ML041050178

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Change to Emergency Plan Implementing Procedures
ML041050178
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 04/06/2004
From: Gordon Peterson
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041050178 (57)
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I Duke GARY R. PETERSON AtPower. Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MGO1 VP / 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 April 6, 2004 704 875 4809 fax grpeters @duke-energy. corn U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation McGuire Nuclear Station Docket Nos. 50-369,370 Change to Emergency Plan Implementing Procedures Attached to this letter are a revised Emergency Plan Implementing Procedure (EPIP) Index and a notice of revision to two (2)

Emergency Plan Implementing Procedures. These procedure revisions were evaluated pursuant to the requirements of 10 CFR 50.54 (q). The changes do not constitute a reduction in the effectiveness of the emergency plan and the plan continues to meet the requirements of 10 CFR 50.47 (b) and 10 CFR 50 Appendix E. Duke implemented these changes on March 11, 2004. A copy of these changes is also being sent to the NRC Office of Nuclear Material Safety and Safeguards as per 10 CFR 72.44 (f). Revision bars within the procedures indicate the revision. The following procedure index changes and procedure revisions have been implemented:

EPIP Index Page 1 Dated 3/11/2004 Rev. 45 EPIP Index Page 2 Dated 3/11/2004 Rev. 45 REVISION to the following procedures:

SH/0/B/2005/001 Dated 3/11/2004 Rev. 003 SH/0/B/2005/002 Dated 3/11/2004 Rev. 003 There are no new regulatory commitments in this document. Two copies of this submittal are being supplied to the Regional Administrator of Region II via this submittal. Questions on this document should be directed to Kevin Murray at (704) 875-4672.

Gary R. Peterson A N lS www.duke-energy.com

U.S. Nuclear Regulatory Commission Document Control Desk April 6, 2004 Page 2 Attachments cc: Mr. Luis Reyes, Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. Martin J. Virgilio, Director Office of Nuclear Material Safety and Safeguards Mail Stop T-8A23 Washington, D.C. 20555-0001 MNS Master File No. 529.01 (w/o attachment)

Leonard N. Olshan, USNRC U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 NRC Senior Resident Inspector McGuire Nuclear Station

U.S. Nuclear Regulatory Commission Document Control Desk April 6, 2004 Page 3 bcc: R. L. Gill, Manager NRIIA (ECO5P)

Electronic Licensing Library (ECO50)

EP File 111

DUKE POWER McGUIRE NUCLEAR SITE EMERGENCY PLAN IMPLEMENTING PROCEDURES APPROVED:

S SURANCE MANAGER DATE APPROVED I I Ig EPIP Index Page 1 Dated 3/11/2004 Rev. 45 EPIP Index Page 2 Dated 3/11/2004 Rev. 45 SH/O/B/2005/001 Dated 3/11/2004 Rev. 003 SH/O/B/2005/002 Dated 3/11/2004 Rev. 003

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE # TITLE REVISION NUMBER RP/O/AI5700/000 Classification of Emergency Rev. 010 RP/O/A/5700!001 Notification of Unusual Event Rev. 020 RPI1/A/5700/002 Alert Rev. 020 RP/O/A15700/003 Site Area Emergency Rev. 020 RP/O/A/5700/004 General Emergency Rev. 020 RPIO/A/5700/006 Natural Disasters Rev. 010 RPIO/A/5700/007 Earthquake Rev. 007 RPIO/A/5700/008 Release of Toxic or Flammable Gases Rev. 004 RP10/A157001009 Collisions/Explosions Rev. 002 RPIO/A/5700/01 0 NRC Immediate Notification Requirements Rev. 013 RP/O/A/5700/0 l Conducting a Site Assembly, Site Evacuation or Containment Rev. 006 Evacuation RP/0/A/5700/012 Activation of the Technical Support Center (TSC) Rev. 024 RP/O/A/5700/018 Notifications to the State and Counties from the TSC Rev. 013 RP/O/A/5700/019 Core Damage Assessment Rev. 004 RP/01A/57001020 Activation of the Operations Support Center (OSC) Rev. 015 RP/0/A/5700/022 Spill Response Procedure Rev. 009 RPIO/A/5700/024 Recovery and Reentry Procedure Rev. 002 RP/0/A15700/026 Operations/Engineering Required Actions in the Technical Rev. 003 Support Center (TSC)

RP/0/B/5700/023 Public Affairs Emergency Response Plan Rev. 003 RP/01B1/5700/029 Notifications to Offsite Agencies From The Control Room Rev. 001 HP/O/B/1009/002 Alternative Method for Determining Dose Rate Within Rev. 002 the Reactor Building HP/0/B1/0091003 Recovery Plan Rev. 004 HP/IOB/1009/006 Procedure for Quantifying High Level Radioactivity Rev. 006 Releases During Accident Conditions HP/0IB/1009/010 Releases of Radioactive Effluents Exceeding Selected Rev. 006 Licensee Commitments I March 11, 2004 Rev. 45

