ML030980032
| ML030980032 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/01/2003 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML030980032 (77) | |
Text
Duke Duke Power Mftwtwer.
McGuire Nuclear Station A
WE-W C12700 Hagers Ferry Road Huntersville, NC 28078-9340 (704) 875-4000 D. Al. Jarnil Vice President, McGuire (704) 875-5333 OFFICE Nuclear Generation Department (704) 875-4809 FAX April 1, 2003 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Re:
McGuire Nuclear Station Unit 1 Docket No.
50-369 McGuire Nuclear Station Unit 2 Docket No.
50-370 Changes to Emergency Plan Implementing Procedures Attached to this letter are revised Emergency Plan Implementing Procedures (EPIP) Index and a notice of revision to HP/0/B/1009/029, Initial Response On-Shift Dose Assessment, SH/0/B/2005/001, Emergency Response Offsite Dose Projections, and RP/0/A/5700/006, Natural Disasters.
These procedure revisions were evaluated pursuant to the requirements of 10 CFR 50.54 (q).
These 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 the changes to HP/0/B/1009/029 & SH/0/B/2005/001 on March 4, 2003, and changes to RP/0/A/5700/006 on 3/17/2003.
A copy of these changes are also being sent to the NRC Office of Nuclear Material Safety and Safeguards as per 10 CFR 72.44 (f).
The following procedure index change and procedure revision has been implemented:
EPIP Index Page 1 Dated 3/4/2003 EPIP Index Page 2 Dated 3/4/2003 EPIP Index Page 3 Dated 3/4/2003 SH/0/B/2005/001 Dated 3/4/2003 Rev. 002 HP/0/B/1009/029 Dated 3/4/2003 Rev. 007 RP/0/A/5700/006 Dated 3/17/2003 Rev. 010 There are no new regulatory commitments in these documents.
Duke is also supplying two copies of this submittal to the Regional Administrator of Region II.
Questions on this document should be directed to Kevin Murray at (704) 875-4672.
Very truly yours, D. M. Jamil Attachments A-ACY
U.S. Nuclear Regulatory Commission April 1, 2003 Page 2 xc:
(w/attachment)
Mr. Luis Reyes, Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 (w/attachment)
Mr. Martin J. Virgilio, Director Office of Nuclear Material Safety and Safeguards Mail Stop T-8A23 Washington, D.C. 20555-0001 (w/o attachment)
R. E. Martin, USNRC U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 NRC Resident Inspector McGuire Nuclear Station E.M. Kuhr (EC050)
M.T. Cash, Manager NRIA (ECO50)
Electronic Licensing Library (EC050)
EP File 111
DUKE POWER McGUIRE NUCLEAR SITE EMERGENCY PLAN IMPLEMENTING PROCEDURES APPROVED:
Lx's J /'o/2A by,r SAFETY ASSURANCE MANAGER DATE APPROVED EPIP Index Page EPIP Index Page EPIP Index Page 3-31-03 1
2 3
Dated Dated Dated 3/4/2003 3/4/2003 3/4/2003 SH/Q/B/2005/001 HP/0/B/1009/029 RP/0/A/5700/006 Dated Dated Dated 3 /4/2003 3 /4/2003 3/17/2003 Rev. 002 Rev. 007 Rev. 010
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE #
TITLE REVISION NUMBER RPIO/A/5700/000 RPIO/A/5700/00 1 RPIO/A/5700/002 RPIO/A/5700/003 RPIO/A/5700/004 RP101A/5700105 RPIO/A/57001006 RP/O/A/5700/007 RP/01A/5700/008 RPIO/A/5700/009 RP/O/A/5700/0 10 RP/O/A/5700/0 11 RPIO/A/5700/012 RP/O/A/5700/01 3 RP/O/A/5700/14 RP/O/A/570010 15 RPIO/A/5700!1 6 RPIO/A/5700/17 RPIO/A/5700/01 8 RPIO/A/5700/0 19 RP/O/A/5700/020 RPIO/A/5700/2 1 RP/O/A/57001022 RP/0/A/5700/024 RPIO/A/5700/026 RP/O/B/5700/023 OP/O/B/62001090 Classification of Emergency Notification of Unusual Event Alert Site Area Emergency General Emergency Care and Transportation of Contaminated Injured Individual(s) From Site to Offsite Medical Facility Natural Disasters Earthquake Release of Toxic or Flammable Gases Collisions/Explosions NRC Immediate Notification Requirements Conducting a Site Assembly, Site Evacuation or Containment Evacuation Activation of the Technical Support Center (TSC)
Activation of the Emergency Operations Facility (EOF)
Emergency Telephone Directory Notifications to the State and Counties from the EOF EOF Commodities and Facilities Procedure Emergency Data Transmittal System Access Notifications to the State and Counties from the TSC Core Damage Assessment Activation of the Operations Support Center (OSC)
EOF Access Control Spill Response Procedure Recovery and Reentry Procedure Operations/Engineering Technical Evaluations in the Technical Support Center (TSC)
Public Affairs Emergency Response Plan PALSS Operation for Accident Sampling Rev. 008 Rev. 017 Rev. 017 Rev. 017 Rev. 017 DELETE Rev. 010 Rev. 007 Rev. 004 Rev. 002 Rev. 013 Rev. 006 Rev. 021 DELETE DELETE DELETE DELETE DELETE Rev. 011 Rev. 004 Rev. 013 DELETE Rev. 009 Rev. 002 Rev. 002 Rev. 003 DELETED 1
March 4, 2003 Rev. 35
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE #
TITLE REVISION NUMBER HP/0/B/1009/002 HP/O/B/I1009/003 HP/IOB/I009/05 HPIOIB/ 1009/006 HP/01B/1009/010 Alternative Method for Determining Dose Rate Within the Reactor Building Recovery Plan Initial Evaluation of Protective Action Guides Due to Abnormal Plant Conditions Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions Releases of Radioactive Effluents Exceeding Selected Licensee Commitments Rev. 002 Rev. 004 DELETED Rev. 006 Rev. 006 HP/1/B/10091015 HP/213/1009/015 HP/0fB/1009/016 HP/0fB/1009/020 HPIOIB/1009/021 Unit I Nuclear Post-Accident Containment Air Sampling System Operating Procedure Unit 2 Nuclear Post-Accident Containment Air Sampling System Operating Procedure Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release Manual Procedure for Offsite Dose Projections Estimating Food Chain Doses Under Post-Accident Conditions DELETED DELETED Rev. 003 DELETED Rev. 001 HP/0B11/1009/022 HPIOB/1009/023 HP/0B/1009/024 HP/0/B/1009/029 SHJO/B/2005/001 SHI//B/2005/002 SR/IOB/2000/01 SR/0B/20001002 SR/O/B/2000/003 SR/0/B/2000/004 Accident and Emergency Response Environmental Monitoring for Emergency Conditions Personnel Monitoring for Emergency Conditions Initial Response On-Shift Dose Assessment Emergency Response Offsite Dose Projections Protocol for the Field Monitoring Coordinator During Emergency Conditions Standard Procedure for Public Affairs Response to the Emergency Operations Facility Standard Procedure for EOF Commodities and Facilities Activation of the Emergency Operations Facility Notification to States and Counties from the Emergency Operations Facility Rev. 003 Rev. 005 Rev. 002 Rev. 007 Rev. 002 Rev. 002 Rev. 003 Rev. 002 Rev. 009 Rev. 005 2
March 4, 2003 Rev. 35
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE #
TITLE REVISION NUMBER McGuire Site Directive 280 EP Group Manual MNS RP Manual:
PTIO/A14600/088 Site Assembly/Accountability and Evacuation/Containment Evacuation Section 1.1 Emergency Organization Section 18.1 Accident and Emergency Response Section 18.2 Environmental Monitoring for Emergency Conditions Section 18.3 Personnel Monitoring for Emergency Conditions Section 18.4 Planned Emergency Exposure Functional Check of Emergency Vehicle and Equipment DELETED Rev. 018 DELETED DELETED DELETED DELETED Rev. 007 3
March 4, 2003 Rev. 35
(RO4-01)
Duke Power Company PROCEDURE PROCESS RECORD FOR STANDARD PROCEDURES (1) ID No. SII/O/B/2005/001 Revision No.
002 PREPARATION (2)
Procedure
Title:
Emergency Response Offsite Dose Projections
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Prepared By-XY)AA1 Date I-%3?Gi7 Applicable To:
Advisor WA Requires 0 Yes 0 No ONo X Yes Applicability YES = New procedure or reissue with major changes Determination NO = Reissue with minor changes OR to incorporate previously approved changes Review (QR)
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NA Date NA _49Date t&/2 716' NA
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zo 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 enclosures attached?
O Yes
[ 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 addiional pages, if necessary)
Duke Power Company Catawba and McGuire Nuclear Stations Emergency Response Offsite Dose Projections Reference Use Procedure No.
SH/O/B/2005/001 Revision No.
002 Electronic Reference No.
MP007OPF
SH/OB/2005/001 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 TM Windows©D 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/IOBI1009/006 MNS -HP/O/B/1009/002 Alternative Method for Determining Dose Rate Within the Reactor Building Alternative Method for Determining Dose Rate Within the Reactor Building 2.3 Station specific procedure for abnormal unit vent sampling:
MNS - HP/01B/10091006 Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions 2.4 EPA 400-R-92-001 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.5 Letter from F.G. Hudson, September 20, 1985, Re: Release Rate Information for McGuire and Catawba Nuclear Stations (File: GS-750.25, NUC-0306) 2.6 Letter from H.B. Tucker, November 30, 1989, Re: Follow-up on McGuire Alert (March 7 - 8, 1989) Critique Action Items 2.7 U.S. Nuclear Regulatory Commission Response Technical Manual (RTM-93)
SH/iOB/2005l001 Page 3 of 16 2.8 Station specific procedures for classification of emergencies:
CNS - RP/O/AI5000/001 Classification of Emergency MNS - RPIO/A/5700/000 Classification of Emergency
- 3. Limits and Precautions 3.1 Use this procedure during abnormal or emergency conditions (including exercises and drills).
3.2 This procedure may be performed in sections or parts, using steps in any sequential order, to evaluate and/or assess offsite radiological conditions.
- 4. Procedure 4.1 Use Raddose 5 program to calculate Total Effective Dose Equivalent (TEDE) exposure, Committed Dose Equivalent (CDE) Thyroid exposure, and Effective Dose Equivalent (EDE) exposure in ten mile Emergency Planning Zone (EPZ).
