ML023310204
| ML023310204 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Limerick  |
| Issue date: | 11/21/2002 |
| From: | Gallagher M Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation, Office of Nuclear Security and Incident Response |
| References | |
| Download: ML023310204 (44) | |
Text
N Exelkni, Exelon Nuclear 200 Exelon Way www exeloncorp corn Nuclear Kennett Square, PA 19348 10CFR50, Appendix E November 21, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Peach Bottom Atomic Power Station, Units 2 & 3 Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Limerick Generating Station, Units 1 & 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 EP-MA-1 10-200, Revision 1, "Dose Assessment" Enclosed is a revised Emergency Plan Procedure for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, and Limerick Generating Station (LGS), Units 1 and 2. This procedure is required to be submitted within thirty (30) days of its revision in accordance with 10CFR50, Appendix E, and 10CFR50.4.
Also, enclosed are copies of a computer generated report index identifying the latest revisions of the LGS and PBAPS procedures.
If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, M. P. Gallagher Director - Licensing & Regulatory Affairs Mid-Atlantic Regional Operating Group Enclosures cc: H. J. Miller, Administrator, Region I, USNRC (w/ Enclosures)
A. C. McMurtray, USNRC, Senior Resident Inspector, PBAPS (w/o Enclosures)
A. L. Burritt, USNRC, Senior Resident Inspector, LGS (w/o Enclosures)
J. P. Boska, USNRC, Senior Project Manager (w/ Enclosures)
S. P. Wall, USNRC, Senior Project Manager (w/ Enclosures)
ATTACHMENT 1 LIMERICK GENERATING STATION, UNITS 1 & 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 & 3 Docket Nos. 50-352 50-353 50-277 50-278 License Nos. NPF-39 NPF-85 DPR-44 DPR-56 EMERGENCY PROCEDURES EP-MA-110-200, "Dose Assessment" - Revision 1
so= EP-MA-1 10-200
,,n, Revision 1 Page 1 of 35 Nuclear Level 2 - Reference Use DOSE ASSESSMENT PURPOSE 1.1. This procedure provides guidance for performing offsite radiological dose assessments during an emergency using Dose Assessment and Protective Action Recommendation (DAPAR) Program for Limerick Generating Station (LGS) and Peach Bottom Atomic Power Station (PBAPS).
1.1.1. As a Windows-based application designed in Microsoft ACCESS, DAPAR uses many standard user interfaces. Instructions are not provided in basic computer operations in the Windows environment. The user must be familiar with these to efficiently operate the program. It is also assumed user is familiar with health physics fundamentals. Emergency Response Organization (ERO) training will provide an overview of dose assessment methodologies.
- 2. TERMS AND DEFINITIONS 2.1. Centerline (plume): An imaginary line drawn in the middle of the plume along its downwind travel direction. The plume concentrations and deposition are assumed to be the highest along the centerline.
2.2. Cloud Shine: Gamma radiation from radioactive materials in the air (plume).
2.3. Committed Dose Equivalent (CDE): Committed dose equivalent means the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.
2.4. 2.4Committed Effective Dose Equivalent (CEDE): Committed effective dose equivalent is the sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent (CDE) to these organs or tissues. Thyroid values are taken from EPA-400, Table 5-4 to be consistent with the NRC RASCAL dose assessment program used by the Pennsylvania Emergency Management Agency (PEMA)/
Bureau of Radiation Protection (BRP). Actual meteorology is used, since it gives the most accurate dose projection.
2.5. Core Damage: Damage to the components that comprise the reactor core.
Core damage typically refers to the failure of fuel cladding and/or fuel melting as a result of overheating.
2.6. .Curie (Ci): A unit of radioactivity equal to 3.7E+10 disintegrations per second.
EP-MA-1 10-200 Revision 1 Page 2 of 35
2.7. DAPAR
Dose Assessment and Protective Action Recommendation (DAPAR) software provides two major functions (Quick Assessment and Full Assessment) in order to perform dose assessment. (Refer to Attachment I for a Basis System Flow Diagram.)
A. Quick Assessment is used by the Shift Dose Assessor to arrive at offsite dose projections and PARs, or to verify classifications in as prompt a time as possible during fast breaking events without taking too much time away from their event mitigating actions. A monitored release is the only method used in the quick assessment. Some assumptions and standard numbers are used to limit the amount of data Control Room personnel must enter prior to calculating a PAR.
B. Full Assessment is used by the called-in ERO Staff in the TSC/EOF and allows for more detailed assessment of a release. The following methods may be used to project offsite doses:
"* Monitored Release: Offsite radiological assessment related to a monitored value taken at one of several release locations (Plant Vent Stack, Waste Processing Vent Stacks and Turbine Building Vent Stack) within the plant.
"* ContainmentLeakage / Failure:Offsite radiological assessment related to a default, known, or predicted level of containment leakage or failure.
"* Field Team Survey and Sample Analysis: Offsite radiological assessment related to comparisons of field team radiological survey and isotopic sample concentrations with predicted plume dispersion.
"* Release Point Sample Analysis: Offsite radiological assessment related to a measured isotopic concentration taken at the point of release to the environment.
2.8. Delta T: The difference in temperature from the lower temperature sensor and the upper temperature sensor on the Exelon meteorological tower. Delta T is used to calculate stability class.
2.9. Deposition
The contamination found on the surface of the ground.
2.10. Dose Commitment: The dose that will be accumulated by a specific organ over a specified period following uptake.
2.11. Dose Conversion Factor (DCF): The dose equivalent per unit intake of a radionuclide (mrem/uCi) or the effects of exposure to a given concentration of an isotope in a plume. RPhr per uCi/cc.
2.12. Dose Proiection: The calculation of individual radiation exposure at a given location at some time in the future. Dose projections are performed in response to an actual or anticipated release of radioactive material to the environment.
EP-MA-1 10-200 Revision I Page 3 of 35 2.13. Emergency Planning Zone (EPZ): An area around a nuclear power plant in which plans are in place for an emergency at the plant. Plans are in place to take immediate protective actions for individuals located within 10 miles of the Nuclear Plants. This area is called the Plume Exposure Emergency Planning Zone. In addition, longer-term plans are in place for the Ingestion Pathway Emergency Planning Zone which is within 50 miles of the plant.
2.14. Evacuation Exposure Period: The period during which those being evacuated are exposed to the radioactive plume.
2.15. Millirem (mR): One one-thousandth of a Rem. The Rem is a unit of measure that defines the extent of biological injury that results to the body when it is exposed to radiation.
2.16. Emergency Preparedness Data System (EPDS): Electronic graphical display of plant, meteorological and radiological data needed for accident and dose assessment.
2.17. Protective Action Guidelines (PAGs): Radiation exposure guidelines established by the Environmental Protection Agency which are used to determine the appropriate protective actions to be taken on the part of emergency workers and the general public. These actions include sheltering and evacuation.
2.18. Protective Action Recommendations (PARs): A recommendation made by Exelon personnel to the offsite authorities on the appropriate protective actions to be taken on the part of the general public. The PARs are based on plant conditions or dose projections using the PAGs for guidance.
EP-MA-1 10-200 Revision 1 Page 4 of 35 2.19. Radiological Release: The movement of radioactive materials, gaseous or liquid, beyond a protected area.- The definition requires the assessment of both plant conditions and effluent monitors to fully evaluate the situation.
2.20. Release in Progress: Defined as ANY radioactive release that is a result of, or associated with, the emergency event (not attributed to the normal operation of plant systems).
NOTE: The following guidelines may not cover every potential scenario. As such, judgment must be used in final determination, specifically in regards to field monitoring team survey results.
Have ANY of the following occurred:
"aIncrease in effluent radiation monitors (2X normal expected)?
"* ANY radioactivity (other than naturally occurring) detected by air sampling in site ventilation, buildings?
"*Reactor trip or rapid shutdown with ANY primary-to secondary leakage or CVCS leakage, venting or NO draining outside containment?
"* ANY secondary system steam release with primary to-secondary leakage?
"*ANY other event-related indication of gas or liquid release outside of containment from a system containing radioactive matenal?
"* ANY breach in a radiological storage area (i.e.,
waste decay tank, fuel poollstorage structure, etc.)?
"* LOSS of both RCS and Containment barriers per EAL Fission Product Barrier Matrix?
Increase in effluent monitors is NOT attnbuted to the NO normal operabon of plant systems.
OR If effluent monitors are by-passed, a pathway exists from aiher
- RCS to Containment to Environment a Storage structure to Environment
~ ES Release is in progress
EP-MA-1 10-200 Revision 1 Page 5 of 35 I 2.21. Safety Relief Valve: A valve that serves to reduce excessive pressure in the Reactor Coolant System (RCS) to protect them from being damaged by excessive pressure.