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE # TITLE REVISION NUMBER HP10/3/1009/021 Estimating Food Chain Doses Under Post-Accident Conditions Rev. 001 HP/O/B/1 009/022 Accident and Emergency Response Rev. 003 HP/O/B/1 009/023 Environmental Monitoring for Emergency Conditions Rev. 005 HP/O/B/1009/024 Personnel Monitoring for Emergency Conditions Rev. 002 HP/0//1 009/029 Initial Response On-Shift Dose Assessment Rev. 007 SH/01B/2005/001 Emergency Response Offsite Dose Projections Rev. 003 SH10JB/2005/002 Protocol for the Field Monitoring Coordinator During Emergency Rev. 003 Conditions SH110B12005/003 Distribution of Potassium Iodide Tablets in the Event of a Rev. 000 Radioiodine Release SR/O/B/2000/001 Standard Procedure for Public Affairs Response to the Rev. 004 Emergency Operations Facility SR/O/13/2000/002 Standard Procedure for EOF Services Rev. 003 SR/O/B/2000/003 Activation of the Emergency Operations Facility Rev. 012 SR/O/B/2000/004 Notification to States and Counties from the Emergency Rev. 007 Operations Facility EP Group Manual Section 1.1 Emergency Organization Rev. 018 PT/O/A/4600/088 Functional Check of Emergency Vehicle and Equipment Rev. 007 2 March 11, 2004 Rev. 45

(R04-01) Duke Power Company (1) ID No. SHIO[/B/2005/00I PR6CEDURE PROCESS RECORD Revision No. 003 FOR STANDARD PROCEDURES PREPARATION

<> (2) Procedure Tite: Emergency Response Offsite Dose Projections (3) Prepared By YM)AUL4 W40t" -Date 9-a2o _ C5 (4) Applicable To: OM l NS M< CNS (5) Technical 1 11 Advisor LJ Z( OdJ____(C C oavc-y WG (6) Requires O Yes O No AYes O No Yes O No NSD 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 JB By Date Date. 3/:1 Date 3 0 Cross-Disciplinary By_ By & D YG8 By Review (OR) NA Date N/ Dte 2/o0 NA DateZ- 0O $

Reactivity Mgmt. BY_ By By Review (OR) NA _Date NA _Date /ND° MgmL Involvement By By By Review (Ops. Supt.

A Date NAiDale / NA&G' Date___

(8) Additional By (QA) By (QA) By ttk At Reviews Date Date Date A /6S By By . By Date Date <7- Date_

(9) Approved By __ __ B By __ __

Date Date 6 Y-7/--o Date 3 =//-Of£ (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 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?

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

o Yes 0 NA Procedure requirements met?

Verified By Date (14) Procedure Completion Approved Date (15) Remarks (attach add ionai pages, ifnecessary)

Duke Power Company Procedure No.

Catawba and McGuire Nuclear Stations sO/B/sL2005/oo 1 Revision No.

Emergency Response Offsite Dose Projections 003 Electronic Reference No.

Reference Use MP007OPF

SH/0/B/2005/00 l Page 2 of 17 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 Tm Windows(C 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 I and 2 2.2 Station specific procedures for alternate method of determining Reactor Building dose rate:

CNS - HPIO/B/1009/006 Alternative Method for Determining Dose Rate Within the Reactor Building MNS - HP/O/B/1009l002 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)

SH/0/13/2005/00 I Page 3 of 17 2.8 Station specific procedures for classification of emergencies:

CNS - RPIOIA/5000/001 Classification of Emergency MNS - RP/OIA/5700I000 Classification of Emergency 2.9 Station specific procedures for notification to the States and Counties from the Technical Support Center:

CNS - RPO1IBI5000I006B Notifications to States and Counties from the Technical Support Center MNS - RP/O/A/5700/018 Notifications to State and Counties from the Technical Support Center 2.10 SR/I/B/2000/004 Notification to States and Counties from the Emergency Operations Facility I

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.

SH/0/B/2005/o01 Page 4 of 17 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.

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 "P1 Server" for program query of fifteen minute average data from Operator Aided Computer (OAC).
  • Select "Manual" for keyboard entry of data.

SH/O/B/2005/001 Page 5 of 17 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.

4.2.9.2 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." I 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

SH/IOB/2005/O01 Page 6 of 17 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 0 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.
  • 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."

SH/OIB/2005/OO1 Page 7 of 17 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.

E the Containment High Range Monitor is greater than the values in the IF 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.
  • "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.

SH/O/B/2005/001 Page 8 of 17

  • "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 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.

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 Temn 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.

SH/B1/2005/00 1 Page 9 of 17 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 Containment 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 RIHr

>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.

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.