- Provide information for offsite dose exposure and projected offsite dose rate results, from any radioactive material(s) released offsite, to ERO Management.
4.2 Access the Raddose 5 software.
4.2.1 Click on the Raddose 5 icon.
4.2.2 A dialog box should appear stating "Note: this workstation is configured as (EOF or TSC)". Click on "OK" to access the DAS (Dose Assessment Software) Desktop.
4.2.3 IF the dialog box above does NOT appear, change the DAS configuration as follows:
4.2.3.1 At the DAS Desktop, click on "FILE".
4.2.3.2 Click on "DAS Configuration".
4.2.3.3 Click on appropriate Work Station Type (EOF or TSC) and Mode (Production or Training).
4.2.3.4 Restart Raddose 5 for changes to take affect.
4.2.4 Select the appropriate Station and Unit from the DAS Desktop.
SH/lOB/2005/00 1 Page 4 of 16 NOTE:
This procedure is for "Normal Mode" operation of Raddose only. The "Automatic Mode" contains limited choices and default assumptions. The "Automatic Mode" is used for on-shift dose assessment only.
4.2.5 Select "Normal Mode" at the Dialog Box.
4.2.6 Select "Accident Mode" or "Drill Mode" as appropriate.
4.2.7 Select "PI Server" or "Manual" as appropriate.
- Select "PI Server" for program query of fifteen minute average data from Operator Aided Computer (OAC).
- Select "Manual" for keyboard entry of data.
4.2.8 IF this is the initial dose assessment calculation, select "Begin New Incident".
4.2.8.1 Enter information (e.g., reactor trip date, reactor trip time, release date and release time).
- IF the reactor did not trip, and shutdown is in progress, THEN use current time in the blank for reactor trip time.
CAUTION:
IF the automatic transfer of Raddose data into the Electronic Emergency Notification Form is going to be used, per the "Save Green Form Data To Ini File" Function, it is 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/0/13/2005/001 Page 5 of 16 4.2.9.2 Select "Network Data" to continue previous dose assessment calculation that was previously performed at another facility.
4.3 Select "Enter/Edit Meteorological Data" from program selection.
4.3.1 IF "Manual" was selected in Step 4.2.7, select "OK" to Raddose pop-up message: "No automatic meteorological data available. Enter data manually."
4.3.2 Input data for current meteorological conditions.
- Use actual site meteorology for assessment of a release until it is appropriate to use forecasted data provided by a meteorologist 4.3.3 IF site meteorology cannot be obtained from meteorological tower systems, refer to Enclosure 5.1 (Meteorology) for alternate methods for obtaining meteorological data.
4.3.4 Enter meteorological data, or "Requery" for automatic meteorological input.
4.3.4.1 IF manual meteorological data entries are required use Enclosure 5.1 (Meteorology) as necessary.
- Enter lower wind speed in miles per hour (mph).
- Enter upper wind direction; where wind direction is from North (N=O degrees).
- Enter Delta temperature gradient (AT) in degrees centigrade (AT = 0C).
- Enter air temperature in degrees centigrade (Temperature in 0C).
- Enter precipitation occurring (inches per fifteen minute period).
Mean mixing height (in meters) is computer selected from a table of seasonal afternoon mixing heights for each station.
Sa/O/B/2005o001 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.
SH/O/B/2005/001 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 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.3 (Containment Source Term Release) for NG Method selection.
SH/0/1/2005/001 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 Containment Monitor Reading Time After Shutdown (hours)
(EIMF 51 A/B or EMF 53 A/B) 0-2 864 R/Hr 2-4 624 RJHr 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/O/B/2005/001 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'I' 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/0/13/2005/001 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.
SHIO/B/2005/001 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/ OBo2005/001 Page 12 of 16 4.7.6 Select "OK" to the screen prompt "Note: Forecast will use the meteorological and source term data from Step 1. Continue?"
NOTE:
Forecast Mode doses are calculated using the most current time step and are displayed on ten mile EPZ map.
4.7.7 IF General Emergency was selected in Step 4.5, THEN select "Both PARs" to display the General Emergency Protective Action Recommendations, and the Dose Protective Action Recommendations.
4.7.8 Select "Continue" from map display to go to the Forecast Mode Output Menu.
4.7.9 At the popup dialog box item "Do you want to save PAZs identified in forecast mode for evacuation?", select "Yes".
4.7.10 Select "Go To Report Menu" to go to the Forecast Mode Report Options Menu and access the Raddose 5 Green Form.
NOTE:
Refer to Step 4.6.2.2 for a description of the other choices on this menu. However, it should be noted that all outputs will consist of forecasted data instead of real-time data.
4.7.11 Select "Print Green Form + Summary Form" to print the Emergency Notification Form (green sheet) and the Summary Report.
4.7.12 Select "Save Green Form Data to Ini File" to transfer the Raddose data to the Electronic Notification Form application.
4.7.13 Other menu items may be selected as follows:
- "View Green Form" is used to display the Green Form report.
- "View Reports" is used to view all reports.
- "Print Green Form" is used to print the Green Form report.
- "Print Summary Form" is used to print the Summary Form report.
- "Print Reports and Maps" is used to select any combination of the available reports.
4.7.14 Select "Return to Output Menu" when done with Forecast Mode reports.
4.7.15 Select "Continue Calculations" to return to the main menu in real-time mode.
SH/O/B/2005/001 Page 13 of 16 4.7.16 Select "OK" to the Raddose prompt: "You have just completed a forecast.
Remember to check the meteorological and source term data for current information".
4.8 Refer to Enclosure 5.5 (Radiological Emergency Action Levels) and evaluate the Emergency Action Levels (EALs) based on radiological conditions.
4.8.1 Provide EAL radiological assessment classifications to ERO Management in the TSC and/or EOF.
4.9 IF desired, obtain the Self Reading Dosimeter Correction Factor (SRDCF) from the Real-Time Summary Report.
NOTE:
Raddose 5 calculates Effective Dose Equivalent (EDE) exposure and provides Self Reading Dosimeter (SRD) correction factor (SRDcF).
=
TEDE EDE SRDCF
=
=
Total Effective Dose Equivalent EDE
=
Effective Dose Equivalent NOTE:
The SRDCF value is based on accident specific source term nuclide(s) and is a calculation of TEDE to EDE ratio at site boundary.
- SRDCF is provided to offsite Emergency Workers during an accident, after a declared General Emergency, and when a release is occurring.
- SRDcF is used as a multiplier of Emergency Worker SRD readings for EPA 400 Manual Of Protective Action Guides And Protective Actions For Nuclear Incidents, "Early Phase" Emergency Worker TEDE estimate.
- Provide the SRDCF the Field Monitoring Coordinator and the OSC.
4.10 IF manual completion of the Emergency Notification Form is to be used, provide the Radiological Assessment Manager (RAM), Lead TSC Dose Assessor and/or ERO personnel the following information for each of the Emergency Notification Form line items:
SHI/OB/2005/001 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
- Particulates
SH/O/BJ2005/001 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.
E 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= Odegrees 4.10.6.2 Wind Speed (miles per hour) 4.10.6.3 Stability Class 4.10.6.4 Precipitation (type) (in/l5min) 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.
SH/O/B/2005/001 Page 16 of 16
- 5. Enclosure 5.1 Meteorology 5.2 Steam Source Term Release 5.3 Containment Source Terrn Release 5.4 Unit Vent Source Term Release 5.5 Radiological Emergency Action Levels 5.6 Raddose 5 Green Form Report
.1 SFI/0B/2005o001 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) = O0 5.1.2 IF Meteorological Tower is not available, obtain meteorological information from:
- Duke meteorologist at 594-0341/0289
- Unaffected plants control room:
CNS - Unit-I 8-831-5345 Unit-2 8-831-5344 MNS - Unit-I 8-8754262 Unit-2 8-875-4263
- National Weather Service (NWS) at 1-800-268-7785
- Gastonia Automated Surface Observation System (ASOS) at 704-868-9034 5.1.3 IF meteorological tower temperature gradient (AT0) is unknown, use the following default values:
.1 Meteorology SH/O/B/2005/001 Page 2 of 2 5.1.4 Use the following tables to determine stability class when AT data is available:
CNS (AT in 0C)
MNS (AT in 0C)
Stability Class i
I A - Extremely Unstable B - Moderately Unstable C - Slightly Unstable D - Neutral E - Slightly Stable F - Moderately Stable G - Extremely Stable AT < -0.97
-0.97 < AT < -0.87
-0.87 < AT < -0.76
-0.76 < AT < -0.25
-0.25 < AT < +0.76
+0.76 < AT < +2.04
+2.04 < AT AT < -0.95
-0.95 < AT < -0.86
-0.85 < AT < -0.76
-0.75 < AT < -0.26
-0.25 < AT < +0.74
+0.75 < AT < +2.00
+2.00 < AT
___.1
__I
.2 SH0/1B/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 EMP 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).
- IF field team data is available, select BACKSL.
(a)
Enter the field team data.
(b)
Click on "OK" for Raddose to calculate the source term in Ci/sec.
.2 Steam Source Term Release SH/O/B/2005/001 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:
=
EMP x CF x AJ x LR x (0.41ft3/lbm x 28320 ml/ft3 x 1E-6 Ci/ILCi x 1/3600/hr/s)
Where:
= release rate activity in Ci/sec CF
= steam line radiation monitor Correlation Factor EMF
= radiation monitor reading in mR/hr (normally a 15 minute average reading)
AJ
= Adjustment Factor (unit-less) based on accident types (SGTR, SGTRG, SGTRM)
LR
= Steam release rate from safety valve in pounds mass of steam released through each valve during valve open period (Ibm/15 min), where; default release rate = 5.235E4 Ibm/15 min NOTE:
Raddose 5 calculates steam source term for the GRABSL method as follows:
=
SLK x LR x (0.41ft3/lbm x 28320 ml/ft3 x 1E-6 Ci/[Ci x 1/3600/hr/s Where:
=
release rate activity in Ci/sec SLg
=
secondary grab sample (gCi/mnI)
LR
=
steam release rate from safety valves pounds mass of steam released through the respective valves during the valve open period (Ibm/hr) default release rate = 5.235E4 Ibm/15 min
.2 SH/0/1/2005/001 Steam Source Term Release Page 3 of 4 NOTE:
Raddose calculates the steam source term for the BACKSL method as follows:
=
Field Measurement Device Reading (mR/hr) x FM Device Correlation (jiCilcc)/(mRlhr)IXIQ(seclm3) (1E-6 Ci/ItCi x 1E+6 cc/m3=1) 5.2.4 For Catawba only, use Step 5.2.5 source term assessment worksheet steam generator tube rupture coincident with loss of offsite power; when appropriate and due to the following:
- Loss of offsite power and steamline radiation monitor is unavailable
- Primary to secondary coolant leakage is occurring
- Steam source term release is occurring
- Steam generator sample cannot be obtained
- Computer program for calculating steam release is not available
.2 SH/0/B/2005/001 Page 4 of 4 Steam Source Term Release 5.2.5 (Catawba Only) Source term assessment worksheet with steam generator tube rupture coincident with loss of offsite power for unavailable Steam Line Monitor EMF Unit Dose Projection based on:
I I
Time since trip:
hours mm dd yy hh mm EMF53 reading* Correction Factor** LRps dT Lbsmr***
1VOPEN R/hrx pCi/ml x gal x _
min x lbmr x
1 x
R/hr min 2400 Ibm sec.