2.22. Site Boundary: For classification and dose projection purposes, the Site Boundary is the Exclusion Area Boundary, a 2500-foot (LGS) / 2700-foot (PBAPS) radius around the plant. The actual boundary is specified in the ODCM.
2.23. Station Vent: That part of the plant's ventilation system through which the containment building and auxiliary building air may be processed to the outside atmosphere. The discharge of the station vent is continuously monitored for abnormal amounts of radiation and would be isolated long before radiation levels approach federal limits.
2.24. Sectors: Pre-designated areas offsite in which Protective Actions such as evacuation will be recommended.
2.25. Total Effective Dose Equivalent (TEDE): Total Effective Dose Equivalent (TEDE) means the sum of the deep-dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures). For the purpose of this procedure TEDE also includes 4 days of deposition exposure.
EP-MA-1 10-200 Revision I Page 6 of 35
- 3. RESPONSIBILITIES 3.1. An on-shift Radiation Protection Technician (RPT) at the unaffected station shall serve as the Shift Dose Assessor and perform required dose assessments prior to responsibility being transferred to either the Technical Support Center (TSC) or Emergency Operations Facility (EOF).
3.2. The TSC Radiological Controls Coordinator shall relieve the Shift Dose Assessor and perform required assessments if the transfer of PAR / dose assessment responsibilities to the EOF is delayed.
3.3. The EOF Dose Assessor shall relieve the TSC Radiological Controls Coordinator when directed by the EOF Dose Assessment Coordinator, and perform required dose assessments. Responsibility for dose assessments can be assumed directly from the Shift Dose Assessor.
- 4. MAIN BODY 4.1. Initiating Conditions:
4.1.1. An emergency has been declared; AND 4.1.2. Events require the calculation of radiological effects due to an actual or potential release of radioactive materials near or beyond the site boundary.
CAUTION Use of the program to project doses based on normal plant readings would indicate offsite doses many magnitudes higher than actual offsite doses. The program should not be used to calculate the actual dose received by populations. As part of the post accident investigations, a more in depth analysis is needed to actually assign doses receives to members of the public.
EP-MA-1 10-200 Revision 1 Page 7 of 35 4.2. Start Up 4.2.1. If the main computer screen has DAPAR icons, then USE left mouse click on the icon to start the program.
NOTE: Backups to the hard drive DAPAR software are a common network drive on the LAN and CD-ROM disk with each dose assessment computer.
The common drive paths are:
0 Limerick Generating Station (LGS):
\\PECO\.PBS2_DATA1.PBS_SRVS.PBS.PECO\EPDAPAR
- Peach Bottom Atomic Power Station (PBAPS):
\\PECO\.PBS2_DATAI.PBS_SRVS.PBS.PECO\EPDAPAR
- 1. If the assigned Dose Assessment Computer cannot access the program over the Exelon LAN or the DAPAR program will not run, then INSTALL the program on any computer from backup CDs or Disks located in the OSC, TSC or the EOF.
4.2.2. VERIFY that the correct station version of the DAPAR program is being used.
NOTE: There is a different version of DAPAR for each Station. Refer to Figures 1-1 & 1-2. Each version takes into account different release points and gaseous effluent radiation monitor conversion factors.
t",W a rm i StatIon
.<\,.*:' .
............ .0.1 :
S .... . . ..Do . se. ,,,eat P..
..... .. .......... ..,,.m:n. dt Figure 1-2 2
EP-MA-110-200 Revision 1 Page 8 of 35 CAUTION Once the User selects "Quick Assessment" or "Full Assessment," returning to the title screen will reset all program values.
4.2.3. From the Title Screen, SELECT either "Full Assessment" or "Quick Assessment" and then GO TO either:
- 1. QUICK ASSESSMENT- Section 4.3
- 2. FULL ASSESSMENT- Section 4.4 4.2.4. PROVIDE the DAPAR Input Sheet (Attachment 7) to the following individual, based on facility, for system / event status information:
"* Control Room -> STNIndependent Assessor (or Shift Manager)
"* TSC -> Operations Communicator (or Operations Manager)
"* EOF 4- Operations Advisor (or Technical Support Manager)
EP-MA-1 10-200 Revision 1 Page 9 of 35 4.3. Quick Assessment: (Figures 2-1 & 2-2)
NOTE: The Quick Assessment operations and calculations are identical to the Full Assessment method for a monitored release, but uses a default release path and core damage assumptions for the determination of offsite doses.
This allows for a rapid assessment from the Main Control Room.
Figure 2-1: LIMERICK Figure 2-2: PEACH BOTTOM 4.3.1. Monitor Information - User chooses the appropriate monitor from the listed effluent monitors.
- 1. SELECT the applicable release point:
STATION MONITOR READOUT Limerick North Stack pCi/sec South Stack pCi/cc Main Stack pCi/sec Peach Bottom Vent (Rx Bldg) Stack pCi/sec Torus Vent cpm
- REFER to Attachment 5 to obtain data from Emergency Preparedness Data System (EPDS) to input into DAPAR.
EP-MA-1 10-200 Revision 1 Page 10 of 35 4.3.2. ENTER Reading Information - Enter the appropriate monitor reading.
4.3.3. ENTER Time After Shutdown Information - Enter the time since the reactor was shutdown in hours and minutes (hh:mm).
4.3.4. ENTER MeteorologicalData - Enter the appropriate data from plant instruments as follows:
- 1. If meteorological data (wind speed / direction and stability class) are NOT available via EPDS or locally in Control Room, then GO TO Attachment 2.
NOTE: The conditions Good or Adverse in the following step are in relation to the weather. Adverse is heavy rain or any other condition that would hinder the flow of traffic.
4.3.5. CLICK ON the Conditionsbutton to open the Weather Conditions Window (Figure 3).
. X::
... .::**% ,.'.'T* .
Figure 3
- 1. SELECT the appropriate conditions for the program to calculate the Maximum Evacuation Time Estimate (ETE).
NOTE: Once the user sets the evacuation conditions, the program will place the Max ETE value in the Release Duration and Max ETE text boxes.
4.3.6. Under Release Duration, CHANGE the displayed time to the known release duration.
- 1. If a good estimate of the release duration cannot be determined, then USE the default ETE value entered by the program.
4.3.7. SELECT the PARs button - The program will calculate the downwind doses based on user inputs and display Protective Action Recommendation Window. GO TO Section 4.9.
EP-MA-110-200 Revision I Page 11 of 35 4.4. Full Assessment The Full Assessment operations and calculations are identical to the Quick Assessment method for a monitored release, but it allows the user to make more choices in performing dose projection calculations.
Choosing the Full Assessment option directs the program to a baseline data entry window (Figure 4). The window is divided into four input areas.
Applicable only to LGS Figure 4 4.4.1. Source Term - This allows user to choose the appropriate source term depending on plant conditions and the type of accident that has occurred:
- 1. SELECT Reactor Core Accident if the source of the release is from the reactor core.
A. Under 'Type of Damage", SELECT Gap or Melt.
B. ENTER the % Damage based on core damage estimates or known conditions in the plant.
EP-MA-1 10-200 Revision 1 Page 12 of 35
- 2. SELECT Spent FuelAccident if the release is caused by damage to the spent fuel.
A. Under "Fuel Type", CHOOSE between New Fuelor Old Fuel.
B. Under "Fuel Status", CHOOSE between Under Wateror Dry.
NOTE: The program uses a gap release scenario and defaults to a reactor Time After Shutdown based on this choice.
Limerick only
- 3. SELECT Backwash Demin Spectrum if the release results from a backwash operation.
EP-MA-1 10-200 Revision 1 Page 13 of 35 4.4.2. Dominant Release Path - This allows user to choose the most appropriate release path: (Figures 5-1 & 5-2)
............... ~..
Fiqure 5-1: LIMERICK Fiaure 5-2: PEACH BOTTOM Flqure 5-1: LIMERICK (Cont'd) Figure 5-2: PEACH BOTTOM (Cont'd)
- 1. If a release through containment or drywell is.
chosen, then DETERMINE if containment sprays are 'ON' or 'OFF'. (Figure 6)
EP-MA-110-200 Revision 1 Page 14 of 35 Containment Reductions
- 2. DETERMINE Containment I Drywell holdup time, and SELECT the appropriate condition. (Figure 7)
Fiaure 7
- 3. If a release through the Aux Bldg or Reao Bld Reduction Rx Bldg., then DETERMINE the building holdup time. (Figure 8)
Figure 8
I
EP-MA-1 10-200 Revision 1 Page 15 of 35
- 5. If a release through a filtered Vent or SBGT, then CHOOSE if the filters are working or not. (LGS: Figure 10a & b / LGS: Figure 10c)
NOTE: If the release has been ongoing for a long time or contains a large amount of liquids filters may not be working.
SG Fite Reutin Figure 10a (LGS) N-iaure IUD (LUS)
Filter Reductions Figure 1Oc (PBAPS) 4.4.3. ENTER MeteorologicalData - Enter the appropriate data from plant instruments.