SH/0/B/2005/001 Page 10 of 17

  • "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

- "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.

SH/0/13/2005/00 1 Page 11 of 17 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 the same as was performed 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.

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.

SH/I/B/2005/00 1 Page 12 of 17

  • 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 0.5 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".

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.

SH/0a13B2005/001 Page 13 of 17 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.

4.7.11.1 Review the dose assessment reports.

4.7.11.2 IF the projected dose OR field measurements at the site boundary is 2 5 rem CDE thyroid, notify the TSC Dose Assessors or the EOF RAM, as applicable, to direct the Offsite Agency Communicators to edit the ENF to add the PAR for public use of KI per the applicable procedures:

CNS - RP/OIBI5000/006B Notifications to States and Counties from the Technical Support Center MNS - RP/0/A15700/018 Notifications to States and Counties from the Technical Support Center SR/IOBI2000/004 Notification to States and Counties from the Emergency Operations Facility 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/0/1B12005/OOI Page 14 of 17 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).

SRDCF = TEDE 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.
  • 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 to the Field Monitoring Coordinator and the OSC. I

SH/O/B/2005100 1 Page 15 of 17 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:

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 mRemlhr.

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
  • Particulates

SH/O/B/2005/001 Page 16 of 17 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 4.10.4.1, 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=0 degrees 4.10.6.2 Wind Speed (miles per hour) 4.10.6.3 Stability Class 4.10.6.4 Precipitation (type) (inches per 15 minute period) 4.10.7 Line #15 - Recommended PAZ protective actions as indicated on the "Green Form Report" (example displayed on Enclosure 5.6).

4.10.7.1 E the projected dose OR field measurements at the site boundary is 2 5 rem CDE thyroid, notify the TSC Dose Assessors or the EOF RAM, as applicable, to direct the Offsite Agency Communicators to edit the ENF to add the PAR for public use of KI per the applicable procedures:

CNS - RP/OIB/5000/006B Notifications to States and Counties from the Technical Support Center MNS - RP/0/A/5700/018 Notifications to States and Counties from the Technical Support Center SRIO/B/20001004 Notification to States and Counties from the Emergency Operations Facility

SH/O/B/2005/00 1 Page 17 of 17 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.
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 SH1O/B/2005/001 Meteorology Page I 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) = 0°
  • Use lower tower wind direction if upper tower wind direction is not available: in degrees from North (N) = 0° 5.1.2 IF Meteorological Tower is not available, obtain meteorological information from:
  • Duke meteorologist at 8-382-0139
  • 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:

CNS I MNS At Stability Class At Stability Class Between 1000-1600 hours: -0.3 D -0.3 D Between 1600-1000 hours: +1.3 F t +1.3 F

Enclosure 5.1 SH/I/B/2005/001 Meteorology Page 2 of 2 5.1.4 Use the following tables to determine stability class when AT data is available:

CNS MNS Stability Class (AT in 'C) (AT in 'C)

A - Extremely Unstable AT < -0.97 AT * -0.95 B - Moderately Unstable -0.97 < AT * -0.87 -0.95 < AT < -0.85 C - Slightly Unstable -0.87 < AT * -0.76 -0.85 < AT * -0.75 D - Neutral -0.76 < AT < -0.25 -0.75 < AT < -0.25 E - Slightly Stable -0.25 < AT < +0.76 -0.25 < AT < +0.75 F - Moderately Stable +0.76 < AT * +2.04 +0.75 < AT * +2.00 G - Extremely Stable +2.04 < AT +2.00 < AT

Enclosure 5.2 SH/W/B/2005/001 Steam Source Term Release Page I 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:

  • "SGTRM" - steam generator tube rupture core melt 5.2.3 Select the appropriate steam line Noble Gas Method as follows:

NOTE: Using the EMF data is the preferred method. Other Noble Gas Methods may be used as conditions and data availability warrant.

E steam line monitor EMF data is available, use the following guidance for Noble Gas IF 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) F manual data entry was selected in Step 4.2.7, enter the monitor data and the flow rate.

E secondary side steam sample data is available, select GRABSL.

IF (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).

Enclosure 5.2 SH0/B1/20051001 Steam Source Term Release Page 2 of 4

  • 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.