- Note: If EMF53<5 R/hr, use 5 R/hr.
x 3.785E-3 Ci ml x =
pCi gal Activity noble Gas Ci sec Activity noble Gas x
Iodine Ratio LOCA Activity LOCA Iodine 131 Equivalent
=
Ci/sec Activity noble Gas x
Iodine Ratio core melt Activity Lcore Melt Iodine 131 Equivalent Ci/sec Where:
=
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 mllgal 2400
=
Mass of steam in the faulted steam generator; conservative valve is 2400 Ibm (mass of steam from S/G nozzle to MSIV)*** If Lbsmr > 2400 Ibm; use 2400 Ibm.
Time since Rx Trip EMF 53 Correction Factor Iodine Ratio LOCA Iodine Ratio Core Melt (hours)
- (CF)
Ž 0 7.74 E+3 1.52 E-3 4.23 E-3
Ž 2 9.82 E+3 1.95 E-3 1.46 E-3
Ž 4 9.96 E+3 2.24 E-3 2.21 E-2
Ž 8 1.28 E+4 2.63 E-3 4-09 E-2
Ž 24 2.15 E+4 3.00 E-3 1.14 E-1
Ž 48 3.69 E+4 3.05 E-3 1.78 E-1 Emergency FJ or Drill C1 Prepared by:
.3 SIO3/B/2005o001 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:
E 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 EMIF 39(L) < 1E7 counts per minute (cpm), select "CONL".
(b) IF EMF 39(L) > 1E7 cpm AND EMF 39(H) < 1E6 cpm, select "CONH".
(c)
IF EMF 39(H) > 1E6 cpm, select "CONHH".
- IF containment sample line is isolated OR containment sample pump is tripped, use the following guidance for Noble Gas Method selection:
(a) IF containment sample results are available, select "GRABC".
(b) IF containment sample results are NOT available, select "CONHH".
5.3.4 IF CONL, OR CONH, OR CONHH was selected in Step 5.3.3, Raddose displays the Containment Bypass Release Pathway screen. Choose the appropriate selections for:
(a)
Ice Condenser: "No Recirculation", Recirculation", or "No Ice" (b)
Hold-Up: "<=24 Hours" or ">24 Hours" (c)
Spray Status: "On" or "Off" (d)
Containment Leak Rate Method: "Containment Pressure and Hole Size" or "Predefined/User Leak Rate" (e)
Enter or verify the Containment Pressure (g)
When all inputs on the Containment Bypass Release Pathway screen are correct, click on "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.
.3 Containment Source Term Release SHIO/B/20050oo1 Page 2 of 3 NOTE:
Raddose 5 calculates the containment source term for the CONL, CONH, AND CONHH methods as follows:
=
EMF x CF x AJ x BY x Ci4ICi x 1/3600 hr/sec Where:
=
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 EMF51AIB - MNS R/hr reading whenever EMF39(H) is
>LE+6 cpm (offscale) orEMiF39 sample line is isolated, or EMF containment sample pump is tripped (CONHH Method)
=
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)
.3 SHWO/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:
=
EMT x CF x AJ x BY x Ci/[Ci x 1/3600 hr/sec Where:
CONg =
Containment grab sample (gCi/ml)
All other parameters are the same as defined in the NOTE above.
.4 SWO/IB/2005/001 Unit Vent Source Term Release Page 1 of 4 5.4.1 Determine type of accident, source term release pathway, and EMF monitor method.
5.4.2 Enter an accident type for affected release pathway.
- "LOCA" - Loss of Coolant Accident (normal coolant)
- "LOCAG" - Loss of Coolant Accident gap release
- "LOCAM" - Loss of Coolant Accident core melt
- "LOCO" - LOCA outside of containment (normal coolant)
- "LOCOG" - LOCA outside of containment gap release
- "LOCOM" - LOCA outside of containment core melt
- "SGTR" - Steam Generator Tube Rupture (normal coolant) with Condensate Stem Air Ejector(CSAE) pathway to unit vent
- "SGTRG" - Steam Generator Tube Rupture gap release Condensate Steam Air Ejector (CSAE) pathway to unit vent
- "SGTRM" - Steam Generator Tube Rupture core melt Condensate Steam Air Ejector (CSAE) pathway to unit vent "FUEL" - Fuel handling gas release 5.4.3 Select the appropriate unit vent EMF Noble Gas Method as follows:
- IF Unit Vent EMF Data is available, AND unit vent sample pump is NOT tripped, use the following guidance for Noble Gas Method selection:
(a)
IF EMF 36(L) < 1E7 counts per minute (cpm), select "UVIL" or "UV2L" as appropriate.
(b) IF EMF 36(L) > 1E7 cpm AND EMF 36(H) < 1E6 cpm, select "UVlH" or "UV2H" as appropriate.
(c)
IF EMF 36(H) > 1E6 cpm, select "UVIHH" or "UV2HH" as appropriate.
.4 SH/013/2005/001 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 "GRABV1" or "GRABV2" as appropriate.
(i)
Enter the grab sample data.
(ii)
Click on "OK" for Raddose to calculate the source term in Ci/sec.
(b)
IF Field Team Data is available, select "UVI-BACK" or UV2-BACK" as appropriate.
(i)
Enter the field team data.
(ii)
Click on "OK" for Raddose to calculate the source term in Ci/sec.
(c)
IF Total Source Term calculations are available, select "DRCT1" or DRCT2" as appropriate.
(i) Enter the Noble Gas, Iodine, and Particulate source term data.
(ii) Click on "OK" for Raddose to calculate the source term in Ci/sec.
- Check unaffected unit vent monitor data.
- IF appropriate, repeat Step 5.4.3 to include source term assessment for unaffected unit.
.4 SI/O/B/2005/001 Unit Vent Source Term Release Page 3 of 4 NOTE:
Raddose 5 calculates the unit vent source term for the UVIL, UV1H, 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:
=
EMF x CF x AJ x FR x 1E-6 Ci/ttCi x 1/60 min/sec x 28320 ml/ft3 Where:
=
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 - CNS, EMF36HH - MNS (R/hr) reading if EMF36L and EMF36H are offscale, and/or vent EMF sample pump is tripped (UVIHH, UV2HH)
=
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
.4 Unit Vent Source Term Release SO/J/B/2005/001 Page 4 of 4 NOTE:
Raddose 5 calculates the unit vent source term for the GRABVI and GRABV2 methods as follows:
=
UVg x FR x 1E-6 Ci/ftCi x 1/60 min/sec x 28320 ml/ft3 Where:
=
release rate activity in Ci/sec UVg
=
unit vent grab sample (fLCi/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:
= Field Measurement Device Reading (mR/hr) x FM Device Correlation (giCi/cc)/(mR/hr)/X/Q(sec/m 3) x (1E-6 Ci/ItCi x 1E+6 cc/m3=1)
.5 Radiological Emergency Action Levels SVO/B/2005/001 Page 1 of 1 5.5.1 Evaluate the Emergency Action Levels (EALs) based on radiological conditions in the affected site's EAL procedure:
CNS - RP/O/A/5000/001 Classification of Emergency MNS - RP/O/A/5700/000 Classification of Emergency
.6 S].
Raddose 5 Green Form Report PR Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech Current Date: 12109/2002 Stl Current Time: 14:41 Stz Operator: GTJ St H1O/B/2005/001 age 1 of 2 ep #: 1 ep Date: 12/09/2002 epTime: 12:15
- FORECAST FOR 4 HOURS ***
ACCIDENT DESCRIPTION:
General Emergency has NOT been declared Reactor Shutdown:12/09/2002 1200 hrs Accident Time: 12/09/2002 1200 hrs PATHWAY 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 COis Above Normal Operating Limits Iodine Release Rate (Ci/sec):
4.61 E-02 Ci/s Particulate Release Rate (Cisec):
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 1.71 E+02 2.74E1+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 00E+00 9.41 E+01 9.41 E+01 10.00 0.OOE+00 4.79E+00 4.79E+00 0.00E+00 2.81 E+01 2.81 E+01 METEOROLOGICAL DATA Wind Speed:
9.5 mph (P)
Stability Class:
D (P)
Wind Direction:
From 44.90 deg To 224.90 deg RECOMMENDED PROTECTIVE ACTIONS:
Evacuate:
Shelter:
.6 Raddose 5 Green Form Report SwO/fB/2005/001 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 Current Time: 14:41 Operator: GTJ Step #: 1 Step Date: 12/09/2002 Step Time: 12:15
- FORECAST FOR 4 HOURS TOTAL (Forecast + Integrated) DOSES FROM 12/0912002 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 2.84E+02 2.91 E+03 3.55E-05 1.00 3.08E+01 2.59E+02 1.31EE+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 479E+00 2.81E+01 4.16E-07 DOSE CONVERSION FACTORS:
mrem rmA3/Ci*hr TEDE:
2.1 5E+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 mrem No < 5000 mrem PAG Dose Umits:
1 rem 5 rem PAG Exceeded at Site Boundary?
No No PAG Distances (miles):
N/A N/A-MONITOR CORRECTION FACTORS:
Time Since Trip (Hrs)
Ice Condenser Sprays Hold-Up Time Cont Leak Rate Method Cont Leak Type Cont Pressure Cont Leak Rate Cont Bypass Fraction Filters SG Partitioned Pool Scrubbing Field Measurement Distance Direction Fuel Assembly Age (Days)
Pathway 1 0.00 No Recirc On
<-24 hrs No
(R04-01)
Duke Power Company PROCEDURE PROCESS RECORD (1) ID No. HP/I/B/1009/029 Revision No.
