Text

EP-MA-110-200, Revision 3, Dose Assessment
	ML032591165
Person / Time
Site:	Peach Bottom, Limerick, Crane
Issue date:	09/05/2003
From:	Gallagher M; AmerGen Energy Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation, Office of Nuclear Security and Incident Response
References
	5928-03-20185 EP-MA-110-200, Rev 3
	Download: ML032591165 (36)
	v • d • e

ExekOns.

AmerGenrm Nuclear An Exelon/Bntish Energy Company Exelon Generation 4300 Winfield Road Warrenville, IL 60555 www.exeloncorp.com 1 OCFR50, Appendix E 5928-03-20185 September 5, 2003 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 Three Mile Island, Unit 1 (TMI Unit 1)

Facility Operating License No. DPR-50 NRC Docket No. 50-289 EP-MA-1 10-200, Revision 3, 'Dose Assessment" Enclosed is a revised Emergency Plan Procedure for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3; Limerick Generating Station (LGS), Units 1 and 2; and Three Mile Island, (TMI) Unit 1. This procedure is required to be submitted within thirty (30) days of its revision in accordance with 1 OCFR50, Appendix E, and 1 OCFR50.4.

Also, enclosed are copies of a computer generated report index identifying the latest revisions of the LGS, PBAPS, and TMI procedures.

If you have any questions or require additional information, please do not hesitate to contact us.

I5O(

Emergency Plan Procedure September 5, 2003 Page 2 Very truly yours, M. P. Gallagher Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC Exelon Generation Company, LLC Enclosures cc:

H. J. Miller, Administrator, Region I, USNRC (w/ Enclosure)

G. F. Wunder, USNRC, Senior Project Manager (w/ Enclosure)

S. P. Wall, USNRC, Senior Project Manager (w/ Enclosure)

D. M. Skay, USNRC, Senior Project Manager (w/ Enclosure)

A. C. McMurtray, USNRC, Senior Resident Inspector, PBAPS (w/o Enclosure)

A. L. Burritt, USNRC, Senior Resident Inspector, LGS (wlo Enclosure)

D. M. Kem, USNRC, Senior Resident Inspector, TMI-1 (w/o Enclosures)

File No. 03035

ENCLOSURE 1 LIMERICK GENERATING STATION, UNITS 1 & 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 & 3 THREE MILE ISLAND, UNIT 1 Docket Nos.

License Nos.

50-352 50-353 50-277 50-278 50-289 NPF-39 NPF-85 DPR-44 DPR-56 DPR-50 EMERGENCY RESPONSE PROCEDURES EP-MA-1i10-200, "Dose Assessment" - Revision 3

EP-MA-110-200 Revision 3 ExeI--

Page 1 of 17 Nuclear Level 2 - Reference Use DOSE ASSESSMENT

1.

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), Peach Bottom Atomic Power Station (PBAPS) and Three Mile Island (TMI) Station. Procedure should be used concurrent with the appropriate dose assessor checklist:

Shift Dose Assessor - EP-AA-1 12-100, Attachment 3 TSC Radiation Controls Coordinator - EP-AA-1 12-206, Attachment 2 a EOF Dose Assessor - EP-AA-1 12-405, Attachment 3 1.2.

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 WindowsO 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.

1.3.

Refer to the station-specific DAPAR Program Technical Basis for details on program screens, release pathways, and options applicable to respective stations:

EP-LG-123-1001 (Limerick Station)

EP-PB-123-1001 (Peach Bottom Station)

EP-TM-123-1001 (Three Mile Island Station) 1.4.

Protective action recommendations (PARs) are given only when the plant is in a General Emergency classification. The initial PAR shall be based on plant conditions per EP-AA-1 11, Attachments 8 & 9. Subsequently, the dose-based PAR shall be evaluated against the plant-based PAR, if a release is occurring or likely, to determine if a PAR upgrade is warranted based on projected or actual dose.

EP-MA-1 10-200 Revision 3 Page 2 of 17

2.