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:

RR = EMF x CF x AJ x LR x (0.41ft3/lbm x 28320 mI/ft3 x 1E-6 Ci/pCi x 1/3600/hr/s)

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 Ibm/15 min

Enclosure 5.2 SFYO/B/2005/001 Steam Source Term Release Page 3 of 4 NOTE: Raddose 5 calculates steam source term for the GRABSL method as follows:

RR = SLr x LR x (0.4lft3 Abm x 28320 mI/ft 3 x IE-6 Ci/ttCi 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 (Ibm/hr) default release rate = 5.235E4 Ibm/15 min I

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

RR = Field Measurement Device Reading (mR/hr) x FM Device Correlation (gtCi/cc)/(mR/hr)/X/Q(sec/m 3 ) x (IE-6 Ci/pCi x IE+6 cc/M3 )

5.2.4 For Catawba only, use Step 5.2.5 source term assessment worksheet with steam generator tube rupture coincident with loss of offsite power; when the following conditions are present:

  • Loss of offsite power and steamline radiation monitor is unavailable
  • Primary to secondary coolant leakage is occurring
  • Steam source term release is occurring
  • Computer program for calculating steam release is not available l

Enclosure 5.2 SHI0/13/2005/001 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/ l  :- Time since trip: hours mm dd yy hh mm II NOTE: If EMF53 <5 R/hr, use 5 R/hr.

I EMF53 Reading x Correction Factor x LRps x dT x Lbsmr x INOPEN R/hr x iiCi/ml x gal x min x lbmr x I x R/hr min 2400 Ibm __ sec.

Activity noble Gas x 3.785E-3 Ci ml x Ci pCi gal sec Activity noble Gas x Iodine Ratio LOCA Activity LOCA Iodine 131 Equivalent Ci/sec Activity noble Gas x Iodine Ratio core melt Activity Core Melt Iodine 131 Equivalent

=_ Ci/sec Where:

LRps = Primary to secondary leak rate in gallmin.

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 seconds.

3.785E-3 = I E-6 Ci/IiCi x 3.785E3 ml/gal 2400 = Mass of steam in the faulted steam generator; conservative value is 2400 Ibm (mass of steam from S/G nozzle to MSIV)*** If Lbsmr > 2400 lbm; use 2400 lbm.

Time since Rx Trip EMF .53 Correction Factor Iodine Ratio - Iodine Ratio Core 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-l

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

Enclosure 5.3 SHwO/B/2005/001 Containment Source Term Release Page 1 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:

NOTE: Using the EMF data is the preferred method. Other Noble Gas Methods may be used as conditions and data availability warrant. l

  • 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) < IE7 counts per minute (cpm), select "CONL".

(b) IF EMF 39(L)> 1E7 cpm AND EMF 39(H)< IE6 cpm, select "CONH".

(c) IF EMF 39(H)> IE6 cpm, select "CONHH".

E containment sample line is isolated OR containment sample pump is tripped, use the IF 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

Enclosure 5.3 SuIO/B/2005/oo 1 Containment Source Term Release Page 2 of 3 (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 or containment samples. 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.

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 IE-6 Ci/tCi x 1/3600 hr/sec x LR Where:

RR release rate activity in Ci/sec EMF The appropriate EMF reading, in cpm or R/hr, as applicable.

CF Containment Noble Gas monitor Correlation Factor AJ Adjustment factors for Iodine 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 (mi/br) 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 SW/0B/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 = CONg x BY x LR x IE-6 Ci/iCi x 1/3600 hr/sec Where:

CONg = Containment grab sample (jiCi/ml)

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

Enclosure 5.4 SH/0/B/2005/001 Unit Vent Source Term Release Page I 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 Steam 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:

NOTE: Using the EMF data is the preferred method. Other Noble Gas Methods may be used as conditions and data availability warrant.

  • 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) < IE7 counts per minute (cpm), select "UVIL" or "UV2L" as appropriate.

(b) IF EMF 36(L) > IE7 cpm AND EMF 36(H) < IE6 cpm, select "UV IH" or "UV2H" as appropriate.

(c) IF EMF 36(H) > IE6 cpm, select "UVIHH" or "UV2HH" 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 one of the following choices 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.

NOTE: BACKVI and BACKV2 CANNOT be chosen on the first time step. l (b) IF Field Team Data is available, select "BACKVI" or "BACKV2" as appropriate. l (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.

Enclosure 5.4 SHWO/1/2005/001 Unit Vent Source Term Release Page 3 of 4

  • Check unaffected unit vent monitor data.
  • IF appropriate, repeat Step 5.4.3 to include source term assessment for unaffected unit.

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:

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

RR = release rate activity in Ci/sec EMF = Use EMF36L counts per minute (c=m). if reading

  • IE+7 cvm and vei it 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 - CNS, EMF36HH - MNS (R/hr) reading if EMF36L and EMF36H are offscale, and/or vent EMF sample pump is tripped (UV IHH, UV2HH)

CF = Unit Vent radiation monitor Noble Gas Correlation Factor AJ = Adjustment Factors for lodines 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 SHwO/B/2005/oo 1 Unit Vent Source Term Release Page 4 of 4 NOTE: Raddose 5 calculates the unit vent source term for the GRABVI and GRABV2 methods as follows:

RR = UVg x FR x IE-6 Ci/ijCi x 1/60 min/sec x 28320 ml/ft3 Where:

RR = release rate activity in Ci/sec UVg = unit vent grab sample (ptCi/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 BACKVI, BACKV2 method as follows:

RR = Field Measurement Device Reading (mR/hr) x FM Device Correlation (IACi/cc)/(mRlhr)/X/Q(sec/m 3 ) x (IE-6 Ci/pCi x IE+6 cc/mi3 )

Enclosure 5.5 SWO/B/2005/001 Radiological Emergency Action Levels 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/A150001001 - Classification of Emergency MNS - RPIO/A15700/000 - Classification of Emergency

Enclosure 5.6 SHIO/B/2005/001 Raddose 5 Green Form Report Page I of 2 Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech Current Date: 12/09/2002 Step #: I Current Time: 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: 12109/2002 1200 hrs PATHWAY 1 1.31 E+05 Accident Type: LOCA Flow Rate: ftA3/min 1.54E+00 R/hr Noble Gas Method UV1 HH (EMF54) Monitor Reading: (P)

VentCF = 0.328 ____________ ______

RELEASE RATES:

Noble Gas Release Rate (Ci/sec): 3.12E+01 Ci/s Above Normal Operating Limits Iodine Release Rate (Ci/sec): 4.61 E-02 Ci/s Particulate Release Rate (Ci/sec): 3.54E-03 Ci/s 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 2.67E+02 2.84E+02 1.71E+02 2.74E+03 2.91E+03 1.00 7.71EE+00 1.23E+02 1.31E+02 6.46E+01 1.03E+03 1.10E+03 2.00 3.36E+00 5.40E+01 5.74E+01 2.32E+01 3.74E+02 3.97E+02 5.00 O.OOE+00 1.42E+01 1.42E+01 0.OOE+00 9.41E+01 9.41E+01 10.00 0.OOE+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: None Shelter: None

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

    • FORECASTFOR 4 HOURS
  • TOTAL (Forecast + Integrated) DOSES FROM 12/09/2002 12:00 TO 16:15:

Distance Current Dose Rates (mremlhr) Dose (mrem) x/O Thyroid Thyroid (miles) TEDE CDE TEDE CDE (seclm3) 0.50 6.68E+01 6.85E+02 2.84 E.02 2.91 E+03 3.55E-05 1.00 3.08E+01 2.59E+02 1.31 E+02 1.1OE+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 9.41 E+01 1.22E-06 10.00 1.36E+00 8.03 E+00 4.79 E+00 2.81 E.01 4.16E-07 DOSE CONVERSION FACTORS: mrem

  • mA3/Ci'hr TEDE: 2.15E+07 PlumeEDE: 8.65E+04 Ground EDE: 7.33E+06 CDE Thyroid: 4.1 8E+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 rnrem 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 Cant Leak Rate Method Cant Leak Type Cant Pressure Cant Leak Rate Cant Bypass Fraction Filters No SG Partitioned Pool Scrubbing Field Measurement Distance Direction Fuel Assembly Age (Days)

(R04-0 1)

Duke Power Company (1) ID No. SW/O/B/2005/002 PROCEDURE PROCESS RECORD FOR STANDARD PROCEDURES Revision No. 003 PREPARATION (2) Procedure

Title:

Protocol for the Field Monitorinq Coordinator During Emergency Conditions (3) Prepared By K)AAYA-"- -Date _ _q - 5 (4) Applicable To: 0 ONS M MNS J CNS (5) Technical 7L/

Advisor God cAuley / )J (6) Requires D Yes D No ly Yes O No CS Yes O No NSD 228 . II .-

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 y 4g By G-7 d 1 Date Date 3/i vdr Date 3//1of Cross-Disciplinary By_ By By fo0 G Review (QR) NA Date_ _ NA Date NA Date Reactivity Mgmt. By By By Review (QR) NA Date ~7I N$Date NA1W Date 3/i!/e' MgmtL Involvement By By By Review(Ops. Supt) NA Date NAA, Date 2/o NA CW Date (8) Additional By (QA) By (QA) By (QA)

Reviews Date Date_ Date By By.-/zOI , By BLl 6 t Date Date ql~" Date (9) Approved By By Ad Byz Date D ate __ _ _ _ _ _ _ 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 (WOII)

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 Date (14) Procedure Completion Approved Date (15) Remarks (attach additional pages, if necessary)

Duke Power Company Procedure No.

Standard Procedure for Catawba and McGuire SHIO/B/2005/002 Nuclear Stations Revision No.

Protocol for the Field Monitoring Coordinator 003 During Emergency Conditions Electronic Reference No.