4.4.4. Assessment Methods - CHOOSE the appropriate assessment method based on available inputs. Assessment methods:
- 1. MonitoredRelease - SELECT this method for a release through a monitored release point such as the main stack or Rx Bid vent stacks or through the Main Steam Relief Valves. GO TO Section 4.5.
- 2. ContainmentLeakage - SELECT this method for containment failure scenarios.
GO TO Section 4.6.
- 3. FieldTeam Data - SELECT this method iffield team survey or sample data is available. GO TO Section 4.7.
- 4. Release Path - SELECT this method if a sample of a release has been obtained and a release flow rate can be estimated. GO TO Section 4.8.
EP-MA-1 10-200 Revision 1 Page 16 of 35 4.5. Monitored Release (Figure 11) riuure -
4.5.1. SELECT the applicable release point:
STATION MONITOR READOUT Limerick North Stack pCi/sec South Stack pCi/cc Main Stack pCi/sec Peach Bottom Vent (Rx Bldg) Stack pCi/sec Torus Vent cpm 4.5.2. ENTER Reading Information - Enter the appropriate monitor reading.
4.5.3. SELECT the Print button to print a report of offsite dose projections based on the monitored release.
- REFER to Attachment 3, Dose Assessment Report (Printout).
- REFER to Attachment 6 to save report(s) as ADOBE Acrobat file.
- 1. SELECT a different monitor and/or change readings to recalculate doses.
- 2. SELECT the Back button to change input data on Full Assessment Form.
4.5.4. SELECT the PAR button to view PAR form - GOTO section 4.9.
EP-MA-1 10-200 Revision 1 Page 17 of 35 4.6. Containment Leakage/Failure (Figure 12)
Figure 12 4.6.1. SELECT the appropriate containment release mode:
- 1. Leakage - Program defaults to the Design Leakage rate per the station UFSAR. If a different percentage of leak rate has been calculated by TSC engineers enter that value in the % per day text box.
- 2. Failureto Isolate - Assumes 100% of the isotopes available for release are released in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period.
- 3. CatastrophicFailure- Assumes 100% of the isotopes available for release are released in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time period.
4.6.2. [After User enters data the program calculates offsite doses] PERFORM one of the following:
- 1. SELECT the Print button to print offsite dose projections based on containment failure.
- REFER to Attachment 3, Dose Assessment Report (Printout).
- REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
- 2. SELECT the Back button to change input data on Full Assessment Form.
EP-MA-1 10-200 Revision 1 Page 18 of 35 4.7. Field Team Analysis (Figure 13)
The program calculates the plume Travel Time and Release Time to allow Dose Assessment personnel to compare previous dose assessment reports with data measured in the field.
4.7.1. Dose Rate Survey - SELECT this method if Field Team Survey Data is available.
4.7.2. Air Sample Results - SELECT this method if Field Team Air Sample Data is available.
Figure 13
EP-MA-1 10-200 Revision I Page 19 of 35 4.7.3. ENTER the Field Team information as follows:
NOTE: The program will not allow "mr/hr" readings for sample data or isotopic results for survey data.
- 1. ENTER Downwind (miles)- straight-line distance from release point to sample location.
- 2. ENTER Crosswind (miles)- the distance the team was away from the centerline when the sample was taken. The program will warn user if reported sample location is wider than expected plume width
- 3. IF the analysis basis is Dose Rate Survey- ENTER the Field Team Survey reading in "mR/hr" into the box labeled Level.
- 4. IF Analysis basis is Air Sample Results - ENTER the uCi/cc values for each known isotope in the table at the upper right section of the form.
NOTE: Prior to obtaining analysis results from field air sample, the 1-131 concentration, in uCi/cm 3 , calculated using the KI Spreadsheet Program per EP-MW(MA)-110-100 shall be used.
- 5. ENTER Survey Time - Enter the time the survey or sample was taken.
4.7.4. [After User enters data the program calculates offsite doses] PERFORM one of the following:
- 1. SELECT the Printbutton to print offsite dose projection reports based on Field Team Analysis.
- REFER to Attachment 3, Dose Assessment Report (Printout).
A. REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
- 2. SELECT the Back button to change input data on Full Assessment Form.
- 3. IF Field Team samples were the selected basis, SELECT the PAR button to view PAR form - GO TO section 4.9.
EP-MA-110-200 Revision 1 Page 20 of 35 4.8. Release Point Analysis (Figure 14)
Figure 14 4.8.1. ENTER the known Isotopic Concentrationfor each isotope (if unknown leave blank).
4.8.2. ENTER Vent Flow Rate (or estimate flow rate for other releases) in SCFM.
4.8.3. [After User enters data the program calculates offsite doses] PERFORM one of the following:
I. SELECT the Printbutton to print offsite dose projections based on Release Point Analysis.
- REFER to Attachment 3, Dose Assessment Report (Printout).
- REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
- 2. SELECT the Back button to change input data on Full Assessment Form.
EP-MA-1 10-200 Revision 1 Page 21 of 35 4.9. Protective Action Recommendations (Figure 15)
The Protective Action Recommendation (PAR) form displays a summary of the downwind dose projections with a map showing which Sectors (colored areas) where Protective Actions Recommendations should be made.
l Figure 15
EP-MA-1 10-200 Revision 1 Page 22 of 35 4.9.1. The RR button will display the total release rates for isotopic groups in Ci/sec. -..... .................Release F-Group . .. . . .jii I Rat-es-J-777tj (Figure 16)
Fiqure 16 4.9.2. SELECT the Go Back button and modify inputs. This will return user to either Quick Assessment Form or one of the Assessment Method forms available in the Full Assessment mode.
4.9.3. SELECT Printto print the PAR report.
"* REFER to Attachment 4, PAR Report (Printout).
"* REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
4.9.4. SELECT the STATE REPORT button to display DAPAR BRP PARAMETER REPORT and PRINT copy of form.
4.9.5. After each dose calculation is performed, FAX STATE REPORT and copies of associated Dose Assessment and PAR Reports to the Pennsylvania Emergency Operations Center (EOC) - Attention "BRP".
- 5. DOCUMENTATION:
None
- 6. REFERENCES 6.1. Exelon DAPAR Program Software Requirements Specification 6.2. Commitments - None
EP-MA-1 10-200 Revision 1 Page 23 of 35
- 7. ATTACHMENTS 7.1. Attachment 1, Basic Program Flow Diagram 7.2. Attachment 2, Determination of Stability Class 7.3. Attachment 3, Sample Dose Assessment Report 7.4. Attachment 4, Sample Protective Action Recommendation (PAR) Report 7.5. Attachment 5, EPDS Radiological and Meteorological data 7.6. Attachment 6, ADOBE Acobat File Saving 7.7. Attachment 7, DAPAR Input Sheet 7.8. Attachment 8, DAPAR BRP Report - Full Assessment (EXAMPLE)
EP-MA-1 10-200 Revision 1 Page 24 of 35 ATTACHMENT I BASIS PROGRAM FLOW DIAGRAM The above diagram shows basic tasks that can be performed by the DAPAR program and how a user would navigate between them.
There are two methods available to perform calculations:
- 1. Quick Assessment - Normally used by the Control Room and TSC Dose Assessors to quickly determine the appropriate Protective Action Recommendation for a gaseous effluent monitored release point. Program automatically picks conservative choices, limiting the number of user inputs needed to get results.
- 2. Full Assessment - Normally used by EOF Dose Assessor, and TSC Dose Assessor if EOF activation is delayed. Program allows for more choices and user inputs to provide analysis of different releases and/or field monitoring data.
EP-MA-110-200 Revision 1 Page 25 of 35 ATTACHMENT 2 DETERMINATION OF STABILITY CLASS Page 1 of 2 If Met Tower data is unavailable from ERO Applications' programs or via local indications in the Control Room, another source of meteorological data may be used such as the Meteorological Vendor, National Weather Service or a local TV or Radio broadcast stations.
- a. Wind Speed (MPH) - Obtain and enter wind speed in Miles per Hour (MPH)
- b. Wind Direction (From) - Obtain and enter the direction the wind is coming FROM in degrees. (0o-3600)
- c. Stability Class (A-G) - Obtain and enter the stability class.
Stability Class Categories A Extremely unstable conditions B Moderately unstable conditions C Slightly unstable conditions D Neutral conditions E . Slightly stable conditions F Moderately stable conditions G Extremely stable conditions
- 2. If the stability class is not available or provided, use the following tables to choose appropriated value:
NOTE: Meteorological Vendor normally provides AT/Az or CE.
- a. If Surface Wind Speed (in mph) is available, then USE Table 1-1.
- b. If delta temperature (AT) or sigma theta (ae), then USE station-specific table (if provided).
