/lbm x 28320 ml/ft3 x IE-6 Ci/ptCi x 1/3600/hr/s Where:

RR = release rate activity in Ci/sec SLg = secondary grab sample ([tCi/ml)

LR = steam release rate from safety valves pounds mass of steam released through the respective valves during the valve open period (lbm/hr) default release rate = 5.235E4 Ibm/15 min

Enclosure 5.2 SH/0/B/2005/001 Steam Source Term Release Page 3 of 4 I

NOTE: Raddose calculates the steam source term for the BACKSL method as follows:

RR = Field Measurement Device Reading (mRlhr) x FM Device Correlation (ftCilcc)/(mRlhr)IXIQ(seclm 3) x (1E-6 Ci/tCi x 1E+6 cc/m3=l) 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

Enclosure 5.2 swf0B/2005o001 I

Steam Source Term Release Page 4 of 4 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*** 1/VOPEN R/hr x 1,Ci/ml x _ gal x _. min x lbmr x Ix sec.

R/hr min 2400 Ibm

• Note: If EMF53<5 R/hr, use 5 R/hr.

Activity noble Gas x 3.785E-3 Ci ml x = Ci

[tCi gal sec Activity noble Gas x Iodine Ratio LOCA Activity LODCA Iodine 131 Equivalent

= _ _ Ci/sec Activity noble Gas X Iodine Ratio coremelt Activity Ixore 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 = 1E-6 Ci/tCi x 3.785E3 ml/gal 2400 - Mass of steam in the faulted steam generator-, conservative valve is 2400 Ibm (mass of steam from SIG nozzle to MSIV)*** If Lbsmr > 2400 Ibm; use 2400 Ibm.

Time since Rx Trip EMF 53 Correction Factor Iodine Ratio tOCA Iodine Ratio Cor, Melt (hours) **(CF)

Ž0 7.74 E+3 1.52 E-3 4.23 E-3

Ž2 9.82 E+3 1.95 E-3 1.46 E-3

Ž4 9.96 E+3 2.24 E-3 2.21 E-2

Ž8 1.28 E+4 2.63 E-3 4..09 E-2

>24 2.15 E+4 3.00 E-3 1.14 E-1

Ž48 3.69 E+4 3.05 E-3 1.78 E-1 Emergency 0 or Drill 0 Prepared by:

Enclosure 5.3 S/O0/B/2005/001 Containment Source Term Release Page 1 of 3 5.3.1 Determine type of accident source term release path and EWF 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 o "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) < lE7 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(-) > 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 "OK" 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) IF "Manual" was selected in Step 4.2.7, enter the monitor reading.

Enclosure 5.3 sw0/13/2005/00I Containment Source Term Release Page 2 of 3 NOTE: Raddose 5 calculates the containment source term for the CONL, CONH, AND CONHH methods as follows:

RR = EMF x CF x AJ x BY x Ci/[LCi x 1/3600 hr/sec Where:

RR = release rate activity in Ci/sec EMF = 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)

EMF = 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)

EMF = EMF53A/B - CNS or EMF51A/B - MNS R/hr reading whenever EMF39(H) is

>lE+6 cpm (offscale) or EMF39 sample line is isolated, or EMF containment sample pump is tripped (CONHH Method)

CF = Containment Noble Gas monitor Correlation Factor AJ = Adjustment factors for Noble Gas; Iodine's and Particulates BY = 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)

LR = Leak Rate of containment air to the annulus or environment (ml/hr) 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)

Enclosure 5.3 SHO0/B/2005/001 Containment Source Term Release Page 3 of 3 NOTE: Raddose 5 calculates the containment source term for the GRABC method as follows:

RR = EMF x CF x AJ x BY x Ci/ACi x 1/3600 hr/sec Where:

CONg = Containment grab sample ([tCi/ml)

All other parameters are the same as defined in the NOTE above.

Enclosure 5.4 SHO0/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 "UV1L" or "UV2L" as appropriate.

(b) IF EMIF 36(L) > 1E7 cpm AND EMF 36(H) < 1E6 cpm, select "UVIH" or "UV2H" as appropriate.

(c) IF EMF 36(H) > 1E6 cpm, select "UV1HH" or "UV2HII" as appropriate.

Enclosure 5.4 SH/0/B/2005/001 Unit Vent Source Term Release Page 2 of 4 (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" (v) When all inputs on the Unit Vent Release Pathway screen are correct, click on "OK" (e) IF "Manual" was selected in Step 4.2.7, enter the unit vent monitor reading (f) 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 Cilsec.

(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 "DRCTI" 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.