Reference Use MP007OR4

SHO//B/2005/002 Page 2 of 8 Protocol for the Field Monitoring Coordinator During Emergency Conditions

1. Purpose To describe a systematic field monitoring method for sampling and identifying airborne plumes or liquid effluents in order to obtain field data indicative of the radiation exposure to the general public following an unplanned release of radioactive material.
2. References 2.1 Site specific procedures for emergency environmental monitoring:

CNS - HP/O/B/1009/004, Environmental Monitoring for Emergency Conditions Within Ten Mile Radius of CNS MNS - HP/O/B/1009/023, Environmental Monitoring for Emergency Conditions 2.2 EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.3 Site specific emergency phone directories:

CNS - CNS Emergency Phone Directory MNS - RP/O/A/5700/014, Emergency Telephone Directory 2.4 SH/IO/B/2005/003, Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release

3. Limits and Precautions 3.1 Field Monitoring Team environmental sampling performed during emergency conditions does not replace or substitute for normally required environmental monitoring.

3.2 During any drill or emergency, personnel safety and safe operation of the vehicle are of primary concern.

4. Procedure 4.1 Field Monitoring Team (FMT) Activation 4.1.1 Consult with the TSC to determine the status and availability of field teams.

4.1.2 IF the site has NOT activated field teams, consult with the Dose Assessors the need for team activation.

SH/0/3B/200S/002 Page 3 of 8 4.1.3 Once the Radio Operator has established communications with the FMTs, the Field Monitoring Coordinator shall take control of the teams.

4.1.4 IF emergency conditions dictate, request additional survey vehicles.

4.1.5 IF emergency conditions dictate, request additional field monitoring support from an alternate station.

4.1.6 IF possible, ensure that at least one Field Monitoring Team (FMT) member be from the affected station.

4.1.7 Obtain an Emergency Planning map for the affected station.

4.2 Field Monitoring Team (FMT) Communications 4.2.1 Ensure the EOF Base Radio is set as follows:

  • For MNS, Black Box Selector Switch to "A" AND Radio Line Selector to Position "I".
  • For CNS, Black Box Selector Switch to "D" AND Radio Line Selector to Position "2".

4.2.2 Establish radio communications with each available field team.

4.2.3 Maintain open radio communications with each FMT.

l NOTE: Telephone numbers are displayed in Enclosure 5.2 (Telephone Numbers).

4.2.4 IF radio communications become inoperable, use telephone communications I as a back-up.

4.2.5 Provide only pertinent, general information when using the radio.

4.2.6 Communicate over the radio during a drill or exercise by beginning each transmission with "THIS IS A DRILL, THIS IS A DRILL".

NOTE: The phonetic alphabet is displayed on Enclosure 5.5 (Phonetic Alphabet).

4.2.7 Communicate information using the phonetic alphabet.

4.2.8 WHEN using the radio for communications with the FMTs, follow Federal I

Communications Commission (FCC) guidelines at all times.

SH/OB/2005/002 Page 4 of 8 4.3 Locating and Tracking the Plume NOTE: Steps in this section do NOT have to be performed in sequence.

4.3.1 Dispatch FMTs after vehicles and equipment have been confirmed operational.

4.3.2 IF onsite meteorological instruments are not available, consult with the National Weather Service (NWS) in Greenville/Spartanburg.

  • The NWS phone numbers are: 1-800-268-7785 or 1-864-879-1085 (unpublished).

4.3.3 Estimate which meteorological sector or sectors appear to be affected by the plume according to predominant wind direction AND, wind speed.

NOTE: Major roadways delineate the protective action zones (PAZs) surrounding the plant.

Either all or a portion of a PAZ would be expected to be affected to some degree by radioactivity released from the plant. Major roadways are therefore utilized to provide access to suspected regions (outer edges, leading edge(s), centerline) of the plume as necessary.

  • Major roadways on the field monitoring map are identified by numerical designations and responsibility level (federal, state, county, or city) designations.
  • Selected roadways on the field monitoring map are identified by a specific name, rather than a numerical responsibility designation.
  • Predetermined sampling locations are denoted by a red text oval on the field monitoring map. The sampling point designator indicates the protective action zone the point is in and the mileage from the plant. For example, locations are designated in the format.

S 2 Where:

S = Evacuation Zone 10 = MileRadius 2 = SamplePoint#2 4.3.4 Have the FMTs traverse the appropriate meteorological sector or sectors nearest the station, utilizing major roadways, selected roadways, or predetermined sampling locations, as appropriate.

SH/O/B/2005/002 Page 5 of 8 4.3.5 Request that the survey teams remain aware of terrain during air sampling or surveying (i.e., wind breaks formed by landscape or vegetation) which could inhibit acquiring a representative sample.

4.3.6 Have the survey vehicles report all dose rates above background.

4.3.7 Periodically request that the field team members report their accumulated dose.

4.3.8 Send each FMT to pre-determined sample locations, or other survey area as appropriate.

  • Use local landmarks and street names to indicate desired sampling location when a pre-determined location is not available or suitable.

4.3.9 WHEN possible, have the FMTs park their vehicles completely off the road.

4.3.10 Direct the FMTs to use the emergency flashers and the strobe, if available, whenever the vehicle is stopped.

4.3.11 Record each field vehicle's sampling history on Enclosure 5.3, OR in the Field Monitoring Coordinator ERO Facility Log.