007 K
PREPARATION (2) Station McGuire Nuclear Station (3) Procedure Title Initial Response On-Shift Dose Assessment (4) Prepared By Gary Terrell A4,
G ag Date February 24,2003 (5) Requires NSD 228 Applicability Determination? If Applicability Determination is required, attach NSD 228 documentation.
0 Yes (New procedure or revision with major changes) 5 No (Revision with minor changes)
Cl No (To incorpo Ate previously approved hanges)
(6) Reviewed By -
4 12 A
(OR)
Date i -,24-'/'3 Cross-Disciplinary Review By (QR) N AG Date RYO3 Reactivity Mgmt. Review By (QR) NA..StL Date a-2+-03 Mgmt. Involvement Review By (OPS Supt.) NA &
Date O?22 -0 3 (7) Additional Reviews y Reviewed By A
Date /
Reviewed By
/I'd2<
Date 3 Ye (8) Temporary Approval (if necessary By (OSM/QR) Date_
By (OR)
Date (9) Approved By Date 3-o 'A- 0 3 PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification El Yes El NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
El Yes El NA Required enclosures attached?
a Yes Dl NA Data sheets attached, completed, dated and signed?
D Yes El NA Charts, graphs, etc. attached, dated, identified, and marked?
5 Yes [ NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additional pages, if necessary.)
Fonn based on NSD 703 App D (Procedure Process Record)
Duke Power Company McGuire Nuclear Station Initial Response On-Shift Dose Assessment Multiple Use Procedure No.
HP/i/B/1009/029 Revision No.
007 Electronic Reference No.
MC0095KW
HP/B/JI 1009/029 Page 2 of 3 Revision History (significant issues, limited to one page)
Rev 007 (02/05/03) Entire procedure revised to incorporate Rev. 3.0 of Raddose V, including Auto Mode. Rewritten to Procedure Writer's Guide formnat.
Rev 006 (04/03102) For documentation. This revision allows procedure to be accessed via NEDL.
HP/01B/1009/029 Page 3 of 3 Initial Response On-Shift Dose Assessment Information Use
- 1. Purpose The purpose of this procedure is to provide a method for on-shift Radiation Protection personnel to determine offsite dose to the public and to provide information to complete the Emergency Notification form, using Raddose V.
- 2. References 2.1 Earth Tech, Raddose-V Operator's Manual.
- 3. Limits and Precautions None
- 4. Procedure NOTE:
This procedure will only be performed upon declaration of an emergency classification and at the discretion of Operations Shift Manager (OSM)IEmergency Coordinator (EC).
4.1 WHEN directed by the OSM/EC perform on-shift dose assessment using Enclosure 5.1.
4.2 WHEN the Technical Support Center (TSC) is staffed by TSC Dose Assessors, provide following turnover information to TSC Dose Assessors:
4.2.1 Copies of Raddose V printouts.
4.2.2 Copies of completed Enclosure 5.3.
- 5. Enclosures 5.1 On-Shift Dose Assessment Using Automatic Mode in Raddose V 5.2 On-Shift Dose Assessment Using Normal Mode in Raddose V 5.3 Completing Radiological Portion of Emergency Notification Form 5.4 Manual Data Collection Sheet 5.5 Operation of the TSC Laptop Computer
.1 HP/0/lE 1009/029 Page 1 of 4 On-Shift Dose Assessment Using Automatic Mode in Raddose V Reference Use Compared with Control Copy by (print)
Initials DatpeTime l
And_.
Performer (print name)
Initials l Performer (print name)
Initials
- 1. Purpose This enclosure specifies the method to be used by Radiation Protection personnel to perform off-site dose assessment when Automatic Version of Raddose V is available.
- 2. Limits and Precautions None
- 3. Initial Conditions 3.1 An Emergency Classification has been declared by Operations Shift Manager (OSM)/Emergency Coordinator (EC).
3.2 The OSM/EC has directed RP to conduct off-site dose assessment.
- 4. Procedure a 4.1 Obtain following data from OSM or appropriate Control Room personnel:
Unit Affected (Circle One)
Unit 1 Unit 2 Reactor Trip Date/Time:
/
Release Started Date/Time:
/
Accident Type (Circle One)
LOCA SG Tube Rupture Emergency Classification (Circle One)
Unusual Event Site Area Emergency Alert General Emergency Next Followup Emergency Notification Due Date/Time:
I Obtained From:
OSM or Designee (Name)
Data Collected By:
Name:
Date/Time:
I
.1 HP/0/B/1009/029 On-Shift Dose Assessment Using Automatic Page 2 of 4 Mode in Raddose V NOTE:
Raddose V is available on designated shift lab computers, Technical Support Center Dose Assessor Computer, and on the TSC Dose Assessor laptop computer. Enclosure 5.5 provides specific instruction for the use of the laptop computer.
a 4.2 On the Raddose computer, select "DAS/Raddose-V" icon.
Li 4.2.1 WHEN dialog box appears stating "DAS Workstation configuration" (EOF or TSC).
Select "OK" to access the DAS (Dose Assessment Software) Desktop.
4.2.2 IF work station was NOT configured as TSC:
4.2.2.1 At DAS desktop, click on "FILE".
4.2.2.2 Select "DAS Configuration".
4.2.2.3 Select "TSC" for Work Station type 4.2.2.4 Select "Production" for Mode 4.2.2.5 Restart Raddose V per Step 4.2.
4.2.3 IF work station was configured as TSC, select appropriate Station and Unit from DAS Desktop.
L 4.3 At Dialog Box select "Automatic Mode".
11 4.3.1 Select "Accident Mode".
4.4 At the Accident Scenario definition screen:
4.4.1 Edit the following data:
[1 4.4.1.1 Date and time of reactor trip. IF reactor trip has NOT occurred OR trip time is unknown, no editing of time is required.
Li 4.4.1.2 Date and time of start of release. IF actual release time is unknown, input a time 15 minutes previous to current time. Example: current time is 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />.
The correct input would be 0745.
L 4.4.2 Enter operator's initials.
Cl 4.4.3 Select "Accept".
4.5 At dialog box:
4.5.1 IF primary release path is unit vent, select LOCA.
OR 4.5.2 IF steam release is occurring, select SG Tube Rupture.
.1 HP/O/B/1009/029 On-Shift Dose Assessment Using Automatic Page 3 of 4 Mode in Raddose V E 4.6 At Main Menu select "Enter/Edit Meteorological Data".
4.6.1 IF data is NOT automatically loaded, select "Cancel".
4.6.1.1 At main menu, select "Go to Start-Up Menu".
4.6.1.2 At Start-Up menu, select "Exit Raddose V".
4.6.1.3 Use Enclosure 5.2 for alternate method of dose assessment.
4.6.2 IF meteorological data is automatically loaded from OAC, note precipitation.
E 4.6.3 Select "Accept".
E 4.7 At Main Menu select "Enter/Edit Source Term Data".
4.7.1 IF data is NOT automatically loaded, select "Cancel".
4.7.1.1 At main menu, select "Go to Start-Up Menu".
4.7.1.2 At Start-Up menu, select "Exit Raddose V".
4.7.1.3 Use Enclosure 5.2 for alternate method of dose assessment.
4.7.2 IF source term data is automatically loaded from OAC, click on "Accept".
E 4.8 At Main Menu select "Emergency Classification".
E 4.9 Select Emergency Classification recorded in Step 4.1.
E 4.10 Select "continue".
4.11 IF General Emergency was selected in Step 4.9, a dialog box appears stating "Is the Fission Product Inventory inside containment greater than gap activity?" Select "NO".
E 4.12 At Main Menu select "Start Auto Mode w/Auto Reports".
E 4.13 WHEN dialog box asks "Are you sure you want to use Automatic Print mode?" select "yes".
NOTE:
Raddose-V: Automatic Mode Status Screen will appear and display status of automatic dose projections.
4.14 Use Raddose V printouts to complete Enclosure 5.3.
4.14.1 IF the next Emergency Notification Due recorded in Step 4.1 is less than 20 minutes from current time, OR if requested by OSM, complete Enclosure 5.3.
E 4.14.2 Retain copy of Enclosure 5.3 for turnover to TSC Dose Assessors.
.1 HP/O/B/1009/029 On-Shift Dose Assessment Using Automatic Page 4 of 4 Mode in Raddose V 0 4.14.3 Provide completed Table I of Enclosure 5.3 to OSM.
0 4.15 WHEN further on-shift dose projections are NOT needed, select "Quit Automatic Mode".
0 4.16 WHEN dialogue box asks "Are you sure you want to exit Automatic Operating Mode?" select yes 0 4.17 Select "Go To Start-up Menu".
0 4.18 Select "Exit Raddose-V".
.2 HP/0/B/1009/029 On-Shift Dose Assessment Using Normal Page 1 of 10 Mode In Raddose V Reference Use Compared with Control Copy by (print) _
Initials Date/Time
/
Performer (print name)
Initials Performer (print name)
Initials
- 1. Purpose This enclosure specifies the method to be used by Radiation Protection personnel to perform off-site dose assessment when the Automatic Version of Raddose V is NOT available.
- 2. Limits and Precautions None
- 3. Initial Conditions 3.1 An Emergency Classification has been declared by Operations Shift Manager (OSM)IEmergency Coordinator (EC).
3.2 OSM/EC has directed RP to conduct off-site dose assessment.
3.3 The Automatic Version of Raddose V is NOT available for use.
- 4. Procedure 4.1 Obtain plant status:
[l 4.1.1 Obtain following data from Step 4.1 of Enclosure 5.1:
Unit Affected (Circle One)
Unit 1 Unit 2 Reactor Trip Date/Time:
/
Release Started Date/Time:
/
Accident Type (Circle One)
LOCA SG Tube Rupture Emergency Classification (Circle One)
Unusual Event Site Area Emergency Alert General Emergency Next Followup Emergency Notification Due Date/Time:
I
.2 HP/0/B/ 1009/029 Page 2 of 10 On-Shift Dose Assessment Using Normal Mode In Raddose V 0 4.1.2 Obtain the following data from OSM or appropriate control room personnel:
For Leak in Aux Bldg VA Filters Status (Circle One)
ON/OFF For Leak in Containment VE Filters Status (Circle One)
ON/OFF Phase B Containment Isolation (Circle One)
YES/NO SG Tube Leak/Rupture (Circle One) A B C D NA Partitioned/Not Partitioned/NA (Circle One)
Steam Release in Progress (Circle One) YES/NO Release Duration if Known hrs; Obtained From:
OSM or Designee (Name)
Data Collected By:
Date/Time:
Name 4.2 On Data Acquisition computer:
E 4.2.1 Select McGuire Desktop icon.
