ML023310204

EP-MA-110-200, Revision 1, Dose Assessment

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 Kennett Square, PA 19348 www exeloncorp corn Nuclear 1 OCFR50, 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.

License Nos.

50-352 50-353 50-277 50-278 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.

.Curie (Ci): A unit of radioactivity equal to 3.7E+10 disintegrations per second.

2.6.

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.

"* Containment Leakage / 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:

"a Increase 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.

Figure 1-2 2

t",W a

rm i StatIon

.<\\,.*:'.

.0.1 S

Do se,,,eat n

dt P..

....,,.m:.

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 Meteorological Data - 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 Conditions button 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 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.

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.

4.4.

Applicable only to LGS

EP-MA-1 10-200 Revision 1 Page 12 of 35

2.

SELECT Spent Fuel Accident if the release is caused by damage to the spent fuel.

A.

Under "Fuel Type", CHOOSE between New Fuel or 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

2.

DETERMINE Containment I Drywell holdup time, and SELECT the appropriate condition. (Figure 7)

3.

If a release through the Aux Bldg or Rx Bldg., then DETERMINE the building holdup time. (Figure 8)

Fiaure 7 Reao Bld Reduction Figure 8

4.

SELECT Torus - PBAPS (Figure 9a) or Wetwell - LGS (Figure 9b):

I Containment Reductions

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)

Figure 1Oc (PBAPS) 4.4.3.

ENTER Meteorological Data - Enter the appropriate data from plant instruments.

4.4.4.

Assessment Methods - CHOOSE the appropriate assessment method based on available inputs. Assessment methods:

1.

Monitored Release - 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.

Containment Leakage - SELECT this method for containment failure scenarios.

GO TO Section 4.6.

3.

Field Team Data - SELECT this method if field 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.

Filter Reductions

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 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.

Failure to 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.

Catastrophic Failure - 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.

3.

SELECT the PAR button to view PAR form - GO TO section 4.9.

4.6.

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 Print button 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 Release Point Analysis (Figure 14)

Figure 14 4.8.1.

ENTER the known Isotopic Concentration for 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 Print button 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.

3.

SELECT the PAR button to view PAR form - GO TO section 4.9.

4.8.

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.

Figure 15 l

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.

(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 Print to 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 Exelon DAPAR Program Software Requirements Specification 6.2.

Commitments - None 6.1.

.jii I F-Group Release Rat-es-J-777tj

EP-MA-1 10-200 Revision 1 Page 23 of 35

7.

ATTACHMENTS 7.1., Basic Program Flow Diagram 7.2., Determination of Stability Class 7.3., Sample Dose Assessment Report 7.4., Sample Protective Action Recommendation (PAR) Report 7.5., EPDS Radiological and Meteorological data 7.6., ADOBE Acobat File Saving 7.7., DAPAR Input Sheet 7.8., 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

$ufacr f...'..........

I Wind Daytime CditiOns Speed.

rrnb)

I Nighttime CQnI1tIQns 1

.......... I sui~r Sp~at Wit~

Heavy Ti vfas'<1 Hay C~~~~ear~

~

~

~~

Ovrcs or,,k

~I tot ludOecs 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) d*

.....i:

i::~i ::* :~i:i~ ~.":

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

Adja~er-Sectors WSW, WNW True [NRC]:

Ring 2 8.97E+04 2.77E+05 Ring 3 2.50E+04 7.72E+04 fs-famVn eSJ I

Group Release Rates (uCi/sec)

Noble Gases Halogens Particulates 510E07ý 3.83E+05 Page I of I Peach Bottom DAPAR vi.0 Page I off 1 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:

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.

lbalt ý Exerciae----

EP-MA-1 10-200 Revision 1 Page 32 of 35 ATTACHMENT 6 ADOBE ACROBAT FILE SAVING Page 2 of 2 STEP 4:

If the 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:_______________

OBTAIN FROM: CR (STA/IA) / TSC (Ops. Communicator) I EOF (Operations Advisor) r 'New"'

+:./Y

-:.:.:cc.:..