NOTE: The conditions Good or Adverse in the following step are in relation to the weather. Adverse is any weather condition, which would hinder the flow of traffic.
EP-MA-1 10-200 Revision 1 Page 26 of 35 ATTACHMENT 2 DETERMINATION OF STABILITY CLASS Page 2 of 2 Table 1-1 I
$ufacr Speed.
Wind I rrnb) f...'..........
sui~r Sp~at C~~~~ear~
Daytime CditiOns
~ ~
Wit~
~~ .
Heavy '
1
~I or,,k Ovrcs Ti Nighttime CQnI1tIQns vfas'<1 tot ludOecs Hay I
Rain 'cw oe~'rRi
<9 A A-B B D F G D To 9.0 A-B B C D E F D To 13.5 B B-C C D D E D
> 13.5 C C-D D D D D D Table 1-2 Limerick (Tower 1)
- .... *.* :.....i:
i::~i::* .
~.":
- ~i:i~ ... ........ .* - .. . .. . .. . ..d*
A < -2.5 25 B -2.5 to -2.3 20 C -2.2 to -2.0 15 D -1.9 to -0.7 10 E -0.6 to +1.9 5 F +2.0 to +5.2 2.5 G > +5.2 1.7 Table 1-3 Peach Bottom (Tower 2)
A < -2.9 25 B -2.9 to -2.7 20 C -2.6 to -2.4 15 D -2.3 to -0.8 10 E -0.7 to +2.3 5 F +2.4 to +6.2 2.5 G > +6.2 1.7
EP-MA-1 10-200 Revision 1 Page 27 of 35 ATTACHMENT 3 SAMPLE DOSE ASSESSMENT REPORT Page 1 of2 Peach Bottom Dose Assessment Method: N'bnitored Release Time: 18:50 Date: 08D9G2002 Relase Path: <RCS>-<DryWell>-<Torus>-<RBCont>- PRF: 0.16
<SB GT>-<MnStack>- <E NV>
Core Damage : 10% Gap Time After S/D (hours): 0:30 Wind Direction (from) : 10 Release Duration (hours): 400 Monitor: Main Stack WRGM Release Height : Elevated Reading (uC Usec) :1.00EE+06 Monitor Reading for GE : 3.32-E+05 Distance Exdernal Bdernal Inhaltion 4 Day 4 Day Thyroid (miles) DDE DDE CEDE Deposition TEDE Dose CDE (mRihr) (mRem) (mRem) DDE (mRem) (mRem)
(mtRem)
S.B. <.1 <.1 2-55E-01 1.82E-01 475E-01 1.18E+01 1.0 1.18E+01 2.58E+01 1.72E-02 1.23E-02 3.21E+02 7.82E+03 1.5 2.22E+01 484E+01 3.23E+02 2.31E+02 6.02E-02 1.47E-f04 2.0 2.28E-,01 497E+01 3.32E+02 2.36E+02 8.18E+02 1.50E-04 2.5 1.84E+01 401E+01 2.68E+02 1.QIE-02 498E+02 1.21E404 3.0 1.58E+01 3.20E+01 2.31E+02 1.64E+02 430E402 1.05E-04 3.5 1.31E+01 2.85E+01 1.91E202 1.36E+02 3.55E+02 8.65E-03 40 1.10E+01 2.40E+01 1.81E202 1.14E-02 2.99E+02 7.28E203 45 9.24E200 2.02E-I'01 1.35E+02 9.60E+01 2.51E+02 6.11E+03 5.0 6.86E'00 1.50E+01 9.Q9E+01 7.12E+01 1.86E202 453E403 6.5 7.33E+00 1.60E+01 1.07E+02 7.61E401 1.99E+02 4.84E403 6.0 6.47E-00 1.41E+01 0.42E-01 6.72E+01 1.76E+02 427E243 8.5 5.72E+00 1.25E-01 8.34E+01 5.9l--01 1.55E402 3.78E-03 7.0 418E200 9.12E"00 6.09E+01 4.34E'01 1.13E+02 2Z776E403 IPAG Exceeded Pd (Miles): TEDE: None CDE(thyroid) :45 miles Page 1 of 2 Peach Bottom DAPAR vl.0
EP-MA-1 10-200 Revision 1 Page 28 of 35 ATTACHMENT 3 SAMPLE DOSE ASSESSMENT REPORT Page 2 of 2 Peach Bottom Dose Assessment Me-thod: tvbnitored Release Time: 16:52 Date: 08f3Q=02 Relase Path: <RCS>-<DryWell>- <Torus>-<RBCont>- PRF: 0.16
<SBGT>-<MnStack>- <ENW Core Damage : 10% Gap Time After S'D (hours):020 Wind Direction (from) :10 Release Duraton (hours): 4:00 Monitor : Main Stack WROM Release Height : Elevated Reading (u CVsec) :1.00WE+05 Monitor Reading for GE : 3.32 +05 Distance External External Inhalation 4 Day 4 Day Thyroid (miles) DDE DDE CEDE Deposition TEDE Dose CDE (mRAhru (mRem] (mRem) DDE (mRem) (mRem)
(mRem) 7.5 3.64E+00 7.95E+00 5.31E401 3.78E401 9.89E+01 2.41E+03 8.0 3.47E200 7.566E-00 5.05E-401 3.60E401 9.40E+01 2.2@E.03 8.5 Z93E+00 a.39E+00 427E+01 3.04E201 7.96E+01 1.94E203 9.0 2.55E.+00 5.55E+00 3.71E401 2.64E+01 8.91E+01 1.68E+03 9.5 2.40E+00 6-24E+00 3.60E+01 2.50E401 6.52E+01 1.92E403 10.0 2.52E-'00 5.51E+00 3.68E-01 2.62E+01 8.85E+01 1.07E203 IPAG Exceeded At (Miles): TEDE: None CDE(thyroid) 45 miles Page 2 of 2 Peach Bottom DAPAR vl.0
EP-MA-110-200 Revision 1 Page 29 of 35 ATTACHMENT 4 SAMPLE PROTECTIVE ACTION RECOMMENDATION (PAR) REPORT Page 1 of I Peach Bottom Dose Based Protective Action Recommendations Time: 12:41 Date: 07118r2002 Sectors to be Evacuated Assessment Method: .*
Monitored Release w.*.',S.
Evacuation Condifions: - -- ,I Adverse StabiliW/ Class:
Wind Direcfio n (from):
Wind Speed (mph):
Release Duraton(hrs):
Generalized Guidance Evacuate when dose is:
- 1) >= 1000 mRemTEDE 6
- 2) >= 5000 mRem Thyroid a Shelter ivhen evawuation is not possible.
Evacuate: All sectors betv&en 0 to 5 wiles, and sectors WSW, W, WNWbatveen 5to 10 miles Affected Area Dose Tables Emergency Lev".-el GENERAL EMERGENCYTfŽ' tEI Ring I 1.15E+05 3.54E+05 Affected Sectors 1"D-2 niesj w Ring 2 8.97E+04 2.77E+05 Adja~er- Sectors Ring 3 2.50E+04 7.72E+04 WSW, WNW fs-famVn eSJ _______ I Group Release Rates (uCi/sec)
Noble Gases Halogens Particulates True [NRC]: 510E07ý 3.83E+05 of 1I Peach Bottom DAPAR vi .0 Page II off Page P each Bottom DAPAR A1.0
EP-MA-1 10-200 Revision 1 Page 30 of 35 ATTACHMENT 5 EPDS RADIOLOGICAL AND METEOROLOGICAL DATA Page 1 of 1 DAPAR input data is obtained through EPDS. Instructions for use of the EPDS system use procedure EP-MA-1 10-100, "ERO Computer Applications".
The EPDS menu contains a DAPAR screen selection:
STEP 1: Using the mouse, MOVE the arrow to the menu bar STEP 2: CLICK on station of interest STEP 3: CLICK on unit of interest STEP 4: SCROLL down to UDAPAR".
STEP 5: CLICK on UDAPAR"
EP-MA-110-200 Revision 1 Page 31 of 35 ATTACHMENT 6 ADOBE ACROBAT FILE SAVING Page 1 of 2 STEP 1: From the DAPAR PAR report tool bar left mouse click on "File", scroll down left mouse click on print. The following text box appears:
lbalt ý Exerciae----
STEP 2: SAVE report in appropriate file:
, If this is a drill, then SAVE the dose projection in the "Drills and Exercises" folder in the site common drive.
- If this is a real event, then SAVE the dose projection in the "Real Event" folder in the site common drive.
The common drive paths are:
Limerick Generating Station (LGS):
\\PECO\.PBS2_DATAl .PBSSRVS.PBS.PECO\EPDAPAR Peach Bottom Atomic Power Station (PBAPS):
\\PECO\.PBS2_DATA1 .PBSSRVS.PBS.PECO\EPDAPAR STEP 3: If the assigned Dose Assessment Computer cannot access the program, then PERFORM the following:
- 1. TYPE in a file name
- 2. SAVE file type as PDF
- 3. Left mouse CLICK on the "Save" command button NOTE: The dose projection should appear as an Adobe PDF file.