TERMS AND DEFINITIONS

2.1. 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 1 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 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 effluent release locations 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.

2.2.

Release in Progress: Refer to definition contained in EP-MA-1 14-100.

3.

RESPONSIBILITIES 3.1.

A designated, qualified on-shift staff member 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). At LGS and PBAPS, this may be a Radiation Protection Technician (RPT) from the unaffected station.

3.2.

The TSC Radiolocical 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.

EP-MA-1 10-200 Revision 3 Page 3 of 17 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. To be a valid dose projection based on "Gap" release, the status of the fuel clad barrier must be declared either a Loss or Potential Loss per the Emergency Action Levels (EALs). 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 received by members of the public.

4.2.

Start UP 4.2.1.

If the main computer screen has DAPAR icons, then USE the left mouse to double-click on the icon to start the program.

NOTE: Backup to the hard drive DAPAR software is a DAPAR CD-ROM disk with each dose assessment computer.

1.

If the DAPAR program will not run, then INSTALL the program on any computer from backup CD located in the OSC, TSC or the EOF.

4.2.2.

OBTAIN required system / event status information via computer link or from the following individual, based on facility:

NOTE:

The DAPAR Input Sheet (Attachment 3) may be used as a tool in obtaining required information to perform projection.

Control Room STA/Independent Assessor (or Shift Manager) at the affected station or unit performing assessment TSC Operations Communicator (or Operations Manager)

EOF E

Operations Advisor (or Technical Support Manager)

EP-MA-10-200 Revision 3 Page 4 of 17 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 4.3.

Quick Assessment:

I 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.

If the release path is filtered, the assumption is that they are working. This allows for a rapid assessment.

4.3.1.

Monitor Information - User chooses the appropriate monitor from the listed effluent monitors.

Limerick South Stack concentrations must be greater than 1.OE-3 uCi/cm 3 to be considered a release.

SELECT the applicable release point:

STATION MONITOR READOUT Limerick North Stack pClsec South Stack pCi/cc Main Stack pCi/sec Peach Bottom Vent (Rx Bldg) Stack pCi/sec Torus Vent cpm TMVII Station / Rx Purge Vent cpm or mR/hr Main Steam Line cpm I

2.

SELECT monitor ID using pull down button.

3.

Reading Information - ENTER the appropriate monitor reading.

Limerick I TMI

4.

E N T E R E haust Flow.

4.

ENTER Exhaust Flow.

EP-MA-110-200 Revision 3 Page 5 of 17 TMI:

i 4.3.2.

If Main Steam Line monitor was selected, then ENTER the following:

S/G Pressure, in psig

(No. of) SRVs Open

(No. of) ADVs Open

-- If both steam generators have confirmed primary to secondary leaks, then SELECT 2 ADVs open. Otherwise, 1 ADV open should be selected until it is confirmed that both steam generators have primary to secondary leaks resulting in a radioactive release to the environment. (A significant primary to secondary leak (- 1 gallon per minute) in the 'A' S/G would cause an increase on RM-G-26, and a leak on 'B' S/G would cause an increase on RM-G-27.)

4.3.3.

ENTER Reading Information - Enter the appropriate monitor reading.

4.3.4.

ENTER Time After Shutdown Information - Enter the time since the reactor was shutdown in hours and minutes (hh:mm).

4.3.5.

ENTER Meteorological Data - Enter the appropriate data from plant instruments as follows:

1.

If meteorological data (wind speed / direction, stability class or delta temperature) are NOT available via EPDS I PPC or designated DAPAR Screen, 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.

4.3.6.

CLICK ON the Conditions button to open the Weather Conditions Window.

I1.

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. Currently, the program defaults to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.3.7.

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 a default value of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

EP-MA-1 10-200 Revision 3 Page 6 of 17 4.3.8.

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.

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. The window is divided into four input areas.

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 Coolant (TMI), Gap or Melt.

1.

If the containment dose rates exceed the Potential LOSS value defined in Fission Product Barrier Matrix (EAL Table 3-1) under the Primary Containment Barrier, then SELECT 'Melt" spectrum; otherwise, SELECT 'Gap" spectrum".