E 4.2.2 Select McGuire Process Data.
E 4.2.3 Select SDS.
K-;
4.2.4 IF Unit I is affected unit, select Unit 1.
4.2.5 IF Unit 2 is affected unit, select Unit 2.
E 4.2.6 Type GD ERORD5.
E 4.2.7 Press "Enter".
4.2.8 IF Data Acquisition Computer will be used to run Raddose V, minimize SDS Screen.
.2 HP101B/1009/029 On-Shift Dose Assessment Using Normal Page 3 of 10 Mode In Raddose V NOTE:
Raddose V is available on designated shift lab computers, Technical Support Center dose Assessor Computer, and on the TSC Dose Assessor laptop computer. Enclosure 5.5 provides specific instruction for the use of laptop computer.
0 4.3 On Raddose computer, select "DAS/Raddose V" icon.
E 4.3.1 WHEN dialog box appears stating, "DAS Workstation configuration" (EOF or TSC).
Click on "OK" to access DAS (Dose Assessment Software) Desktop.
4.3.2 IF work station was NOT configured as TSC:
4.3.2.1 At DAS desktop, select "FILE".
4.3.2.2 Select "DAS Configuration".
4.3.2.3 Select "TSC" for Work Station type 4.3.2.4 Select "Production" for Mode 4.3.2.5 Restart Raddose V per Step 4.3.
4.3.3 IF work station was configured as TSC, select appropriate Station and Unit from the DAS Desktop.
El 4.4 At Dialog Box, select "Normal Mode".
E 4.5 Select "Accident Mode".
E 4.6 At prompt, "Do you want to use automatic data from the PI Server or manual entry?", select "PI Server".
4.7 At Start-up Menu:
El 4.7.1 Select "Begin New Incident".
E 4.7.2 WHEN pop-up message displays "This erases all previous data. Click Yes to continue or No to abort" select "Yes".
4.8 At Accident Scenario Definition screen edit the following data:
E 4.8.1 Date and time of reactor trip. IF reactor trip has NOT occurred OR trip time is unknown, no editing of time is required.
11 4.8.2 Date and time of start of release. IF actual release time unknown, input time 15 minutes previous to current time. Example: current time is 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />. The correct input would be 0745.
E 4.9 Enter operator's initials.
.2 HP/0/B/1009/029 On-Shift Dose Assessment Using Normal Page 4 of 10 Mode In Raddose V El 4.10 Select "Accept".
O 4.11 At Main Menu Screen, select "EnterlEdit Meteorological Data".
NOTE:
With "PI Server" selected in Step 4.6 data will be automatically populated from SDS.
4.11.1 IF data fields are NOT populated, Raddose V displays following pop-up message:
"No automatic meteorological data available. Enter data manually". Select "OK".
El 4.11.1.1 Go to Enclosure 5.4.
El 4.11.1.2 Manually enter the following data from Table 1 of Enclosure 5.4.
- Lower wind speed in mph. Select "Enter".
- Upper wind direction in degrees. Select "Enter".
- Delta Temperature in degrees C. Select "Enter".
- Air Temperature in degrees C. Select "Enter".
- Precipitation during last 15 mins in inches. Select "Enter".
E 4.11.2 WHEN all fields are populated, select "Accept".
El 4.12 At Main Menu Screen, select "Enter/Edit Source Term Data".
E 4.12.1 At Source Term Data Input screen double select "Accident Type" data field.
E 4.12.2 WHEN "Accident Type" menu is displayed, double select Accident Type recorded in Step 4.1.
E 4.12.3 Double select highlighted area in "NG Method" data field.
4.12.4 IF LOCA was selected in Step 4.12.2, select NG Method from Noble Gas Method Menu as follows:
El 4.12.4.1 Select unit vent EMF pathway:
- IF EMF36L is on-scale, select UVIL or UV2L
- IF EMF36L is off-scale AND EMF36H is on scale, select U`1H or UV2l-l.
- IF EMF36L AND EMF36H are off-scale, select UVi HH or UV2HH.
.2 HP/0/B1/1009/029 On-Shift Dose Assessment Using Normal Page 5 of 10 Mode In Raddose V E 4.12.4.2 WHEN Unit Vent Pathway Data screen appears, select the following:
A. "Filter Status ON/OFF". Select Filter status recorded in Step 4.1.
B.
"Ice Condenser". Select "Recirculation".
C. "Hold-up time". Select "<=24 hours".
D. "Sprays Status".
- 1.
IF containment pressure is >3 psig (Enclosure 5.4, Table 2),
select "On".
- 2.
IF phase B containment isolation has occurred (Step 4.1.2),
select "On".
E 4.12.4.3 Select "OK".
NOTE:
With "PI Server" selected in Step 4.6 data will be automatically populated from SDS.
4.12.5 IF data fields are NOT populated, Raddose V displays following pop-up message:
"No automatic source term data available. Enter data manually". Select "OK".
E 4.12.5.1 Go to Enclosure 5.4, Table 2.
E 4.12.5.2 Manually enter following data from Table 2 of Enclosure 5.4:
- Monitor reading for EMF selected in Step 4.12.4 A. Select "Enter".
- Unit Vent flow rate. Select "Enter".
41
_4.13 4.12.6 WHEN all fields are populated, select "Accept".
4.12.7 Go to Step 4.14.
IF SGTR was selected in Step 4.12.2, select NG Method from Noble Gas Method Menu as follows:
4.13.1 Select Steam Line Monitor for affected SG determined in Step 4.1.
4.13.2 WHEN Steam Line Release Pathway Data screen appears, select partitioned or n El El ot partitioned as determined in Step 4.1.
O 4.13.3 Select "OK".
.2 HP/0/B/l 009/029 Page 6 of 10 On-Shift Dose Assessment Using Normal Mode In Raddose V I NOTE:
With "PI Server" selected in Step 4.6 data will be automatically populated from SDS.l 4.13.4 IF data fields are NOT populated, Raddose V displays following pop-up message:
"No automatic source term data available. Enter data manually." Select "OK".
l 4.13.4.1 E 4.13.4.2 Go to Enclosure 5.4, Table 2.
Manually enter following data from Table 2 of Enclosure 5.4:
- Monitor reading for EMF selected in Step 4.13.1. Select "Enter".
- Flow rate. IF the flow rate is unknown, input the default value of 5.235E4 pounds steam per 15 minutes. Select "Enter".
El 4.13.5 Select unit vent EMF pathway:
- IF EMF36L is on-scale, select UVIL or UV2L
- IF EMF36L is off-scale AND EMF36H is on scale, select UVIH or UV2H.
- IF EMF36L AND EMF36H are off-scale, select VI1HH or UV2HH.
a 4.13.6
'WHEN the Steam Line Release Pathway Data screen appears, select partitioned or not partitioned as determined in Step 4.1.
a 4.13.7 Select "OK".
NOTE:
With "PI Server" selected in Step 4.6 data will be automatically populated from SDS.
4.13.8 IF data fields are NOT populated, Raddose V displays following pop-up message:
"No automatic source term data available. Enter data manually". Select "OK".
El 4.13.8.1 E1 4.13.8.2 Go to Enclosure 5.4, Table 2.
Manually enter following data from Table 2 of Enclosure 5.4:
- Monitor reading for EMF selected in Step 4.13.5. Select "Enter".
- Flow rate. IF the flow rate is unknown, Input the default value of 5.235E4 pounds steam per 15 minutes. Select "Enter".
D 4.13.9 WHEN all data fields are populated, select "accept".
E 4.14 At the Main Menu, select "Emergency Classification".
D 4.15 At the Emergency Classification menu, select the Emergency Classification determined in Step 4.1.
E 4.16 Select "Continue".
.2 HP/01B/1009/029 On-Shift Dose Assessment Using Normal Page 7 of 10 Mode In Raddose V 4.17 IF General Emergency was selected in Step 4.15 a dialog box appears, "Is the Fission Product inventory inside containment greater than gap activity?" Select "NO".
0 4.18 At Main Menu, select "Perform Calculations".
NOTE:
A 10 mile EPZ Map Screen will be displayed after Raddose V calculates data in the current time step.
_ 4.18.1 IF General Emergency was selected in Step 4.15, select "GE PARS".
O 4.18.2 Select "Continue".
O 4.19 At Output Menu, select "Continue Calculations".
a 4.20 At Main Menu, select "Perform Forecast".
4.20.1 IF General Emergency was selected in Step 4.15 a dialog box appears, "General Emergency Classification is chosen. Is the Fission Product Inventory inside containment greater than gap activity?" Select "NO".
O 4.20.2 Select applicable Status of Emergency Release.
El 4.20.3 Select "New" for the Status of Projected Offsite Dose.
0 4.20.4 At Forecast Period box, enter the forecast period in hours. IF the release duration is unknown, input 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as the forecast period.
El 4.20.5 Select "OK".
El 4.21 WHEN pop-up message displays, "NOTE: Forecast will use the meteorological and source term data from (current step). Continue?" select "OK".
NOTE:
A 10 mile EPZ Map Screen will be displayed after Raddose V calculates data in the current time step.
4.21.1 IF General Emergency was selected in Step 4.15, select "GE PARS".
0 4.21.2 Select "Continue".
0 4.22 WHEN pop-up message displays, "Do you want to save PAZ's identified in Forecast Mode for evacuation?", select "No".
.2 On-Shift Dose Assessment Using Normal Mode In Raddose V Cl 4.23 At the Output Menu, select "Go to Report Menu".
4.23.1 IF printer is NOT available:
HP/O/B/ 1009/029 Page 8 of 10 11 4.23.1.1 o 4.23.1.2 o 4.23.1.3 o 4.23.1.4 4.23.2 IF printer 0
4.23.2.1 Cl 4.23.2.2 Select "View Green Form".
IF the Next Emergency Notification Due recorded in Step 4.1 is 20 minutes or less from current time OR if requested by the OSM, use data on Green Form to complete Enclosure 5.3.
Retain copy of Enclosure 5.3 for turnover to TSC Dose Assessors.
Provide completed Table 1 of Enclosure 5.3 to OSM.
is available:
Select "Print Green Form + Summary Form".