EP-MA-1 10-200 Revision 1 Page 32 of 35 ATTACHMENT 6 ADOBE ACROBAT FILE SAVING Page 2 of 2 STEP 4: Ifthe Adobe PDF does not appear, then left mouse CLICK on the Adobe icon on the bottom of the screen.
- 1. Left mouse CLICK on the Abobe print button from the tool bar
- 2. When the adobe 'Print" box appears, left mouse CLICK on the printer "Name" drop down menu arrow.
- 3. Scroll down and HIGHLIGHT the desired printer
- 4. When the desired printer appears in the "Name" field, left mouse CLICK "OK" command button to print.
STEP 5: Left mouse CLICK the X in the upper right hand comer to return to the DAPAR PAR report.
EP-MA-1 10-200 Revision 1 Page 33 of 35 ATTACHMENT 7 DAPAR INPUT SHEET Page I of I Date: / I Time: Station / Unit:_______________
I OBTAIN FROM: CR (STA/IA) / TSC (Ops. Communicator)I EOF(OperationsAdvisor) r 'New"' :. -:.:.:cc.:.. :+:./Y .u.:.,v.::
RELEASE POINT W1: LIMERICK: PEACH BOTTOM:
[jNorth Stack [ ] Main Stack
[]South Stack Vent Stack
[ UNMONITORED [ Torus Hard Pipe Vent
[ UNMONITORED DESCRIBE FROM RPV TO RELEASE POINT:
RELEASE DURATION: [] No Release In Progress START TIME: ISTOP TIME:_ Total Duration: _hrs SIG PRESSURE: pslg I NO. SRVs OPEN: I PORV OPEN: r ]YES I r I NO RXPOWER: % I RXTRIP at: hrs. I ATWAS: r]YES I [INO rINO I [IYES-REASON:
SPRAYS: [I ON I r I HOLDUPTIME:[r24HRS D UP TIME: r. I<HR i / r1.24HRS rNOTAPPLICA .12-24.HRS
[ ] BYPASSED I r I SATURATED I TI SUBCOOLED
[IFILTERS WORKING I] f FILTERS NOT WORKING mm f ]SECONDARY BOILING I [ SECONDARY SOLID I mm r I SECONDARY DRY OBTAIN FROM: CR (STA/IA) / TSC (Core/HydraulicEngr.) / EOF (TechncialAdvisor) 0 REACTOR CORE ACCIDENT 0 SPENT FUEL ACCIDENT TYPE OF DAMAGE: O GAP I O MELT FUEL TYPE: 0 NEW I 0 OLD AMOUNT OF DAMAGE: % FUEL STATUS: 0 UNDER WATER I 0 DRY OTHER:
EP-MA-1 10-200 Revision I Page 34 of 35 ATTACHMENT 8 DAPAR BRP PARAMETER REPORT - FULL ASSESSMENT (EXAMPLE)
Page 1 of 2 NOTE: "QUICK ASSESSMENT" Report also provided.
DAPAR BRP PARAWETER REPORT- FULL ASSESSMENT SITE LIMERICK STATION Di Aug 09.2002 Tirm 0S:19Y1 PMI Release PmL'wa Ck n ib ABCh*CD 0-U0 hur EN Plutm eIL rm 37.8 cum Ti'naAfte'SJD OI0oars.
SOURCE TERM MET DATA E3 RacorCore Ac;ident Whd Sued 1 miklstur Type oarDfD2 0 GS p 0 Mittk WhdDire.bin 1idegree Arnaumtaa tDm~ag 10% Delb T I Sflbi.,*yCks, E o3 Spent Fuel Accident Rel2as Du'abq &W hours rdalTrYP 0 N m 0 Old Rh R 1 A9EE4 09cq mage.
rmwl&~Sta. 0 Underwater 0 Dry Win~ler~onqljon- Adverse o Baclkwmah Damin Spectrum RELEASE CONCENTRATIONS (uCi/co) RELEASE%
Nobe Gas= alogcns Particulat-m Nobla jaw-5 Halogens
.SME-O3 1.19r-0S 2.93 E-07 99M22% 0.2D2 Rediction Factors Dr-yIll Cc-tainmert Vy'tWell Reductions R Bcldg 16 Cant h mae sp gy 'orr 6 B,'pased G Wald up Time r2 &lur O Caw hmeart Sp Wf'ON' 0 O -%tatcd 2-2 2 s4aars.
W RIdaoupTine: c21laur 0 0 :Subcacld b2,. 4aur s 0 2 - 2&Hoam=
o ~it 'lou's SBDT Filter Reduoticss RERS Filter Reduoticns o riLers Not Woking 0 riLers Nat Woraiiu o riterswo~rti, 0 ril~ers.Wortig TOTAL PRF 001 Page 1 of 2 UMERICKDAPAR vl.0
EP-MA-1 10-200 Revision 1 Page 35 of 35 ATTACHMENT 8 DAPAR BRP PARAMETER REPORT - FULL ASSESSMENT (EXAMPLE)
Page 2 of 2 DAPAR BRP PARAMETER REPORT-FULL ASSESSMENT ASSESSMENT NE"ThOD 1UMonitorad Rahaw Maqiar NorthtSaC RE R4drng 1111111 uCnac o3 Connainane L*a khagdFailu ra o Leatmga % per d;2y o rklurcto abwct1e C0pe dmy) o C '*.rphi" rajildr (100% in 1 hCaiT1 o3 Field Tea Analnsis 0 Su*u*ry Dawnwimd LavaI (rn lr)
Cranwild SurveyTime OSmpl2 Downwihd SuiwyTime C r-swird. riculd xo
[o RIc4lnc PointSamplas rklw R~te I
Page 2 of 2 UMERI CK DAPAR vl.0 Page 2 of 2 UMERICKDAPAR vl.0
ATTACHMENT 2 LIMERICK GENERATING STATION, UNITS 1 & 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 & 3 Docket Nos. 50-352 50-353 50-277 50-278 License Nos. NPF-39 NPF-85 DPR-44 DPR-56 EMERGENCY PROCEDURES REPORT INDEXES
4',
11/19/2002 PAGE LIMERICK GENERATING STATION PROCEDURE INDEX REPORT:
CURR DOC PROC REV EFFECTIVE RESP SYSTEM FAC TYPE TYPE PROCEDURE NUMBER NBR TITLE DATE GROUP NBR LG PROC EP EP-AA-I 10 0003 ASSESSMENT OF EMERGENCIES 08/30/02 LG PROC EP EP-AA-110-301 0000 CORE DAMAGE ASSESSMENT (BWR) 08/30/02 LG PROC EP EP-AA-110-302 0000 CORE DAMAGE ASSESSMENT (PWR)
LG PROC EP EP-AA-111 0004 EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS 08/30/02 LG PROC EP EP-AA-112 0006 EMERGENCY RESPONSE ORGANIZATION (ERO)/EMERGENCY RESPONSE 08/30/02, FACILITY (ERF) ACTIVATION AND OPERATION LG PROC EP EP-AA-112-100 0004 CONTROL ROOM OPERATIONS 08/30/02 LG PROC EP EP-AA-112-200 0003 TSC ACTIVATION AND OPERATION 08/30/02 LG PROC EP EP-AA-112-201 0000 TSC COMMAND AND CONTROL 08/30/02 LG PROC EP EP-AA-112-202 0000 TSC FACILITY SUPPORT GROUP 08/30/02 LG PROC EP EP-AA-112-203 0000 TSC OPERATION GROUP 08/30/02 LG PROC EP EP-AA-112-204 0000 TSC TECHNICAL SUPPORT GROUP 08/30/02 LG PROC EP EP-AA-112-205 0000 TSC MAINTENANCE GROUP 08/30/02 LG PROC EP EP-AA-112-206 0000 TSC RADIATION PROTECTION/CHEMISTRY GROUP 08/30/02 LG PROC EP EP-AA-112-300 0003 OPERATIONS SUPPORT CENTER ACTIVATION AND OPERATION 08/30/02 LG PROC EP EP-AA-112-400 0003 EMERGENCY OPERATIONS FACILITY ACTIVATION AND OPERATION 08/30/02 LG PROC EP EP-AA-112-401 0000 NUCLEAR DUTY OFFICER (NDO) 08/30/02 LG PROC EP EP-AA-112-402 0000 EOF COMMAND AND CONTROL 08/30/02 LG PROC EP EP-AA-1 12-403 0000 EOF LOGISTICS SUPPORT GROUP 08/30/02 LG PROC