4.3.12 Have the FMT obtain beta/gamma measurements and/or air samples.

4.3.13 Request survey teams to report the maximum radiation level and location of the boundaries while enroute AND while at sampling locations.

4.3.14 Request FMTs report the location of plume edges based on instrument readings.

4.3.15 Have the FMT take an Iodine sample WHEN, but not limited to:

  • Fuel rod gap activity release has occurred.
  • Waste gas decay tank rupture has occurred.
  • Any suspected iodine release has occurred.
  • The source of release is unknown AND the FMT is in the presence of measurable activity.

4.3.16 Use Enclosure 5.8 (I-131 Dose Calculation Methodology) to convert field team I-131 concentration to CDE thyroid dose rate.

SHwO/B/2005/002 Page 6 of 8 4.3.17 Notify FMTs, as appropriate, of changing plant and meteorological conditions that may have an effect on environmental measurements.

  • Record meteorological plant status information communicated to FMTs on Enclosure 5.4.

4.3.18 Notify FMTs of plant status as reported on the most recent Emergency Notification Form.

4.4 Special Sampling NOTE: Sample locations and sample collection methodologies are described in Reference 2.1. l 4.4.1 WHEN plant conditions are considered to be stabilized, have the field monitoring team perform special sampling. Special sampling may include, but is not limited to:

I I NOTE: Do NOT take smear samples on automobiles.'

  • Smears of surrounding areas (stationary, horizontal surfaces)
  • Vegetation
  • Sediment
  • Water
  • Milk
  • Integrated dose over time using TLDs 4.4.2 Communicate to teams to exercise care to prevent sample cross contamination.

4.4.3 Ensure that each FMT include (at minimum) the following information on each sample container:

  • Sample location
  • Sample reference date and time
  • Sample collected by

SH/0/3/2005/002 Page 7 of 8 4.5 Sample Analysis 4.5.1 Direct each FMT to retain the samples for analysis.

4.5.2 Consult with the RPM as to the best sample drop off and storage location.

NOTE: Normally, the samples will be analyzed at the ENRAD Laboratory. However, other laboratories may be used, including MNS, CNS, ONS, or other, as appropriate.

4.5.3 Consult with the RPM and Laboratory Management to make appropriate arrangements for sample transport for analysis.

4.6 FMT Dose Tracking 4.6.1 IF any field team member is likely to receive 5 rem or greater of thyroid dose, refer to Reference 2.4 for the distribution of potassium iodide tablets.

4.6.2 IF conditions are such that any FMT member may receive 500 mrem or greater during the drill or emergency, use Enclosure 5.6 (Field Monitoring Team Radiation Exposure Record) to track the FMT's exposure.

4.6.3 Use Enclosure 5.7 as guidance for dose to workers providing emergency services.

4.7 FMT Turnover 4.7.1 Consult with the TSC to establish FMT shift relief as appropriate.

4.7.2 Have the FMTs submit all data sheets to Emergency Planning Coordinator.

4.7.3 Have the FAT members report to a designated counting facility for a post-job whole body count, as appropriate.

SH/I/B/2005/002 Page 8 of 8

5. Enclosures 5.1 Field Monitoring Vehicle Designations 5.2 Telephone Numbers 5.3 Field Monitoring Survey Data Sheet 5.4 Meteorological Update for Field Monitoring Teams 5.5 Phonetic Alphabet 5.6 Field Monitoring Team Radiation Exposure Record 5.7 Guidance on Dose Limits for Workers Performing Emergency Services 5.8 I-13 1 Dose Calculation Methodology

Enclosure 5.1 SH/O/B/2005/002 Field Monitoring Vehicle Designations Page 1 of 1 Team Call Signs No. of Members Transportation Sample Van 1 2 Emergency Van Sample Van 2 2 Emergency Van Alpha 2 Station Vehicle Bravo 2 Station Vehicle Charlie 2 Land Vehicle Delta 2 Land Vehicle

  • IF teams from both sites are being used, the team's call sign shall be designated with the station name (e.g., McGuire Sample Van 1, Catawba Sample Van 2, etc.)
  • Form additional teams as necessary.

Enclosure 5.2 SWO/1/r2005/002 Telephone Numbers Page 1 of 1 Field Vehicle / Location Telephone Extension Catawba Sample Van 1 803-372-9021 Catawba Sample Van 2 803-372-9022 Catawba Alpha Station Vehicle 803-372-9023 Catawba Bravo Station Vehicle 803-372-9024 McGuire Sample Van 1 980-722-0595 McGuire Sample Van 2 980-722-0597 McGuire Alpha Station Vehicle 980-722-0599 McGuire Bravo Station Vehicle 980-722-0601 Catawba RP Support 8-831-5882 Catawba TSC Dose Assessment 8-831-5881 or 831-8042 FMC at EOF (General Office) 704-382-0735 or 704-382-0736 RP Support (Radio) Catawba TSC 803-831-8182 McGuire TSC Dose Assessment 8-875-4976 Dose Assessment Bridge Line 8-875-4980

  • Catawba Emergency Phone Numbers are found in the "CNS Emergency Phone Directory".
  • McGuire Emergency Phone Numbers are found in RP/0/A/5700/014, Emergency Telephone Directory.