IF the Next Emergency Notification Due recorded in Step 4.1 is 20 minutes or less from current time OR if requested by the OSM, use Raddose V printout to complete Enclosure 5.3.
Retain a copy of Enclosure 5.3 for turnover to TSC Dose Assessors.
El 4.23.2.3 El 4.23.2.4 Provide completed Table 1 of Enclosure 5.3 to OSM.
El El El El 4.24 Retain the printout for turnover to TSC Dose Assessors.
4.25 Select "Return to Output Menu".
4.26 Select "Return to Main Menu".
4.27 WHEN the popup message displays "You just completed a forecast. Remember to check meteorological and source term data for current information", click "OK".
4.28 IF additional dose projections are NOT needed go to Step 4.31.2:
TE:
Raddose V requires a step and a projection every 15 minutes after the release start time. This function CANNOT be bypassed.
NO o 4.29 At Main Menu Screen, select "Enter/Edit Meteorological Data".
El 4.29.1 WHEN popup displays "Do you want to add a new time step for time [previous time plus 15 minutes]?", click "Yes".
.2 On-Shift Dose Assessment Using Normal Mode In Raddose V HP/0/B/ 1009/029 Page 9 of 10 NOTE:
With "PI Server" selected in Step 4.6, data wjll be automatically populated from SDS.
4.29.2 IF data fields are NOT populated, Raddose V displays following pop-up message:
"No automatic meteorological data available. Enter data manually". Select "OK".
0 4.29.2.1 Go to Enclosure 5.4.
O 4.29.2.2 Manually enter following data from Table 1 of Enclosure 5.4:
- Lower wind speed in mph. Select "Enter".
- Upper wind direction in degrees. Select "Enter".
- Delta Temperature in degrees C. Select "Enter".
- Air Temperature in degrees C. Select "Enter".
- Precipitation during last 15 mins in inches. Select "Enter".
E 4.29.3 WHEN all fields are populated, select "Accept".
0 4.30 At Main Menu Screen, select "Enter/Edit Source Term Data".
0 4.30.1 WHEN popup displays "Do you want to add a new time step for time [previous time plus 15 minutes]?", select "Yes".
NOTE:
With "PI Server" selected in Step 4.6 data will be automatically populated from SDS.
4.30.2 IF data fields are NOT populated, Raddose V displays following pop-up message:
"No automatic source term data available. Enter data manually." Select "OK".
E 4.30.2.1 E 4.30.2.2 Go to Enclosure 5.4, Table 2.
Manually enter following data from Table 2 of Enclosure 5.4:
A. IF LOCA was selected in Step 4.12.2:
- Monitor reading for EMF selected in Step 4.12.4.1. Select "Enter".
- Unit vent flow rate. Select "Enter".
B. IF SGTR was selected in Step 4.12.2:
- Monitor reading for EMF selected in Step 4.13.1. Select "Enter".
- Flow rate. IF the flow rate is NOT known, input the default value of 5.235E4 pounds steam per 15 minutes. Select "Enter".
- Monitor reading for EMF selected in Step 4.13.5. Select "Enter".
- Unit vent flow rate. Select "Enter".
.2 HP/OIB/1009/029 On-Shift Dose Assessment Using Normal Page 10 of 10 Mode In Raddose V 0 4.30.3 WHEN all data fields are populated, select "accept".
E 4.31 Repeat Steps 4.14 - 4.30 until on-shift dose projections are no longer necessary.
l 4.32 WHEN on-shift dose projections are NOT needed:
O 4.32.1 Select "Go to Start-up Menu".
0 4.32.2 Select "Exit Raddose-V".
.3 HPIOIB/1009/029 Completing Radiological Portion of Page 1 of 3 Emergency Notification Form Continuous Use
.v h., {nF"tM Tiiel
^amnar
..,.w+h V--+--l fien wu.AJ1Ip U
A.
,.uIILIVA 1
y
")Y WJIL)
Date/Time
/
Performer (print name)
Initials Performer (print name) l Initials
- 1. Purpose This enclosure provides direction for Radiation Protection shift personnel to report results of off-site dose assessment to Operations Shift Manager (OSM)/Emergency Coordinator (EC).
- 2. Limits and Precautions None
- 3. Initial Conditions 3.1 Completed Enclosure 5.1 OR completed Enclosure 5.2 3.2 Emergency Notification to off-site agencies due.
- 4. Procedure 4.1 Complete Line 10 of Table 1.
4.1.1 IF release is still in progress, select IS OCCURRING.
4.1.2 IF release has stopped, select HAS OCCURRED.
4.2 Complete Line 11 of Table 1.
O 4.2.1 Select GROUND Level o 4.2.2 Select AIRBORNE.
o 4.2.3 Record date AND time release started.
4.2.4 IF release has stopped, record date AND time release stopped.
4.3 Complete line 12 of Table I using data in Release Rate section of the Raddose V printout.
C 4.3.1 Select CURIES PER SEC.
_ 4.3.2 IF release is below normal operating limits, select BELOW.
3 HP/0B/1009/029 Completing Radiological Portion of Page 2 of 3 Emergency Notification Form 4.3.3 IF release is above normal operating limits, select ABOVE.
[1 4.3.4 Record value in Ci/s next to NOBLE GASES.
E1 4.3.5 Record value in Ci/s next to IODINES.
E 4.3.6 Record value in Ci/s next to PARTICULATES.
4.4 Complete line 13 of Table I using data in Actual, Forecast and Total (Forecast + Integrated)
Doses section of Raddose V printout.
El 4.4.1 Select NEW.
E 4.4.2 Record Step Time (from header information) in blank following PROJECTION TIME.
[1 4.4.3 Record 1 hr. in blank following ESTIMATED DURATION.
D 4.4.4 Record the TEDE values from the TEDE (mrem) Forecast column in following blanks:
- SITE BOUNDARY (use the value for 0.50 miles)
- 2MILES S MILES 10 MILES E
4.4.5 Record Thyroid CDE values from Thyroid CDE (mrem) Forecast column in following blanks:
- SITE BOUNDARY (use value for 0.50 miles)
- 2 MULES
- 5 MILES 10 MILES 4.5 Complete line 14 of Table 1 using data from Meteorological Data section of Raddose V printout.
El 4.5.1 Record Wind Direction (from).
E 4.5.2 Record Wind Speed.
D 4.5.3 Record Stability Classification.
El 4.5.4 Record Precipitation. Value used when entering Meteorological data in Raddose V.
4.6 Provide completed Table I to OSM.
.3 HP/O/B/1009/029 Completing Radiological Portion of Page 3 of 3 Emergency Notification Form TABLE 1 EMERGENCY NOTIFICATION RADIOLOGICAL DATA
- 10. EffRENCY RELEASE(S):
II NONE (Go to item 14 )IIPOTENTIAL (Go to item 14.)
L IS OCCURRING L.J HAS OCCURRED
- 11. TYPE OF RELEASE:
[]ELEVATED GROUND LEVEL
[
AIRBORNE:
Started:_______________
/
I Stopped.__________
I I
Tmire (Easzem) tMM DD YY Tnne (Eastern)
MM DD YY Fq LIQUID:
Started:____________
I
/ I Stopped:____________
I I
Tnme (Eastern)
MMli DO YY Time (Easen)
MtM DO WY
- 12. RELEASE MAGNITUDE L CURIES PER SECfl CURleS NORMAL OPERATING LIMITS [
BELOW D ABOVE FW NOBLE GASES
[CI B
OD IESDINES_
[c] PARTICULATES E] OTHER_
- 13. ESTIMATE OFPROJECTED OFFSITE DOSE:
F NEW F
UNCHANGED PROJECTIONTIME:________
TEDE Thyroid CDE mrem mrem SITE BOUNDARY ESTIMATED DURATION:
HRS.
2 MILES 5 MILES 10 MILES
- 14. METEOROLOGICALDATA: E3 WIND DIRECTION (from)
[]
SPEED (MPH)
[
STABILITY CLASS RD PRECIPITATION (type)
.4 HP/O/B/1009/029 Manual Data Collection Sheet Page I of 2 Reference Use Compared with Control Copy by (print)-
Date/Time
/
Performer(print name)
Initials Performer (print name)
Initials
- 1. Purpose This enclosure provides a format for recording data used by Raddose V when data is NOT automatically loaded from SDS.
- 2. Limits and Precautions None
- 3. Initial Conditions 3.1 SDS data is NOT automatically loaded into Raddose V.
- 4. Procedure 4.1 Obtain Meteorological Data as follows:
4.1.1 IF SDS data is available complete Table I using SDS values.
4.1.2 IF SDS data is NOT available complete Table I using values obtained from the control room.
4.1.3 IF Meteorological data is NOT available in the Control Room D 4.1.3.1 Obtain wind speed, direction, air temp and precip from one of the following sources:
- Duke meteorologist at 594-0341/0289
- National Weather Service (NWS) at 1-800-268-7785 C 4.1.3.2 Use the following default values for Delta temp:
- Between 1000-1600 hrs: -0.3
- Between 1600-1000 hrs: +1.3
.4 HP/0B/ 1I009/029 Page 2 of 2 Manual Data Collection Sheet Table 1. Meteorological Data Step Date/Time Lower Wind Upper Wind Delta Temp Air Temp Precip Speed Direction (deg C)
(deg C)
(diff/l hr)
(mph)
(deg from N)
AVG D/T AVG AMB PRE DIF AVG LWS AVG UWD
+
4 4
4 4
4-4.2 Obtain Source Data as follows:
4.2.1 IF SDS data is available complete Table 2 using SDS values.
4.2.2 IF SDS data is NOT available complete Table 2 using values obtained from the control room.
Table 2. Source Term Data Unit Vent Steamline Step Date/Time EMF #
EMF Reading Unit Vent Actual Cont EMF #
EMF (cpm or R/hr)
Percent Flow Rate Press Reading Flow
(% Flow Rate x (psig)
(mR/hr)
Rate 188,748 cfm) 4.3 Use data from Tables I and 2 to input data to Raddose V.
.5 HP/0[B/1009/029 Operation of the TSC Laptop Computer Page 1 of 1 Information Use
- 1. Purpose This enclosure provides instructions for the operation of the laptop computer in the TSC.
- 2. Limits and Precautions None
- 3. Initial Conditions 3.1 Other computers are NOT available for performing off-site dose projections.
3.2 The OSM has directed Radiation Protection shift personnel to perform off-site dose projections.
- 4. Procedure 4.1 Use key in TSC Dose Assessment cabinet to open wall cabinet containing laptop computer.