EP EP-AA-112-404 0000 EOF TECHNICAL SUPPORT GROUP 08/30/02 LG PROC EP EP-AA-112-405 0000 EOF PROTECTIVE MEASURES GROUP 08/30/02 LG PROC EP EP-AA-112-500 0004 EMERGENCY ENVIRONMENTAL MONITORING 08/30/02 LG PROC EP EP-AA-112-600 0004 JOINT PUBLIC INFORMATION CENTER (JPIC) ACTIVATION 08/30/02 LG PROC EP EP-AA-112-601 0000 EMERGENCY NEWS CENTER (ENC) OPERATIONS 08/30/02 LG PROC EP EP-AA-112-602 0000 JPIC ACTIVATION AND OPERATION 08/30/02 LG PROC EP EP-AA-113 0004 PERSONNEL PROTECTIVE ACTIONS 08/30/02 LG PROC EP EP-AA-114 0003 NOTIFICATIONS 08/30/02 LG PROC EP EP-AA-115 0001 RECOVERY FROM A CLASSIFIED EVENT 08/30/02 LG PROC EP EP-AA-120 0000 EMERGENCY PLAN ADMINISTRATION LG PROC EP EP-AA-120-1001 0002 10 CFR 50.54(Q) CHANGE EVALUATION 10/09/02 LG PROC EP EP-AA-120-1002 0000 STORM/EVENT RESTORATION PROC 10/09/02 LG EP EP-AA-122 0002 DRILLS AND EXERCISES 10/09/02 LG PROC EP EP-AA-122-1001 0001 DRILL DEVELOPMENT, CONDUCT AND EVALUATION 10/09/02 LG PROC EP EP-AA-122-1002 0001 EXERCISE DEVELOPMENT, CONDUCT AND EVALUATION 10/09/02 LG PROC EP EP-AA-122-1003 0001 SCHEDULING OF DRILLS AND EXERCISES PROC 10/09/02 LG EP EP-AA-122-1004 0001 DEMONSTRATION CRITERIA 10/09/02 LG PROC EP EP-AA-123 0002 COMPUTER PROGRAMS LG PROC 11/05/02 EP EP-AA-124 0000 INVENTORIES AND SURVEILLANCES LG PROC EP EP-AA-125 0000 EMERGENCY PREPAREDNESS SELF EVALUATION PROCESS LG PROC EP EP-AA-125-1001 0000 EP PERFORMANCE INDICATOR GUIDANCE LG PROC EP EP-AA-125-1002 0000 ERO PERFORMANCE - PERFORMANCE INDICATORS GUIDANCE LG PROC EP EP-C-1-2 0003 DEVELOPMENT AND MAINTENANCE OF THE NUCLEAR EMERGENCY 08/06/96 PLAN AND EMERGENCY RESPONSE PROCEDURES CANCELLED LG PROC EP EP-C-2 0008 EMERGENCY PREPAREDNESS CORRECTIVE ACTION PROCESS 07/24/01 SUPERCEDED BY LS-AA-125 LG PROC EP EP-C-2-1 0001 IFA FOR ACTION ITEM TRACKING SYSTEM 03/10/97 CANCELLED LG PROC EP EP-C-2-2 0001 ACTION/REQUEST EVALUATION NUMBERS AND TREND CODES 07/20/99 DELETED
11/19/2002 PAGE 2 LIMERICK GENERATING STATION PROCEDURE INDEX REPORT:
CURR DOC PROC REV EFFECTIVE RESP SYSTEM FAC TYPE TYPE PROCEDURE NUMBER NBR TITLE DATE GROUP NBR LG PROC EP EP-C-3-1 0000 DEVELOPMENT AND MAINTENANCE OF THE EMERGENCY RESPONSE FACILITIES 07/20/98 AND EQUIPMENT (ERF/E) PROGRAM CANCELLED LG PROC EP EP-C-4-1 0000 FLOWCHART FOR THE DESIGNATION, TRAINING AND MAINTENANCE OF 03/10/97 NUCLEAR ERO CANCELLED LG PROC EP EP-C-5-1 0000 INTERFACE AGREEMENT FOR OFFSITE ORGANIZATION MATRIX REVIEW 03/10/97 CANCELLED LG PROC EP EP-C-5-2 0000 INTERFACE AGREEMENT MATRIX FOR OFFSITE ORGANIZATIONS 04/10/00 CANCELLED LG PROC EP EP-C-6 0004 PREPARATION, CONDUCT, AND EVALUATION OF EMERGENCY RESPONSE 02/26/02 DRILLS AND EXCERCISES - SUPERCEDED BY EP-MA-122 LG PROC EP EP-C-6-1 0000 DRILL OBJECTIVES 03/10/97 CANCELLED LG PROC EP EP-C-6-2 0000 ANNUAL EXCERCISE SCENARIO SUBMITTAL GUIDELINES 03/10/97 CANCELLED LG PROC EP EP-C-6-3 0000 SCENARIO MANUAL FORMAT 03/10/97 CANCELLED LG PROC EP EP-C-6-4 0000 DRILL ACTIVITY CHECKLIST 03/10/97 CANCELLED LG PROC EP EP-C-6-5 0000 DRILL REPORT FORMAT 03/10/97 CANCELLED LG PROC EP EP-C-7-1 OOOO IFA FOR ROUTINE ADMINISTRATION AND TESTING 03/10/97 CANCELLED LG PROC EP EP-C-7-2 0000 IFA FOR EMERGENCY SIREN MAINTENANCE 03/10/97 CANCELLED LG PROC EP EP-MA-110-100 0000 ERO COMPUTER APPLICATIONS LG PROC EP EP-MA-110-200 0001 DOSE ASSESSMENT 08/30/02 LG PROC EP EP-MA-112-406 0000 MAROG OFFSITE LIAISONS, 11/18/02 LG PROC EP EP-MA-113-100 0000 ASSEMBLY AND SITE EVACUATION 08/30/02 LG PROC EP EP-MA-114-100 0001 MAROG NOTIFICATIONS 08/30/02 LG PROC EP EP-MA-122 0000 EXERCISES AND DRILLS 10/28/02 LG PROC EP EP-MA-122-1001 0002 DRILL DEVELOPMENT, CONDUCT AND EVALUATION 02/26/02 SUPERCEDED BY EP-AA-122-1001 10/09/02 LG PROC EP EP-MA-122-1002 0002 EXERCISE DEVELOPMENT, CONDUCT AND EVALUATION SUPERCEDED BY EP-AA-122-1002 10/09/02 LG PROC EP EP-MA-122-1003 0000 SCHEDULING OF DRILLS AND EXERCISES SUPERCEDED BY EP-AA-122-1003 10/09/02 LG PROC EP EP-MA-122-1004 0000 DEMONSTRATION CRITERIA SUPERCEDED BY EP-AA-122-1004 10/09/02 LG PROC EP EP-MA-125-1003 0001 COLLECTION AND EVALUATION OF DATA FOR INDICATOR R.EP.02, "EMERGENCY RESPONSE ORGANIZATION PARTICIPATION" 10/07/02 LG PROC EP EP-1O0 0003 CANCELLED 4/03/92 (SUPERCEDED BY ERP-200)
LG PROC EP EP-100-1 APP. 0003 CANCELLED 04/03/92 (SUPERCEDED BY ERP-200 APP.1)
LG PROC EP EP-101 0013 CANCELLED 04/03/92 (SUPERCEDED BY ERP-101)
LG PROC EP EP-102 0015 CANCELLED INCORPORATED INTO EP1O0 &EP112 LG PROC EP EP-102 APP.1 LWE 0010 CANCELLED INCORPORATED INTO EPlO0 & EP112 LG PROC LWE EP EP-103 0018 CANCELLED INCORPORATED INTO EP1O0 & EP112 LG PROC LWE EP EP-103 APP.1 0009 CANCELLED INCORPORATED INTO EPIOO & EP112 LG PROC EP LWE EP-104 0017 CANCELLED INCORPORATED INTO EPIO0 & EP112 LWE
11/19/2002 PAGE 3 LIMERICK GENERATING STATION PROCEDURE INDEX REPORT:
CURR DOC PROC REV EFFECTIVE RESP SYSTEM FAC TVPE TYPE PROCEDURE NUMBER NBR TITLE DATE GROUP NBR LG PROC EP EP-104 APP. 1 0009 CANCELLED INCORPORATED INTO EPIO0 & EP112 LWE LG PROC EP EP-105 0017 CANCELLED INCORPORATED INTO EPIO0 & EP112 LWE LG PROC EP EP-105 APP. 1 0009 CANCELLED INCORPORATED INTO EPIO0 & EP112 LG LWE PROC EP EP-106 0009 CANCELLED 04/03/92 (SUPERCEDED BY ERP-106)
LG PROC EP EP-1 10 0015 CANCELLED 04/03/92 LG PROC EP EP-1 12 0006 CANCELLED 04/03/92 (SUPERCEDED BY ERP-110)
LG PROC EP EP-120 0009 CANCELLED 04/03/92 (SUPERCEDED BY ERP-C-12 00)