.u.:.,v.::

RELEASE POINT W1:

LIMERICK:

[jNorth Stack

[]South Stack

[

UNMONITORED DESCRIBE FROM RPV TO RELEASE POINT:

PEACH BOTTOM:

[ ] Main Stack Vent Stack

[ Torus Hard Pipe Vent

[

UNMONITORED 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

.12-24.HRS

/ r1.24HRS rNOTAPPLICA

[ ] BYPASSED I r I SATURATED I TI SUBCOOLED

[I FILTERS WORKING I f

]

FILTERS NOT WORKING f ]SECONDARY BOILING I [ SECONDARY SOLID I r I SECONDARY DRY OBTAIN FROM: CR (STA/IA) / TSC (Core/Hydraulic Engr.) / EOF (Techncial Advisor) 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:

mm mm I

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 37.8 rm 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 R h 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

&lu r O Caw hmeart Sp Wf'ON' O -%tatcd 0 2-2 2 s4aars.

W RIdaoupTine: c21laur 0 :Subcacld 0 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 Page 2 of 2 UMERICKDAPAR vl.0 ASSESSMENT NE"ThOD 1U Monitorad Rahaw Maqiar NorthtSaC RE R4drng 1111111 uCnac o3 Connainane L*a khagdFailu ra o Leatmga

% per d;2y o rklurc to 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

ATTACHMENT 2 LIMERICK GENERATING STATION, UNITS 1 & 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 & 3 Docket Nos.

License Nos.

50-352 50-353 50-277 50-278 NPF-39 NPF-85 DPR-44 DPR-56 EMERGENCY PROCEDURES REPORT INDEXES

11/19/2002 PROCEDURE INDEX REPORT:

LIMERICK GENERATING STATION PAGE DOC PROC FAC TYPE TYPE LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP PROCEDURE NUMBER EP-AA-I 10 EP-AA-110-301 EP-AA-110-302 EP-AA-111 EP-AA-112 EP-AA-112-100 EP-AA-112-200 EP-AA-112-201 EP-AA-112-202 EP-AA-112-203 EP-AA-112-204 EP-AA-112-205 EP-AA-112-206 EP-AA-112-300 EP-AA-112-400 EP-AA-112-401 EP-AA-112-402 EP-AA-1 12-403 EP-AA-112-404 EP-AA-112-405 EP-AA-112-500 EP-AA-112-600 EP-AA-112-601 EP-AA-112-602 EP-AA-113 EP-AA-114 EP-AA-115 EP-AA-120 EP-AA-120-1001 EP-AA-120-1002 EP-AA-122 EP-AA-122-1001 EP-AA-122-1002 EP-AA-122-1003 EP-AA-122-1004 EP-AA-123 EP-AA-124 EP-AA-125 EP-AA-125-1001 EP-AA-125-1002 EP-C-1-2 EP-C-2 EP-C-2-1 EP-C-2-2 CURR REV NBR TITLE 0003 0000 0000 0004 0006 0004 0003 0000 0000 0000 0000 0000 0000 0003 0003 0000 0000 0000 0000 0000 0004 0004 0000 0000 0004 0003 0001 0000 0002 0000 0002 0001 0001 0001 0001 0002 0000 0000 0000 0000 0003 0008 0001 0001 ASSESSMENT OF EMERGENCIES CORE DAMAGE ASSESSMENT (BWR)

CORE DAMAGE ASSESSMENT (PWR)

EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS EMERGENCY RESPONSE ORGANIZATION (ERO)/EMERGENCY

RESPONSE

FACILITY (ERF)

ACTIVATION AND OPERATION CONTROL ROOM OPERATIONS TSC ACTIVATION AND OPERATION TSC COMMAND AND CONTROL TSC FACILITY SUPPORT GROUP TSC OPERATION GROUP TSC TECHNICAL SUPPORT GROUP TSC MAINTENANCE GROUP TSC RADIATION PROTECTION/CHEMISTRY GROUP OPERATIONS SUPPORT CENTER ACTIVATION AND OPERATION EMERGENCY OPERATIONS FACILITY ACTIVATION AND OPERATION NUCLEAR DUTY OFFICER (NDO)

EOF COMMAND AND CONTROL EOF LOGISTICS SUPPORT GROUP EOF TECHNICAL SUPPORT GROUP EOF PROTECTIVE MEASURES GROUP EMERGENCY ENVIRONMENTAL MONITORING JOINT PUBLIC INFORMATION CENTER (JPIC) ACTIVATION EMERGENCY NEWS CENTER (ENC)

OPERATIONS JPIC ACTIVATION AND OPERATION PERSONNEL PROTECTIVE ACTIONS NOTIFICATIONS RECOVERY FROM A CLASSIFIED EVENT EMERGENCY PLAN ADMINISTRATION 10 CFR 50.54(Q)