Enclosure 5.3 Sa0O/B/2005/002 Field Monitoring Survey Data Sheet Page 1 of 1 I Air l I Instrument Readings mRemlhr Time Team Location CDE Special Open l Closed l Beta I Gamma Thyroid 4 1 + 4 4 4 4- I 4 I 4 4 4 4 4- I 4 I 4 4 4- 4- 9 4 I + 4 4 4 4 I 4 1 4- 4- 4 4- 4- I 4 I 4 4 4 4 4- I 4 I + 4 4 4 4- I 4 I 4- 4 4 4 1- I 4 I 4 4 4 4 4 I 4 I 4 4- 4 4 1- I 4 I 4 4 4 4 4 I

Enclosure 5.4 SH/0/B/2005/002 Meteorological Update for Field Page 1 of I Monitoring Teams Date: Time:

Classification:

Wind Speed: mph Wind Direction from: ° Zones Affected:

Information From Emergency Notification Form #_

Other:

Date: Time:

Classification:

Wind Speed: mph Wind Direction from: ° Zones Affected:

Information From Emergency Notification Form #

Other:

Date: Time:

Classification:

Wind Speed: mph Wind Direction from: 0 Zones Affected:

Information From Emergency Notification Form #_

Other:

Enclosure 5.5 SH/O/B/2005/002 Phonetic Alphabet Page I of I A - Alpha B - Bravo C - Charlie D - Delta E - Echo F - Foxtrot G - Golf H - Hotel I - India J - Juliett K - Kilo L - Lima M - Mike N - November o - Oscar P - Papa Q - Quebec R - Romeo S - Sierra T - Tango U - Uniform V - Victor W - Whiskey X - X-ray Y - Yankee Z- Zulu

( c Enclosure 5.6 SH0/3B/2005/002 Field Monitoring Team Radiation Exposure Record Page 1 of 1 TEAM NAME Sample Van 1 Sample Van 2 Alpha FMT Bravo FMT Other FMTs Individual's Name _ _

TLD #

Time _ _ _

Current Deep Dose Equivalent (SRD or ED Reading)

Time Subsequent Deep Dose Equivalent (SRD or ED Reading) _

Cumulative Deep Dose at T im e_ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Time __ _ _ _

Subsequent Deep Dose Equivalent (SRD or ED Reading)

Cumulative Deep Dose at Time l Total Deep Dose Equivalent For FMT Member (Total Deep Dose Equivalent) X (Committed Dose Equivalent SRD Correction Factor)a

= Total Effective Dose Equivalent .

a SRD Correction Factor is obtained from the Raddose Printout.

Enclosure 5.7 SH/O/B/2005/002 Guidance on Dose Limits for Workers Page 1 of 1 Performing Emergency Services Dose Limit a Activity Condition (rem) 5 all 10 protecting valuable lower dose not practicable property 25 life saving or lower dose not practicable protection of large populations

>25 life saving or only on a voluntary basis protection of large to persons fully aware of populations the risks involved (see Tables 2-3 and 2-4) a Sum of external effective dose equivalent and committed effective dose equivalent to nonpregnant adults from exposure and intake during an emergency situation. Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and body extremities) to ten times the listed value. These limits apply to all doses from an incident, except those received in unrestricted areas as members of the public.

Source: EPA 400-R-92-001

Enclosure 5.8 SH/O/B/2005/002 1131 Dose Calculation Methodology Page 1 of I

1. To calculate the CDE Thyroid dose rate from the field team results, use the following formula:

CDEThyroid(mremlhr) = giCi/ml

  • 1.3E9mrem/lhr jiCi I ml Where:

pCi/ml = I-131 concentration from field team air sample results 1.3E9 = Dose conversion factor, I-131 conc. (pCi/ml) to CDE Thyroid (mrem/hr) per EPA-400-R-922-001, Table 5-2

2. To calculate the expected I-131 concentration (gCi/ml) from a Raddose calculated CDE thyroid dose rate (mrem/hr), use the following formula:

1-131 gCi/ml =CDE Thyroid (mrem/hr) 1.3E9 rnrem/hr pCi / mnl Where:

CDE thyroid (mrem/hr) from the Raddose Report 1.3E9 = Dose conversion factor, I-131 conc. (pCi/ml) to CDE Thyroid (mrem/hr) per EPA-400-R-922-001, Table 5-2

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