LG PROC EP EP-201 0012 CANCELLED (4/3/92) INCORPORATED INTO ERP-B O0 LG PROC EP EP-202 0012 CANCELLED 04/03/92 (SUPERCEDED BY ERP-230)
LG PROC EP EP-203 0012 CANCELLED 04/03/92 (SUPERCEDED BVERP-C-120(0)
LG PROC EP EP-204 0001 CANCELLED(08/20/90) LWE LG PROC EP EP-20B 0015 CANCELLED 04/03/92 (SUPERCEDED BY ERP-500)
LG PROC EP EP-210 0016 CANCELLED (4/3/92) INCORPORATED INTO ERP-31O0 LG PROC EP EP-211 0009 CANCELLED (4/3/92) INCORPORATED INTO ERP-3*40 LG PROC EP EP-220 0000 CANCELLED LG PROC EP EP-221 LWE 0000 CANCELLED LG PROC EP EP-222 LWE 0000 CANCELLED LG PROC EP EP-225 CANCELLED 04/03/92 (SUPERCEDED BY ERP-700) LWE 0003 LG PROC EP EP-230 0015 CANCELLED 04/03/92 (SUPERCEDED BY ERP-400)
LG PROC EP EP-231 0019 CANCELLED (3/15/91)
LG PROC EP EP-232 0000 CANCELLED LG PROC EP EP-233 CANCELLED (3/22/91) LWE 0010 LG PROC EP EP-234 0010 CANCELLED (3/22/91)
LG PROC EP EP-235 0009 CANCELLED (3/15/91)
LG PROC EP EP-236 0007 CANCELLED (3/15/91)
LG PROC EP EP-237 0013 CANCELLED (3/13/91)
LG PROC EP EP-238 0007 CANCELLED (3/15/91)
LG PROC EP EP-240 0000 CANCELLED LG PROC EP EP-241 0014 CANCELLED 04/03/92 (SUPERCEDED BY ERP-410) LWE LG PROC EP EP-242 0007 CANCELLED 04/03/92 (SUPERCEDED BY ERP-420)
LG PROC EP EP-243 0012 CANCELLED 04/03/92 (SUPERCEDED BY ERP-430)
LG PROC EP EP-244 0005 CANCELLED 04/03/92 (SUPERCEDED BY ERP-440)
LG PROC EP EP-250 0009 CANCELLED (4/3/92) INCORPORATED INTO ERP-6(O0 LG PROC EP EP-251 0005 CANCELLED (4/3/92) INCORPORATED INTO ERP-6120 LG PROC EP EP-252 0016 CANCELLED 04/03/92 (SUPERCEDED BY ERP-500)
LG PROC EP EP-253 0000 CANCELLED LG PROC EP EP-254 CANCELLED (4/3/92) INCORPORATED INTO ERP-6 30 LWE 0005 LG PROC EP EP-255 0005 CANCELLED (4/3/92) INCORPORATED INTO ERP-2 60 LG PROC EP EP-256 0001 CANCELLED (09/26/91)
LG PROC EP EP-257 0002 CANCELLED (09/26/91)
LG PROC EP EP-260 0004 CANCELLED LG PROC EP EP-261 CANCELLED 04/03/92 (SUPERCEDED BY ERP-800) LWE 0010 LG PROC EP EP-272 0000 CANCELLED LG PROC EP EP-273 CANCELLED LWE 0000 LG PROC EP EP-275 CANCELLED LWE 0000 LG PROC EP EP-276 0013 CANCELLED(11/19/90) LWE LG PROC EP EP-277 0021 CANCELLED(11/19/90) LWE LG PROC EP EP-278 0015 CANCELLED LWE LG PROC EP EP-279 0020 CANCELLED(11/13/90) LWE LG PROC EP EP-280 0021 CANCELLED(11/13/90)
11/19/2002 PAGE 4 LIMERICK GENERATING STATION P PROCEDURE INDEX REPORT:
CURR DOC PROC REV EFFECTIVE RESP SYSTEM FAC TYPE TYPE PROCEDURE NUMBER NBR TITLE DATE GROUP NBR LG PROC EP EP-282 0016 CANCELLED (8/13/91)
LG PROC EP EP-284 0013 CANCELLED (8/13/91)
LG PROC EP EP-287 0006 CANCELLED - 11/02/88 LWE LG PROC EP EP-291 0026 CANCELLED 04/03/92 (SUPERCEDED BY ERP-140)
LG PROC EP EP-292 0018 CANCELLED (4/24/90) LWE LG PROC EP EP-294 0020 CANCELLED(6/29/90)INCORP. INTO EP-305 LWE LG PROC EP EP-301 0003 CANCELLED INCORPORATED INTO EP305 LWE LG PROC EP EP-302 0002 CANCELLED 04/03/92 (SUPERCEDED BY ERP-800)
LG PROC EP EP-303 0004 CANCELLED 04/03/92 (SUPERCEDED BY ERP-120)
LG PROC EP EP-304 0007 CANCELLED 04/03/92 (SUPERCEDED BY ERP-120)
LG PROC EP EP-305 0010 CANCELLED 04/03/92 (SUPERCEDED BY (ERP-120)
LG PROC EP EP-306 0006 CANCELLED 04/03/92 (SUPERCEDED BY ERP-500)
LG PROC EP EP-307 0004 CANCELLED 04/03/92 (SUPERCEDED BY ERP-C-1500)
LG PROC EP EP-312 0011 CANCELLED (4/3/92) INCORPORATED INTO ERP-350 LG PROC EP EP-313 0007 CANCELLED (4/3/92) INCORPORATED INTO ERP-660 LG PROC EP EP-314 0003 CANCELLED(01/03/91)
LG PROC EP EP-315 0009 CANCELLED LWE LG PROC EP EP-316 0004 CANCELLED LWE LG PROC EP EP-317 0014 CANCELLED (4/3/92) INCORPORATED INTO ERP-370 LG PROC EP EP-318 0004 CANCELLED (4/3/92) INCORPORATED INTO ERP-350 LG PROC EP EP-319 0002 CANCELLED LWE LG PROC EP EP-320 0002 CANCELLED(09/21/90) LWE LG PROC EP EP-321 0003 CANCELLED(09/21/90) LWE LG PROC EP EP-322 0000 CANCELLED(09/21/90) LWE LG PROC EP EP-322 APP.9 0001 CANCELLED(11/05/90) LWE LG PROC EP EP-324 0000 CANCELLED (4/3/92) INCORPORATED INTO ERP-300 LG PROC EP EP-324 APP. 5 0000 CANCELLED (4/3/92) INCORPORATED INTO ERP-300 LG PROC EP EP-324 APP.6 0000 CANCELLED (4/3/92) INCORPORATED INTO ERP-300 LG PROC EP EP-325 0010 CANCELLED (4/3/92) INCORPORATED INTO ERP-370 LG PROC EP EP-327 0002 CANCELLED (4/2/92) INCORPORATED INTO ERP-370 LG PROC EP EP-328 0000 CANCELLED (4/2/92) INCORPORATED INTO ERP-370 LG PROC EP EP-330 0007 CANCELLED (4/2/92) INCORPORATED INTO ERP-640 LG PROC EP EP-333 0002 CANCELLED (4/3/92) INCORPORATED INTO ERP-360 LG PROC EP EP-401 0005 CANCELLED (4/3/92) INCORPORATED INTO ERP-650 LG PROC EP EP-410 0013 CANCELLED 04/03/92 (SUPERCEDED BY ERP-C-1900)
LG PROC EP EP-500 0002 CANCELLED LWE