2.

SELECT "Coolant" until plant conditions for a Fuel Clad Barrier Loss or Potential Loss as defined in Fission Product Barrier Matrix (EAL Table 3-1) are met; then SELECT"Gap".

B.

ENTER the % Damage based on core damage estimates or known conditions obtained from:

TSC Radiation Controls Engineer (for PASS results)

TSC Core/Thermal Hydr. Engineer (for core damage assessments)

NOTE: The "% Damage" will only impact the magnitude of the dose projection if the Assessment Method selected is "Containment Leakage I Failure".

1.

If "% Damage" is unknown, then SELECT a default value of 10%.

I EP-MA-110-200 Revision 3 Page 7 of 17

2.

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

A.

Under 'Fuel Type", SELECT New Fuel if it is less than 1 year since the spent fuel was removed from the reactor core; otherwise, SELECT Old.

B.

Under 'Fuel Status", SELECT Dry if the spent fuel pool is drained or a spent fuel bundle is exposed to air; otherwise, SELECT Underwater.

NOTE:

The program uses a gap release scenario and defaults to a reactor Time After Shutdown based on this choice.

Limerick only l

'3.

SELECT Backwash Demin Spectrum if the release results from al backwash operation.

TMI onLy

4.

SEETWaste Gas Decay Tank Accident, as applicable.

4.4.2.

Dominant Release Path - SELECT the appropriate reduction factors from the options provided, based on the identified release path:

Limerick I Peach Bottom Reactor Building PRFs:

If SBGT flow rate information is unavailable, with normal ventilation running, or ventilation status is unknown, then SELECT a Holdup time < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

If SBGT is running > 700 cfm, then SELECT a Holdup time of 2 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If SBGT is running < 700 cfm, then SELECT a Holdup time of > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Torus I Wetwell PRFs:

If the effluent stream does not passes through the Torus/Wetwell or is unknown, then SELECT 'Bypassed";

If the effluent stream passes through the TorusNVetwell and Torus/Wetwell water temperature is greater than 212'F, then SELECT "saturated"; otherwise, SELECT 'Subcooled".

EP-MA-1 10-200 Revision 3 Page 8 of 17 TMI Auxiliary Buildinq PRFs:

If the Station Vent flow rate is unknown or > 4,000 cfm, then SELECT a Holdup time < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

If the Station Vent flow rate is < 350 cfmn, then SELECT a Holdup time of

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If the Station Vent flow rate is > 350 cfm but < 4,000 cfm, then SELECT a Holdup time of 2 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Steam Generator PRFs:

If the Steam Generator water level is > 600 inches, then SELECT 'Solid".

If the Steam Generator water level is < 6 inches, then SELECT 'Dry'.

If the Steam Generator water level is > 6 inches but < 600 inches, then SELECT "Boiling".

Containment Building PRFs:

If ANY of the following conditions exist, then SELECT a Hold-Up Time of U< 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ":

Rx Purge flow rate is unknown; Rx Purge flow rate is > 16,000 cfm, or Catastrophic Failure" under Containment Leakage / Failure Assessment Method is selected.

If ANY of the following conditions exist, then SELECT a Hold-Up Time of

"> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ":

Rx Purge flow rate is < 1,300 cfm; Path D is chosen, or "Design Leakage" under Containment Leakage / Failure Assessment Method is selected.

If ANY of the following conditions exist, then SELECT a Hold-Up Time of "2 -24 hours":

Rx Purge flow rate is > 1,300 cfm or < 16, 000 cfm, or "Failure to Isolate" under Containment Leakage / Failure Assessment Method is selected.

If the exact status can not be determined, then SELECT the following options until they can be verified by the TSC Technical Support Group:

Containment Spray: "OFF" Holdup time: "< 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months " Filters: "Working"

EP-MA-1 10-200 Revision 3 Page 9 of 17 4.4.3.

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

1.