4.2 Place laptop on desk under cabinet.
4.3 IF yellow LAN cable is NOT attached to laptop, connect LAN cable to back of laptop.
4.4 Turn the laptop on.
4.5 WHEN prompted, press ctrl-alt-delete.
4.6 WHEN prompted, enter your user id and personal domain password.
4.7 Perform dose projections in accordance with procedure.
4.8 WHEN laptop computer is no longer needed, shutdown computer.
4.9 Return laptop to wall storage cabinet.
(RW4-01)
Duke Power Company (1)
ID No. RP/0/A15700/006 PROCEDURE PROCESS RECORD Revision No. 010 PREPARATION (2) Station MCGUIRE NUCLEAR STATION (3) Procedure Title Natural Disasters (4) Prepared By 0
(5) Requires NSD 228xpplicability Determination?
I23 Yes (New procedure or revision with major changes)
E No (Revision with minor changes)
D No (To incorporqte previously a proved changes)
(6) Reviewed By
/V-
,/
Cross-Disciplinary Review By Reactivity Mgmt. Review By Mgmt. Involvement Review By (7) Additional Reviews Reviewed By Reviewed By (8) Temporary Approval (if necessary)
Date 3
/5 (QR)
(QR)
(QR)
(Ops Supt.)
Date NA Date NA Date NA Date 37/ 7 3
e?
- - a// 12-e 0
3//7-?
5/7 2-'03 Date Date By (OSM/QR)
Date By (QR)
Date (9) Approved By Date
__/____3 PERFORMANCE (Compare with Control coievery 14 calendar days while work is being performed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (I 1)Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification E Yes E NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
E Yes E NA Required enclosures attached?
E Yes E NA Data sheets attached, completed, dated, and signed?
E Yes 0 NA Charts, graphs, etc. attached dated, identified, and marked?
o Yes E NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additional pages, if necessary)
Duke Power Company McGuire Nuclear Station Natural Disasters Reference Use Procedure No.
RP/O/A15700/006 Revision No.
010 Electronic Reference No.
MC0094MH
RP/O/A/57001006 Page 2 of 13 Natural Disasters
- 1. Symptoms The following conditions are observed on the site or notification from the National Weather Service, System Dispatcher, or local radio broadcast has been received that the condition is imminent or occurring:
- Low Lake Level: Lake Normal level has dropped to the <745 foot elevation.
- High Lake Level: Lake Nonmal level has risen to the >767.9 foot elevation.
- Flood or Seiche: Flood on site or an earthquake induced tidal wave on the lake.
- Tornado Watch in Mecklenburg County: A tornado watch means conditions are favorable for a tornado to occur.
- Tornado Warning in Mecklenburg County: A tornado warning indicates that an actual tornado has been reported to the National Weather Service or has been sighted on radar.
- High Wind Speed: Sustained (greater than 15 minutes) wind speed >60 mph as reported by the National Weather Service or from the environmental tower (Environmental tower wind speed over-ranged).
- Hurricane Watch or Warning for Mecklenburg County: As reported by the National Weather Service.
- 2. Immediate Action None
- 3. Subsequent Actions 3.1 Notify the Operations Shift Manager.
3.2 IF design basis conditions are exceeded which jeopardize the safe operation of the reactor, THEN take the units to hot standby.
3.3 As directed by OSM, perform the following:
3.3.1 Turn on outside page speakers.
I,..I
RP/O/A/5700/006 Page 3 of 13 3.3.2 Using any plant phone in the Control Room horse shoe, or extension 4021, dial 710; pause, dial 80, and announce actual or impending condition over the plant page system and give a brief description.
3.3.3 Repeat the announcement.
3.3.4 Turn off outside speakers when announcements are complete.
3.4 Notify the dispatcher of the actual or imminent condition.
3.5 Notify Radiation Protection to minimize or stop all handling of radioactive materials.
3.6 Notify Radwaste Chemistry to minimize or stop all handling of radioactive materials.
NOTE:
It may be necessary to operate systems that release radioactivity such as VQ to maintain the plant, but operation of these systems should be minimized.
3.7 Minimize or stop all radioactive releases to the environment for the duration of the emergency (VQ, VP, VE, LWRs, GWRs, etc.).
3.8 Contact Station Management to evaluate the following {PIP-M-01-0258}:
3.8.1 Any high risk evolution in progress.
3.8.2 IF in midloop operation, THEN evaluate raising NCS level.
3.9 Notify the following groups to ensure the following doors are closed unless the event is Low Lake Level:
3.9.1 Work Control Center:
Warehouse doors All breached fire doors VE doors IF no obstructions prevent timely closure, THEN the equipment hatch should be closed for tornado protection. Consult Operations Shift Manager to evaluate closure requirements (fully closed or partially closed) in present mode of operation.
{PIP 0-M96-1572}
- IF equipment hatch is unable to be closed, THEN the personnel airlock doors (inner or outer door) should be placed into service, if available.
Consult Operations Shift Manager to evaluate closure requirements in present mode of operation. {PIP 0-M96-1572}
RP/O/A/5700/006 Page 4 of 13
3.9.2 Security
All CAD doors except for normal transit Spent Fuel Building Rollup doors.
3.9.3 Radiation Protection:
All Waste Shipping Facility Rollup and personnel access doors Staging Building Rollup door.
3.9.4 Operations
All Turbine Building Rollup doors (truck corridor, by the Atmospheric Steam Dump valves, by the Auxiliary Electric Boiler, unit two turbine floor, north end)
All Turbine Building personnel access doors Equipment windows (2) on the north wall of each Turbine Building, 786 ft. elevation.
3.10 Take necessary steps to increase the levels of Upper Surge Tanks, Auxiliary Feedwater Condensate Storage Tank, and the CA towers.
3.11 Classify the emergency per RP/O/A/5700/000 (Classification of Emergency) and commence notification and other protective measures as directed by appropriate Emergency Response Procedure.
3.12 IF AT ANY TIME conditions degrade to a point that the Control Room crew determines a reactor trip is prudent, THEN perform as follows:
3.12.1 Trip the reactors.
3.12.2 GO TO EP/1&2/A/5000/E-0 (Reactor Trip or Safety Injection) while continuing with this procedure.
3.13 For the following conditions, GO TO the following sections:
3.13.1 Low Lake Level:
GO TO Section 4.
3.13.2 High Lake Level, Flood, Seiche:
GO TO Section 5.
3.13.3 Tornado Watch:
GO TO Section 6.
RP/O/A/5700/006 Page 5 of 13 3.13.4 Tornado Warning:
GO TO Section 7.
3.13.5 High Winds or Hurricane:
GO TO Section 8.
NOTE:
The following step does not apply unless a unit restart is needed following a natural disaster.
3.14 Contact Emergency Planning to evaluate off-site capabilities per EP FAM 3.4 (Assessment of Off-Site Capabilities Post-Natural Disasters).
- 4. Subsequent Actions For Low Lake Level 4.1 IF Loss of RN suction from low level intake is imminent, THEN GO TO AP/1&2/A/5500/020 (Loss of Nuclear Service Water System) while continuing with this procedure.
4.2 REFER TO RP/I/A/5700/000 (Classification of Emergency).
4.3 Consult with station management to consider shutting down both units, consider staffing the Technical Support Center and the Operations Support Center, and consider placing additional personnel on shift.
- 5. Subsequent Actions For High Lake Level, Flood Or Seiche 5.1 Notify the Work Control Center to take prudent actions to expedite the restoration of important plant systems and components (such as safety systems and electrical systems) which are out of service for maintenance or testing 5.2 Determine the status of Electrical Power Sources (buslines, emergency diesels, SSF diesel generator, vital and non-vital batteries) and take any prudent actions to ensure their availability.
5.3 Monitor Groundwater Sumps and ensure sump levels are being maintained.
5.4 Monitor Turbine Building Sumps and ensure sump levels are being maintained.
5.5 Consult with station management to consider shutting down both units, consider staffing the Technical Support Center and the Operations Support Center, and consider placing additional personnel on shift.
RP/O/A/5700/006 Page 6 of 13 5.6 Operators should review EP/1&2/A/5000/ECA-0.0 (Loss of All AC Power) and AP/1&2/5500/007 (Loss of Electrical Power) and take any prudent actions to ensure equipment required for station blackout response is available.
5.7 WHEN conditions permit, THEN contact the Work Control Center or the TSC (if activated), to organize a team to survey plant structures and equipment to determine the extent of damage, if any, and to develop contingency plans to repair any damaged structures or equipment.
- 6. Subsequent Actions For Tornado Watch NOTE:
A Tornado Watch indicates conditions are favorable for a tornado to occur.
Wind speed information > 90 mph shall be obtained from National Weather Service at 1-864-879-1085 (unpublished).
Actions may be performed simultaneously.
6.1 Contact the National Weather Service (1-864-879-1085), or Duke Power Meteorological group (704-594-0341), as required to obtain the latest information.
6.2 Ensure fuel handling activities are secured.
6.3 Notify the Work Control Center to take prudent actions to expedite the restoration of important plant systems and components (such as safety systems and electrical systems) which are out of service for maintenance or testing.
6.4 Determine the status of Electrical Power Sources (buslines, emergency diesel generators, SSF diesel generator, vital and non-vital batteries) and take any prudent actions to ensure their availability.
CAUTION:
The site inspection is meant to be done before a tornado arrives on sight. It would NOT be prudent to send a team out to survey the site in the middle of a tornado.
Operations Shift Manager discretion based on safety considerations should determine sending personnel for any site inspection.
6.5 IF time and personnel safety permit, THEN notify the Work Control Center, SWM, and Nuclear Site Services personnel (ext. 4303) to have appropriate personnel inspect the site (including the switchyard) for the following items and secure, or relocate them away from the site, or relocate to the NE side of the plant, if possible: {PIP 0-M96-0716}
RP/O/A/5700/006 Page 7 of 13 Large cranes (lower boom to ground, if possible)
Lifting devices secured Vehicles (ensure materials stacked on truck are tied down)
Hazardous Material containers Trash bin or equipment on wheels Compressed gas cylinders Loose lumber or material near critical equipment.
6.6 Operators should review EP/1&2/A/5000/ECA-0.0 (Loss of All AC Power) and AP/1&2/5500/007 (Loss of Electrical Power) and take any prudent actions to ensure equipment required for station blackout response is available.
6.7 Notify the Work Control Center to have Maintenance stop use of the Turbine Building Cranes and park and anchor the cranes furthermost from the Auxiliary Building.