CHANGE EVALUATION STORM/EVENT RESTORATION DRILLS AND EXERCISES DRILL DEVELOPMENT, CONDUCT AND EVALUATION EXERCISE DEVELOPMENT, CONDUCT AND EVALUATION SCHEDULING OF DRILLS AND EXERCISES DEMONSTRATION CRITERIA COMPUTER PROGRAMS INVENTORIES AND SURVEILLANCES EMERGENCY PREPAREDNESS SELF EVALUATION PROCESS EP PERFORMANCE INDICATOR GUIDANCE ERO PERFORMANCE -

PERFORMANCE INDICATORS GUIDANCE DEVELOPMENT AND MAINTENANCE OF THE NUCLEAR EMERGENCY PLAN AND EMERGENCY RESPONSE PROCEDURES CANCELLED EMERGENCY PREPAREDNESS CORRECTIVE ACTION PROCESS SUPERCEDED BY LS-AA-125 IFA FOR ACTION ITEM TRACKING SYSTEM CANCELLED ACTION/REQUEST EVALUATION NUMBERS AND TREND CODES DELETED EFFECTIVE RESP SYSTEM DATE GROUP NBR 08/30/02 08/30/02 08/30/02 08/30/02, 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 10/09/02 10/09/02 10/09/02 10/09/02 10/09/02 10/09/02 10/09/02 11/05/02 08/06/96 07/24/01 03/10/97 07/20/99 4',

11/19/2002 PAGE 2

PROCEDURE INDEX REPORT:

LIMERICK GENERATING STATION DOC PROC FAC TYPE TYPE PROCEDURE NUMBER LG PROC EP EP-C-3-1 LG PROC EP EP-C-4-1 LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP-C-5-1 EP-C-5-2 EP-C-6 EP-C-6-1 EP-C-6-2 EP-C-6-3 EP-C-6-4 EP-C-6-5 EP-C-7-1 EP-C-7-2 EP-MA-110-100 EP-MA-110-200 EP-MA-112-406 EP-MA-113-100 EP-MA-114-100 EP-MA-122 EP-MA-122-1001 EP-MA-122-1002 EP-MA-122-1003 EP-MA-122-1004 EP-MA-125-1003 EP-1O0 EP-100-1 APP.

EP-101 EP-102 EP-102 APP.1 EP-103 EP-103 APP.1 EP-104 CURR REV NBR TITLE 0000 DEVELOPMENT AND MAINTENANCE OF THE EMERGENCY RESPONSE FACILITIES AND EQUIPMENT (ERF/E)

PROGRAM CANCELLED 0000 FLOWCHART FOR THE DESIGNATION, TRAINING AND MAINTENANCE OF NUCLEAR ERO CANCELLED 0000 INTERFACE AGREEMENT FOR OFFSITE ORGANIZATION MATRIX REVIEW CANCELLED 0000 INTERFACE AGREEMENT MATRIX FOR OFFSITE ORGANIZATIONS CANCELLED 0004 PREPARATION,

CONDUCT, AND EVALUATION OF EMERGENCY RESPONSE DRILLS AND EXCERCISES -

SUPERCEDED BY EP-MA-122 0000 DRILL OBJECTIVES CANCELLED 0000 ANNUAL EXCERCISE SCENARIO SUBMITTAL GUIDELINES CANCELLED 0000 SCENARIO MANUAL FORMAT CANCELLED 0000 DRILL ACTIVITY CHECKLIST CANCELLED 0000 DRILL REPORT FORMAT CANCELLED OOOO IFA FOR ROUTINE ADMINISTRATION AND TESTING CANCELLED 0000 IFA FOR EMERGENCY SIREN MAINTENANCE CANCELLED 0000 ERO COMPUTER APPLICATIONS 0001 DOSE ASSESSMENT 0000 MAROG OFFSITE LIAISONS, 0000 ASSEMBLY AND SITE EVACUATION 0001 MAROG NOTIFICATIONS 0000 EXERCISES AND DRILLS 0002 DRILL DEVELOPMENT, CONDUCT AND EVALUATION SUPERCEDED BY EP-AA-122-1001 0002 EXERCISE DEVELOPMENT, CONDUCT AND EVALUATION SUPERCEDED BY EP-AA-122-1002 0000 SCHEDULING OF DRILLS AND EXERCISES SUPERCEDED BY EP-AA-122-1003 0000 DEMONSTRATION CRITERIA SUPERCEDED BY EP-AA-122-1004 0001 COLLECTION AND EVALUATION OF DATA FOR INDICATOR R.EP.02, "EMERGENCY RESPONSE ORGANIZATION PARTICIPATION" 0003 CANCELLED 4/03/92 (SUPERCEDED BY ERP-200) 0003 CANCELLED 04/03/92 (SUPERCEDED BY ERP-200 APP.1) 0013 CANCELLED 04/03/92 (SUPERCEDED BY ERP-101) 0015 CANCELLED INCORPORATED INTO EP1O0