Enclosure 5.4 SH/0/B/2005/001 Unit Vent Source Term Release Page 3 of 4 NOTE: Raddose 5 calculates the unit vent source term for the UVIL, UVIH, UV1HH, 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:

x 28320 ml/ft 3 RR = EMF x CF x AJ x FR x 1E-6 Ci/fiCi x 1/60 min/sec Where:

RR = release rate activity in Ci/sec EMF = Use EMIF36L counts per minute (cpm), if reading < 1E+7 cpm and vent EMF sample pump is not tripped (UVIL, UV2L)

EMF = Use EMF36H cpm reading if EME6L is offscale and EM < 1E+6 cpm M6H and sample pump is not tripped (UV1H, UV2H)

EMF = Use EMF54 - CNS, EMF36HH - MNS (R/hr) reading if EMF36L and EMF36H are offscale, and/or vent EMP sample pump is tripped (UVIHH, UV2H)

CF = Unit Vent radiation monitor Noble Gas Correlation Factor AJ = Adjustment Factors for Noble Gas, Iodines 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

Enclosure 5.4 SwOIB200o5/001 Page 4 of 4 Unit Vent Source Term Release NOTE: Raddose 5 calculates the unit vent source term for the GRABV1 and GRABV2 methods as follows:

mlI/ft 3 RR = UVg x FR x 1E-6 Ci/ItCi x 1/60 min/sec x 28320 Where:

RR = release rate activity in Ci/sec UVg = unit vent grab sample ([tCi/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 NOTE: Raddose 5 calculates the source term for the UVI-BACK, UV2-BACK method as follows:

RR Field Measurement Device Reading (mR/hr) x FM Device Correlation 3 3 (ItCilcc)I(mRlhr)IXIQ(sec/m ) x (1E-6 Ci/ljCi x 1E+6 cc/m =1)

Enclosure 5.5 Radiological Emergency Action Levels SwO//B/2005/001 Page 1 of 1 I

5.5.1 Evaluate the Emergency Action Levels (EALs) based on radiological conditions in the affected site's EAL procedure:

CNS - RP/OIAI50001001 - Classification of Emergency MNS - RPIO/A/57001000 - Classification of Emergency

Enclosure 5.6 SI /O0/B/2005/001 age 1 of 2 Raddose 5 Green Form Report P Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech ep #: 1 Current Date: 12/09/2002 St St ep Date: 12/09/2002 Current Time: 14:41 ep Time: 12:15 Operator: GTJ St

• • • FORECAST FOR 4 HOURS***

ACCIDENT DESCRIPTION: General Emergency has NOT been declared Accident Time: 12109/2002 1200 hrs Reactor Shuldown:1 2/09/2002 1200 hrs PATHWAY 1 1.31 E+05 ftA3/min Accident Type: LOCA Flow Rate: 1.54E+00 R/hr Monitor Reading: (P)

Noble Gas Method UV1HH (EMF54)

VentCF = 0.328 RELEASE RATES:

3.12E+01 Ci/s Above Normal Operating Umits Noble Gas Release Rate (Ci/sec):

4.61 E-02 Ci/s Iodine Release Rate (Ci/sec):

3.54E-03 Ci/s Particulate Release Rate (Ci/sec):

ACTUAL, FORECAST AND TOTAL (Forecast + Integrated) DOSES:

Distance TEDE (mrem) Thyroid CDE (mrem)

Actual Forecast Total Actual Forecast Total (miles) 1.67E+01 2.67E+02 2.84E+02 1.71 E+02 2.74E+03 2.91 E+03 0.50 7.71 E+00 1.23E+02 1.31E+02 6.46E+01 1.03E-+03 1.10E+03 1.00 5.40E+01 5.74E+O1 2 32E+01 3.74E+02 3.97E+02 2.00 3.36E+00 O.OOE+00 1.42E+01 1.42E-+01 0OOE+00 9.41E+01 9.41E+O1 5.00 4.79E-00 4.79E+00 0.OOE-i00 2.81E+01 2.81E1+01 10.00 0.00E+00 METEOROLOGICAL DATA 9.5 mph (P) Stability Class: D (P)

Wind Speed:

Wind Direction: From 44.90 deg To 224.90 deg RECOMMENDED PROTECTIVE ACTIONS:

Evacuate: None Shelter: None

Enclosure 5.6 SH/0/B/2005/001 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: 12/09/2002 Step #: 1 Step Date: 12/09/2002 Current Time: 14:41 Step Time: 12:15 Operator: GTJ

• • • FORECAST FOR 4 HOURS TOTAL (Forecast+ Integrated) DOSES FROM 12/0912002 12:00 TO 16:15:

Distance Current Dose Rates (mrem/hr) Dose (mrem) XIQ Thyroid Thyroid (miles) TEDE CDE TEDE CDE (seclm3) 0.50 6.68E+01 6.85E+02 2.84E+02 2.91 E+03 3.55E-05 1.00 3.08E+01 2.59E+02 131E1+02 1.10E+03 1 34E-05 2.00 1.35E+01 9.35E+01 5 74E+01 3.97E+02 4 85E-06 5.00 3.49E+00 2.35E+01 1 42E+01 9.41E+01 1 22E-06 10.00 1.36E+00 8.03E+00 4.79E-+00 2.81E+01 4.16E-07 DOSE CONVERSION FACTORS: mrem *rnV3/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 Limits: 1 rem 5 rem PAG Exceeded at Site Boundary? No No PAG Distances (miles): N/A N/A -

MONITOR CORRECTION FACTORS:

Pathway 1 Time Since Trip (Hrs) 0.00 Ice Condenser No Recirc Sprays On Hold-Up Time <=24 hrs Cont Leak Rate Method Cont Leak Type Cent Pressure Cont Leak Rate Cont Bypass Fraction Filters No SG Partitioned Pool Scrubbing Field Measurement Distance Direction Fuel Assembly Age (Days)