6.8 IF Loss of RN suction from low level intake is imminent, THEN GO TO AP/1&2/A/55001020 (Loss of Nuclear Service Water System) while continuing with this procedure.
6.9 This procedure remains in effect until one of the following conditions are met:
Termination of Tornado Watch for Mecklenburg County by National Weather Service OR Duke Power Meteorological Group (704-594-0341) verifies that a tornado threat to the McGuire Nuclear Site no longer exists.
- 7. Subsequent Actions For Tornado Warning NOTE:
Tornado Warning indicates that an actual tornado has been reported to NWS or has been sighted on radar.
Wind speed information > 90 mph shall be obtained from National Weather Service at 1-864-879-1085 (unpublished).
Actions may be performed simultaneously.
7.1 Turn on outside page speakers.
RP/O/A/5700/006 Page 8 of 13 7.2 Using any plant phone in the Control Room horse shoe, or extension 4021, dial 710, pause, dial 80, and announce one of the following:
- IF the tornado is NOT expected to pass over the Site, THEN announce the following:
"Attention all plant personnel. Attention all plant personnel. This is the Operations Control Room. A tornado warning has been issued for Mecklenburg County. Be prepared to take shelter should a tornado develop on site. Further updates will be provided as conditions warrant."
- IF the tornado is expected to pass over the Site, THEN announce the following:
"Attention all plant personnel. Attention all plant personnel. This is the Operations Control Room. A tornado warning has been issued for Mecklenburg County. Take shelter immediately. Do NOT take shelter in temporary buildings or trailers.
Further updates will be provided as conditions warrant."
7.3 Turn off outside page speakers when announcements are complete.
7.4 Contact the National Weather Service (1-864-879-1085) or Duke Power Meteorological group (704-594-0541), as required to obtain the latest information.
7.5 Ensure fuel handling activities are secured.
7.6 Notify the Work Control Center to take prudent actions to expedite the restoration of important plant systems and components (such as safety systems and electrical systems) which are out of service for maintenance or testing.
7.7 Determine the status of Electrical Power Sources (buslines, emergency diesel generators, SSF diesel generator, vital and non-vital batteries) and take any prudent actions to ensure their availability.
CAUTION:
The site inspection is meant to be done before a tornado arrives on sight. It would NOT be prudent to send a team out to survey the site in the middle of a tornado.
Operations Shift Manager discretion based on safety considerations should determine sending personnel for any site inspection.
RP/O/A/5700/006 Page 9 of 13 7.8 IF time and personnel safety permit, THEN notify the Work Control Center, SWM and Nuclear Site Services personnel (ext. 4303) to have appropriate personnel inspect the site (including the switchyard) for the following items and secure or relocate them away from the site or relocate to the NE side of the plant, if possible: {PIP 0-M96-07161 0
0 S
0 0
Large Cranes (lower boom to ground, if possible)
Lifting devices secured Vehicles (ensure materials stacked on truck are tied down)
Hazardous Material containers Trash bin or equipment on wheels Compressed gas cylinders Loose lumber or material near critical equipment.
7.9 Operators should review EP/1&2/A/5000JECA-O.O (Loss of All AC Power) and AP/1&2/5500/007 (Loss of Electrical Power) and take any prudent actions to ensure equipment required for station blackout response is available.
7.10 7.11 Notify the Work Control Center to have Maintenance stop use of the Turbine Building Cranes and park and anchor the cranes furthermost from the Auxiliary Building.
IF loss of RN suction from low level intake is imminent, THEN GO TO API1&2/A/5500/020 (Loss of Nuclear Service Water System) while continuing with this procedure.
NOTE:
Considerations should be given to the potential for difficulty to travel to the site following tornado due to debris.
7.12 Consult with station management to consider staffing the Technical Support Center and the Operations Support Center, and consider placing additional personnel on shift.
7.13 Consult with station management to evaluate conducting a site assembly and/or a site evacuation. IF a site assembly is NOT conducted, THEN evaluate evacuating personnel from site trailers and sea containers (MTU's).
lNOTE:
The following step places VA and VC in Tech Spec 3.0.3. {PIP-0-M-99-4081 )
7.14 IF a tornado has been determined to be on site, THEN perform the following:
7.14.1 7.14.2 Shut down all VA fans.
Shut down all VF fans.
7.14.3 Close VC1A, 2A, 3B, 4B, 9A, 10A, 1 B and 12B (Outside Air Intake Valves).
RPIO/A/5700/006 Page 10 of 13 7.15 7.16 IF a tornado has been observed touching down on, or near site, THEN REFER TO RP/0/A/5700/000 (Classification of Emergency).
IF a tornado has been determined to be onsite, THEN notify the Work Control Center or TSC (if activated) to organize a team to survey the plant when conditions permit. Survey plant structures (including the switchyard) and equipment to determine the extent of the damage and develop contingency plans to repair any damaged structures or equipment.
7.17 If applicable, discuss the extent of plant damage caused by tornado with site management and determine the need for plant shutdown and/or repair.
7.18 After condition clears, realign any systems shutdown previously as desired.
7.19 This procedure remains in effect until one of the following conditions are met:
Termination of Tornado Warning for Mecklenburg County by National Weather Service OR Duke Power Meteorological Group (704-594-0341) verifies that a tornado threat to the McGuire Nuclear Site no longer exists.
- 8. Subsequent Actions For High Winds Or Hurricane NOTE:
Wind speed information > 90 mph shall be obtained from National Weather Service at 1-864-879-1085 (unpublished).
I Actions may be performed simultaneously.
8.1 WHEN the hurricane is within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from arriving onsite, THEN turn on the outside page speakers.
8.2 Using any plant phone in the Control Room horse shoe, or extension 4021, dial 710; pause, dial 80, and announce:
"Attention all plant personnel. Attention all plant personnel. This is the Operations Control Room. Hurricane force winds are projected to be on site within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Be prepared to take shelter should the hurricane force winds develop on site. Further updates will be provided as conditions warrant."
8.3 Turn off the outside page speakers.
RP/O/A/5700/006 Page 11 of 13 8.4 Operators should review EP/1&2/A/5000/ECA-0.0 (Loss of All AC Power) and AP/1&2/5500/007 (Loss of Electrical Power) and take any prudent actions to ensure equipment required for station blackout response is available.
8.5 Contact the National Weather Service (1-864-879-1085) or Duke Power Meteorological group (704-594-0541), as required to obtain the latest information.
8.6 Discussions should be held with the Station Manager so that a decision can be made on when and how to place the plant in a safe shutdown condition two hours before the anticipated hurricane arrival at the site (i.e., sustained wind speeds in excess of 73 mph).
{ PIP 0-M96-2508)
NOTE:
Considerations should be given to the potential for difficulty to travel to the site following storm due to storm debris. {PIP 0-M96-2508}
8.7 IF not performed in RP/0/B/5700/027 (Hurricane Preparation), THEN consult with station management to consider staffing the Technical Support Center and the Operations Support Center and consider placing additional personnel on shift.
8.8 IF Loss of RN suction from low level intake is imminent, THEN GO TO AP/1 &2/A/5500/020 (Loss of Nuclear Service Water System) while following this procedure.
8.9 Ensure fuel handling activities are secured.
8.10 8.11 8.12 8.13 8.14 Notify the Work Control Center to take prudent actions to expedite the restoration of important plant systems and components (such as safety systems and electrical systems) which are out of service for maintenance or testing.
Return any out of service battery chargers to service. {PIP 0-M96-2508)
Consult station management to evaluate testing on the onsite Diesel Powered VI compressors prior to arrival of hurricane onsite. { PIP 0-M96-2508 }
Consult station management to evaluate starting, loading and testing D/Gs within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of hurricane force winds arriving on site. Previous run history of the D/Gs should be utilized when making this determination, it would be unnecessary to run any D/G ran within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. {PIP 0-M96-2508}
Determine the status of Electrical Power Sources (buslines, emergency diesel generators, SSF diesel generator, vital and non-vital batteries) and take any prudent actions to ensure their availability.
RP/O/A/5700/006 Page 12 of 13 CAUTION:
The site inspection is meant to be done before high winds arrive on sight. It would NOT be prudent to send a team out to survey the site in the middle of high winds (sustained wind speed >60 mph). Operations Shift Manager discretion based on safety considerations should determine sending personnel for any site inspection.
8.15 IF not performed in RP/I/B/5700/027 (Hurricane Preparation), AND time and personnel safety permit, THEN notify the Work Control Center and SWM to have appropriate personnel inspect the site (including the switchyard) for the following items and secure or relocate them away from the site or relocate to the NE side of the plant (to reduce the potential for missiles), if possible: {PIP O-M96-25081 S
0 00 S
0 Large cranes (lower boom to ground, if possible)
Lifting devices (Outside Lift if being used for SGRP) secured Vehicles (ensure materials stacked on truck are tied down)
Hazardous Material containers Trash bin or equipment on wheels Compressed gas cylinders Loose lumber or material near critical equipment.
8.16 Notify the Work Control Center to have Maintenance stop use of the Turbine Building Cranes and park and anchor the cranes furthermost from the Auxiliary Building.
8.17 8.18 8.19 8.20 8.21 8.22 8.23 Send an operator to ensure the equipment windows (2) on the north wall of each Turbine Building 786 ft. elevation are closed and locked.
Monitor Groundwater Sumps and ensure sump levels are being maintained.
Monitor Turbine Building Sumps and ensure sump levels are being maintained.
Consult with station management to evaluate conducting a site assembly and/or a site evacuation. IF a site assembly is NOT conducted, THEN evaluate evacuating personnel from site trailers and sea containers (MTU's).
REFER TO RP/0/A/5700/000 (Classification of Emergency).
WHEN conditions permit, contact the Work Control Center or the TSC (if activated) to organize a team to survey plant structures (including the switchyard) and equipment to determine the extent of damage, if any, and to develop contingency plans to repair any damaged structures or equipment.
If applicable, discuss the extent of plant damage caused by hurricane with site management and determine the need for plant shutdown and/or repair.
8.24 After condition clears, realign any systems shutdown previously as desired.
RP/O/A/5700/006 Page 13 of 13 8.25 This procedure remains in effect until one of the following conditions are met:
Termination of Hurricane Conditions for Mecklenburg County by National Weather Service OR Duke Power Meteorological Group (704-594-0341) verifies that a hurricane threat to the McGuire Nuclear Site no longer exists.
End or Body