&EP112 0010 CANCELLED INCORPORATED INTO EPlO0

& EP112 0018 CANCELLED INCORPORATED INTO EP1O0 & EP112 0009 CANCELLED INCORPORATED INTO EPIOO & EP112 0017 CANCELLED INCORPORATED INTO EPIO0

& EP112 EFFECTIVE DATE 07/20/98 03/10/97 03/10/97 04/10/00 02/26/02 03/10/97 03/10/97 03/10/97 03/10/97 03/10/97 03/10/97 03/10/97 08/30/02 11/18/02 08/30/02 08/30/02 10/28/02 02/26/02 10/09/02 10/09/02 10/09/02 10/09/02 10/07/02 RESP SYSTEM GROUP NBR LWE LWE LWE LWE LWE

11/19/2002 PROCEDURE INDEX REPORT:

LIMERICK GENERATING STATION DOC PROC FAC TVPE TYPE LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP PROCEDURE NUMBER EP-104 EP-105 EP-105 EP-106 EP-1 10 EP-1 12 EP-120 EP-201 EP-202 EP-203 EP-204 EP-20B EP-210 EP-211 EP-220 EP-221 EP-222 EP-225 EP-230 EP-231 EP-232 EP-233 EP-234 EP-235 EP-236 EP-237 EP-238 EP-240 EP-241 EP-242 EP-243 EP-244 EP-250 EP-251 EP-252 EP-253 EP-254 EP-255 EP-256 EP-257 EP-260 EP-261 EP-272 EP-273 EP-275 EP-276 EP-277 EP-278 EP-279 EP-280 APP. 1 APP. 1 CURR REV NBR 0009 0017 0009 0009 0015 0006 0009 0012 0012 0012 0001 0015 0016 0009 0000 0000 0000 0003 0015 0019 0000 0010 0010 0009 0007 0013 0007 0000 0014 0007 0012 0005 0009 0005 0016 0000 0005 0005 0001 0002 0004 0010 0000 0000 0000 0013 0021 0015 0020 0021 TITLE CANCELLED INCORPORATED INTO EPIO0

& EP112 CANCELLED INCORPORATED INTO EPIO0

& EP112 CANCELLED INCORPORATED INTO EPIO0

& EP112 CANCELLED 04/03/92 (SUPERCEDED BY ERP-106)

CANCELLED 04/03/92 CANCELLED 04/03/92 (SUPERCEDED BY ERP-110)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-C-12 CANCELLED (4/3/92) INCORPORATED INTO ERP-B CANCELLED 04/03/92 (SUPERCEDED BY ERP-230)

CANCELLED 04/03/92 (SUPERCEDED BVERP-C-120(

CANCELLED(08/20/90)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-500)

CANCELLED (4/3/92) INCORPORATED INTO ERP-31 CANCELLED (4/3/92) INCORPORATED INTO ERP-3*

CANCELLED CANCELLED CANCELLED CANCELLED 04/03/92 (SUPERCEDED BY ERP-700)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-400)

CANCELLED (3/15/91)

CANCELLED CANCELLED (3/22/91)

CANCELLED (3/22/91)

CANCELLED (3/15/91)

CANCELLED (3/15/91)

CANCELLED (3/13/91)

CANCELLED (3/15/91)

CANCELLED CANCELLED 04/03/92 (SUPERCEDED BY ERP-410)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-420)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-430)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-440)

CANCELLED (4/3/92) INCORPORATED INTO ERP-6(

CANCELLED (4/3/92) INCORPORATED INTO ERP-61 CANCELLED 04/03/92 (SUPERCEDED BY ERP-500)

CANCELLED CANCELLED (4/3/92) INCORPORATED INTO ERP-6 CANCELLED (4/3/92) INCORPORATED INTO ERP-2 CANCELLED (09/26/91)

CANCELLED (09/26/91)