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11/19/2002 PAGE PROCEDURE INDEX REPORT: PEACH BOTTOM ATOMIC POWER STATION CURR DOC PROC REV FAC TYPE TYPE EFFECTIVE RESP SYSTEM PROCEDURE NUMBER NBR TITLE DATE GROUP NBR PB PROC EP EP-AA-1I000 0013 STANDARIZED RADIOLOGICAL EMERGENCY PLAN PB PROC EP EP-AA-1007 08/30/02 PWE 0002 RADIOLOGICAL EMERGENCY PLAN ANNEX FOR PEACH BOTTOM ATOMIC POWER 11/18/02 PWE STATION PB PROC EP EP-AA-110 0003 ASSESSMENT OF EMERGENCIES PB PROC EP EP-AA-110-301 08/30/02 PWE 0000 CORE DAMAGE ASSESSMENT (BWR) 08/30/02 PB PROC EP EP-AA-111 0004 EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS PWE PB PROC EP EP-AA-112 0006 EMERGENCY RESPONSE ORGANIZATION (ERO)/EMERGENCY RESPONSE 08/30/02 PWE 08/30/02 PWE FACILITY (ERF) ACTIVATION AND OPERATION PB PROC EP EP-AA-112-100 0004 CONTROL ROOM OPERATIONS PB PROC EP EP-AA-112-200 08/30/02 PWE 0003 TSC ACTIVIATION AND OPERATION PB PROC EP EP-AA-112-201 0000 TSC COMMAND AND CONTROL 08/30/02 PWE PB PROC EP EP-AA-112-202 08/30/02 PWE 0000 TSC FACILITY SUPPORT GROUP PB PROC EP EP-AA-112-203 0000 TSC OPERATION GROUP 08/30/02 PWE PB PROC EP EP-AA-112-204 0000 TSC TECHNICAL SUPPORT GROUP 08/30/02 PWE PB PROC EP EP-AA-112-205 08/30/02 PWE 0000 TSC MAINTENANCE GROUP PB PROC EP EP-AA-112-206 08/30/02 PWE 0000 TSC RADIATION PROTECTION/CHEMISTRY GROUP PB PROC EP EP-AA-112-300 0003 OPERATIONS SUPPORT CENTER ACTIVIATION AND OPERATION 08/30/02 PWE PB PROC EP EP-AA-112-400 0003 EMERGENCY OPERATIONS FACILITY ACTIVATION AND OPERATION 08/30/02 PWE PB PROC EP EP-AA-112-401 0000 NUCLEAR DUTY OFFICER (NDO) 08/30/02 PWE PB PROC EP EP-AA-112-402 0000 EOF COMMAND AND CONTROL 08/30/02 PWE PB PROC EP EP-AA-112-403 0000 EOF LOGISTICS SUPPORT GROUP 08/30/02 PWE PB PROC EP EP-AA-112-404 0000 EOF TECHNICAL SUPPORT GROUP 08/30/02 PWE PB PROC EP EP-AA-112-405 0000 EOF PROTECTIVE MEASURES GROUP 08/30/02 PWE PB PROC EP EP-AA-112-500 0004 EMERGENCY ENVIRONMENTAL MONITORING 08/30/02 PWE PB PROC EP EP-AA-112-600 0004 PUBLIC INFORMATION ORGANIZATION ACTIVATION AND OPERATIONS 08/30/02 PWE PB PROC EP EP-AA-112-601 0000 EMERGENCY NEWS CENTER (ENC) OPERATIONS 08/30/02 PWE PB PROC EP EP-AA-112-602 0000 JPIC ACTIVATION AND OPERATION 08/30/02 PWE PB PROC EP EP-AA-113 0004 PERSONNEL PROTECTIVE ACTIONS 08/30/02 PWE PB PROC EP EP-AA-114 0003 NOTIFICATIONS 08/30/02 PWE PB PROC EP EP-AA-115 0001 RECOVERY FROM A CLASSIFIED EVENT 08/30/02 PWE PB PROC EP EP-AA-120-1001 0002 10 CFR 50.54(Q) CHANGE EVALUATION 08/30/02 PWE PB PROC EP EP-AA-120-1002 0000 STORM/EVENT RESTORATION 10/18/02 PWE PB PROC EP EP-AA-121-1001 0002 AUTOMATED CALL-OUT SYSTEM MAINTENANCE 10/18/02 PWE PB PROC EP EP-AA-122 0002 DRILLS AND EXERCISES 10/18/02 PWE PB PROC EP EP-AA-122-1001 0001 DRILL DEVELOPMENT, CONDUCT AND EVALUATION 10/18/02 PWE PB PROC EP EP-AA-122-1002 0001 EXERCISE DEVELOPMENT, CONDUCT AND EVALUATION 10/18/02 PWE PB PROC EP EP-AA-122-1003 0001 SCHEDULING OF DRILLS AND EXERCISES 10/18/02 PWE PB PROC EP EP-AA-122-1004 0001 DEMONSTRATION CRITERIA 10/18/02 PWE PB PROC EP EP-AA-123 0002 COMPUTER PROGRAMS 10/18/02 PWE PB PROC EP EP-C-2 0008 EMERGENCY PREPAREDNESS CORRECTIVE ACTION PROCESS - CANCELLED 11/12/02 PWE REPLACED BY LS-AA-125 07/24/01 PWE PB PROC EP EP-C-2-1 0001 IFA FOR ACTION ITEM TRACKING SYSTEM - CANCELLED - NO REPLACEMENT PB PROC EP EP-C-2-2 0001 ACTION/REQUEST EVALUATION NUMBERS AND TREND CODES CANCELLED - NO 03/10/97 PWE 12/18/98 PWE EWPLACEMENT PB PROC EP EP-C-3-1 EXH 0000 DEVELOPMENT AND MAINTENANCE OF THE EMERGENCY RESPONSE FACILITIES AND EQUIPMENT (ERF/E) PROGRAM 04/17/95 PWE
- CANCELLED - NO REPLACEMENT PB PROC EP EP-C-4-1 0000 FLOWCHART OF DESIGNATION, TRAINING AND MAINTENANCE OF 03/10/97 PWE NUCLEAR ERO CANCELLED - NO REPLACEMENT PB PROC EP EP-C-5-1 0000 INTERFACE AGREEMENT FOR OFFSITE ORGANIZATION MATRIX REVIEW 03/10/97 PWE CANCELLED - NO REPLACEMENT
11/19/2002 PAGE 2 PEACH BOTTOM ATOMIC POWER STATION PROCEDURE INDEX REPORT:
CURR DOC PROC REV EFFECTIVE RESP SYSTEM FAC TYPE TYPE PROCEDURE NUMBER NBR TITLE DATE GROUP NBR PB PROC EP EP-C-5-2 0000 INTERFACE AGREEMENT MATRIX FOR OFFSITE ORGANIZATIONS CANCELLED 04/10/00 PWE NO REPLACEMENT CANCELLED - NO REPLACEMENT PB PROC EP EP-C-6 0004 PREPARATION, CONDUCT, AND EVALUATION OF EMERGENCY RESPONSE 02/21/02 PWE DRILLS AND EXCERCISES CANCELLED - REPLACED BY EP-MA-122 PB PROC EP EP-C-6-1 0000 DRILL OBJECTIVES - CANCELLED - NO REPLACEMENT 03/10/97 PWE PB PROC EP EP-C-6-2 0000 ANNUAL EXCERCISE SCENARIO SUBMITTAL GUIDELINES - CANCELLED - NO 03/10/97 PWE REPLACEMENT PB PROC EP EP-C-6-3 0000 SCENARIO MANUAL FORMAT - CANCELLED - NO REPLACEMENT 03/10/97 PWE PB PROC EP EP-C-6-4 0000 DRILL ACTIVITY CHECKLIST - CANCELLED - NO REPLACEMENT 03/10/97 PWE PB PROC EP EP-C-6-5 0000 DRILL REPORT FORMAT - CANCELLED - NO REPLACEMENT 03/10/97 PWE PB PROC EP EP-C-7-1 0000 IFA FOR ROUTINE ADMINISTRATION & TESTING CANCELLED - NO 03/10/97 PWE REPLACEMENT PB PROC EP EP-C-7-2 0000 IFA FOR EMERGENCY SIREN MAINTENANCE CANCELLED - NO REPLACEMENT 03/10/97 PWE PB PROC EP EP-MA-110-100 0000 ERO COMPUTER APPLICATIONS 08/30/02 PWE PB PROC EP EP-MA-110-200 0001 DOSE ASSESSMENT 11/18/02 PWE PB PROC EP EP-MA-112-406 0000 MAROG OFFSITE LIASONS 08/30/02 PWE PB PROC EP EP-MA-113-100 0000 ASSEMBLY AND SITE EVACUATION 08/30/02 PWE PB PROC EP EP-MA-114-100 0001 MAROG NOTIFICATIONS 10/18/02 PWE PB PROC EP EP-MA-122 0000 EXERCISE AND DRILLS - CANCELLED REPLACED BY EP-AA-122 10/18/02 PWE PB PROC EP EP-MA-122-1001 0002 DRILL DEVELOPMENT, CONDUCT AND EVALUATION - CANCELLED REPLACED 10/18/02 PWE BY EP-AA-122-1001 PB PROC EP EP-MA- 122-1002 0002 EXERCISE DEVLOPMENT, CONDUCT AND EVALUATION - CANCELLED REPLACED 10/18/02 PWE BY EP-AA-122-1002 PB PROC EP EP-MA-122-1003 0000 SCHEDULING OF DRILLS AND EXERCISES - CANCELLED REPLACED BY 10/18/02 PWE EP-AA-122-1003 PB PROC EP EP-MA-122-1004 0000 DEMONSTRATION CRITERIA - CANCELLED REPLACED BY EP-AA-122-1004 10/18/02 PWE PB PROC EP EP-MA-125-1003 0001 COLLECTION AND EVALUATION OF DATA FOR INDICATOR R.EP.02, 10/18/02 PWE "EMERGENCY RESPONSE ORGANIZATION PARTICIPATION-'
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