CANCELLED CANCELLED 04/03/92 (SUPERCEDED BY ERP-800)

CANCELLED CANCELLED CANCELLED CANCELLED(11/19/90)

CANCELLED(11/19/90)

CANCELLED CANCELLED(11/13/90)

CANCELLED(11/13/90)

EFFECTIVE RESP SYSTEM DATE GROUP NBR LWE LWE LWE

00)

O0

0)

O0 40 LWE LWE LWE LWE LWE LWE O0 20 30 60 LWE LWE LWE LWE LWE LWE LWE LWE PAGE 3

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 END OF REPORT

11/19/2002 PAGE PEACH BOTTOM ATOMIC POWER STATION PROCEDURE INDEX REPORT:

DOC PROC FAC TYPE TYPE PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP PROCEDURE NUMBER EP-AA-1I000 EP-AA-1007 EP-AA-110 EP-AA-110-301 EP-AA-111 EP-AA-112 EP-AA-112-100 EP-AA-112-200 EP-AA-112-201 EP-AA-112-202 EP-AA-112-203 EP-AA-112-204 EP-AA-112-205 EP-AA-112-206 EP-AA-112-300 EP-AA-112-400 EP-AA-112-401 EP-AA-112-402 EP-AA-112-403 EP-AA-112-404 EP-AA-112-405 EP-AA-112-500 EP-AA-112-600 EP-AA-112-601 EP-AA-112-602 EP-AA-113 EP-AA-114 EP-AA-115 EP-AA-120-1001 EP-AA-120-1002 EP-AA-121-1001 EP-AA-122 EP-AA-122-1001 EP-AA-122-1002 EP-AA-122-1003 EP-AA-122-1004 EP-AA-123 EP-C-2 EP-C-2-1 EP-C-2-2 EP-C-3-1 EXH EP-C-4-1 EP-C-5-1 CURR REV NBR TITLE 0013 STANDARIZED RADIOLOGICAL EMERGENCY PLAN 0002 RADIOLOGICAL EMERGENCY PLAN ANNEX FOR PEACH BOTTOM ATOMIC POWER STATION 0003 ASSESSMENT OF EMERGENCIES 0000 CORE DAMAGE ASSESSMENT (BWR) 0004 EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS 0006 EMERGENCY RESPONSE ORGANIZATION (ERO)/EMERGENCY

RESPONSE

FACILITY (ERF)

ACTIVATION AND OPERATION 0004 CONTROL ROOM OPERATIONS 0003 TSC ACTIVIATION AND OPERATION 0000 TSC COMMAND AND CONTROL 0000 TSC FACILITY SUPPORT GROUP 0000 TSC OPERATION GROUP 0000 TSC TECHNICAL SUPPORT GROUP 0000 TSC MAINTENANCE GROUP 0000 TSC RADIATION PROTECTION/CHEMISTRY GROUP 0003 OPERATIONS SUPPORT CENTER ACTIVIATION AND OPERATION 0003 EMERGENCY OPERATIONS FACILITY ACTIVATION AND OPERATION 0000 NUCLEAR DUTY OFFICER (NDO) 0000 EOF COMMAND AND CONTROL 0000 EOF LOGISTICS SUPPORT GROUP 0000 EOF TECHNICAL SUPPORT GROUP 0000 EOF PROTECTIVE MEASURES GROUP 0004 EMERGENCY ENVIRONMENTAL MONITORING 0004 PUBLIC INFORMATION ORGANIZATION ACTIVATION AND OPERATIONS 0000 EMERGENCY NEWS CENTER (ENC)

OPERATIONS 0000 JPIC ACTIVATION AND OPERATION 0004 PERSONNEL PROTECTIVE ACTIONS 0003 NOTIFICATIONS 0001 RECOVERY FROM A CLASSIFIED EVENT 0002 10 CFR 50.54(Q) CHANGE EVALUATION 0000 STORM/EVENT RESTORATION 0002 AUTOMATED CALL-OUT SYSTEM MAINTENANCE 0002 DRILLS AND EXERCISES 0001 DRILL DEVELOPMENT, CONDUCT AND EVALUATION 0001 EXERCISE DEVELOPMENT, CONDUCT AND EVALUATION 0001 SCHEDULING OF DRILLS AND EXERCISES 0001 DEMONSTRATION CRITERIA 0002 COMPUTER PROGRAMS 0008 EMERGENCY PREPAREDNESS CORRECTIVE ACTION PROCESS -

CANCELLED REPLACED BY LS-AA-125 0001 IFA FOR ACTION ITEM TRACKING SYSTEM -

CANCELLED -

NO REPLACEMENT 0001 ACTION/REQUEST EVALUATION NUMBERS AND TREND CODES CANCELLED -

NO EWPLACEMENT 0000 DEVELOPMENT AND MAINTENANCE OF THE EMERGENCY RESPONSE FACILITIES AND EQUIPMENT (ERF/E)

PROGRAM CANCELLED -

NO REPLACEMENT 0000 FLOWCHART OF DESIGNATION, TRAINING AND MAINTENANCE OF NUCLEAR ERO CANCELLED -

NO REPLACEMENT 0000 INTERFACE AGREEMENT FOR OFFSITE ORGANIZATION MATRIX REVIEW CANCELLED -

NO REPLACEMENT EFFECTIVE RESP SYSTEM DATE GROUP NBR 08/30/02 PWE 11/18/02 PWE 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 08/30/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 11/12/02 07/24/01 PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE 03/10/97 PWE 12/18/98 PWE 04/17/95 03/10/97 PWE PWE 03/10/97 PWE

PEACH BOTTOM ATOMIC POWER STATION PROCEDURE INDEX REPORT:

FAC PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB DOC TYPE PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC TYPE EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP EP PROCEDURE NUMBER EP-C-5-2 EP-C-6 EP-C-6-1 EP-C-6-2 EP-C-6-3 EP-C-6-4 EP-C-6-5 EP-C-7-1 EP-C-7-2 EP-MA-110-100 EP-MA-110-200 EP-MA-112-406 EP-MA-113-100 EP-MA-114-100 EP-MA-122 EP-MA-122-1001 EP-MA-122-1002 EP-MA-122-1003 EP-MA-122-1004 EP-MA-125-1003 END OF REPORT CURR REV NBR 0000 0004 0000 0000 0000 0000 0000 0000 0000 0000 0001 0000 0000 0001 0000 0002 0002 0000 0000 0001 TITLE INTERFACE AGREEMENT MATRIX FOR OFFSITE ORGANIZATIONS CANCELLED NO REPLACEMENT CANCELLED -

NO REPLACEMENT PREPARATION,

CONDUCT, AND EVALUATION OF EMERGENCY RESPONSE DRILLS AND EXCERCISES CANCELLED -

REPLACED BY EP-MA-122 DRILL OBJECTIVES -

CANCELLED -

NO REPLACEMENT ANNUAL EXCERCISE SCENARIO SUBMITTAL GUIDELINES -

CANCELLED -

NO REPLACEMENT SCENARIO MANUAL FORMAT -

CANCELLED -

NO REPLACEMENT DRILL ACTIVITY CHECKLIST -

CANCELLED -

NO REPLACEMENT DRILL REPORT FORMAT -

CANCELLED NO REPLACEMENT IFA FOR ROUTINE ADMINISTRATION & TESTING CANCELLED -

NO REPLACEMENT IFA FOR EMERGENCY SIREN MAINTENANCE CANCELLED -

NO REPLACEMENT ERO COMPUTER APPLICATIONS DOSE ASSESSMENT MAROG OFFSITE LIASONS ASSEMBLY AND SITE EVACUATION MAROG NOTIFICATIONS EXERCISE AND DRILLS -

CANCELLED REPLACED BY EP-AA-122 DRILL DEVELOPMENT, CONDUCT AND EVALUATION CANCELLED REPLACED BY EP-AA-122-1001 EXERCISE DEVLOPMENT, CONDUCT AND EVALUATION -

CANCELLED REPLACED BY EP-AA-122-1002 SCHEDULING OF DRILLS AND EXERCISES -

CANCELLED REPLACED BY EP-AA-122-1003 DEMONSTRATION CRITERIA -

CANCELLED REPLACED BY EP-AA-122-1004 COLLECTION AND EVALUATION OF DATA FOR INDICATOR R.EP.02, "EMERGENCY RESPONSE ORGANIZATION PARTICIPATION-'

EFFECTIVE DATE 04/10/00 02/21/02 03/10/97 03/10/97 03/10/97 03/10/97 03/10/97 03/10/97 03/10/97 08/30/02 11/18/02 08/30/02 08/30/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 RESP SYSTEM GROUP NBR PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE 11/19/2002 PAGE 2