If meteorological data (wind speed / direction, stability class or delta temperature) are NOT available via EPDS / PPC or designated DAPAR Screen, then GO TO Attachment 2.

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. GO TO Section 4.5.

2.

Containment Leakage /Failure - SELECT this method for containment failure scenarios. GO TO Section 4.6.

3.

Field Team Analysis - SELECT this method if field team survey or sample data is available. GO TO Section 4.7.

4.

Release Point Sample - SELECT this method if a sample of release was obtained and release flow rate can be estimated. GO TO Section 4.8.

4.5.

Monitored Release 4.5.1.

Under Monitor-User chooses or enters the following: -

1.

SELECT the applicable monitor from the listed effluent monitors (using the pull down button).

2.

ENTER Reading Information - Enter the appropriate monitor reading.

Limerick I TMI

13.

ENTER Exhaust Flow. _

TM[

4.5.2.

If Main Steam Line monitor was selected, then ENTER the following:

SIG Pressure, in psig

(No. of) SRVs Open

(No. of ) ADVs Open

-- If both steam generators have confirmed primary to secondary leaks, then SELECT 2 ADVs open. Otherwise, 1 ADV open should be selected until it is confirmed that both steam generators have primary to secondary leaks resulting in a radioactive release to the environment. (A significant primary to secondary leak (- 1 gallon per minute) in the 'A' S/G would cause an increase on RM-G-26, and a leak on 'B' S/G would cause an increase on RM-G-27.)

EP-MA-110-200 Revision 3 Page 10 of 17 4.5.3.

SELECT the Print button to print a report of offsite dose projections based on the monitored release.

NOTE: Some DAPAR programs may require going to the PAR Screen to print a report.

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 - GO TO section 4.9.

4.6.

Containment Leakage/Failure 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time period.

CAUTION The use of catastrophic failure option results in extremely high doses offsite. As such, this option should only be used if both the Reactor Coolant System (RCS) and Fuel Clad Barriers are considered lost and Primary Containment has at least a 4 ft2 hole providing a direct release path to the environment.

3.

Catastrophic Failure - Assumes 100% of the isotopes available for release are released in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.

NOTE: Some DAPAR programs may require going to the PAR Screen to print a report.

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.

EP-MA-1 10-200 Revision 3 Page 11 of 17 4.7.

Field Team Analysis 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.

4.7.3.

ENTER the Field Team information as follows:

NOTE:

The program will not allow Tmr/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 umR/hrs 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/cm3, calculated using the KI Spreadsheet Program per EP-MW(MA)-1 10-100 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.

NOTE: Some DAPAR programs may require going to the PAR Screen to print a report.

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-1 10-200 Revision 3 Page 12 of 17 4.8.

Release Point Analysis 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:

1.

SELECT the Print button to print offsite dose projections based on Release Point Analysis.

NOTE: Some DAPAR programs may require going to the PAR Screen to print a report.

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.

4.9.

Protective Action Recommendations (PAR) - The PAR displays a summary of the downwind dose projections with a map showing which Sectors (colored areas) where a PAR should be made.

4.9.1.

SELECT the RR button to display the total release rates for isotopic groups.

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.

4.9.4.

If project performed following a General Emergency classification or PAR update, then PERFORM the following:

1.

SELECT the STATE REPORT button to display DAPAR BRP PARAMETER REPORT and PRINT copy of form.

CAUTION DO NOT fax contingency ("what if") calculations offsite. The results of these projections should be discussed directly with State officials.

2.

TRANSMIT (fax) a copy of DAPAR Dose Assessment, PAR and designated STATE reports to the Pennsylvania Emergency Operations Center (EOC) using the nos. listed in the Emergency Response Facility (ERF) Telephone Directory (Section 5.0, under PEMA - use BRP fax numbers).

EP-MA-1 10-200 Revision 3 Page 13 of 17 A.

If BRP Representative is present in facility, then PROVIDE copies of reports directly to this individual rather than faxing.

5.

DOCUMENTATION:

None

6.

REFERENCES 6.1.

Exelon DAPAR Program Software Requirements Specification 6.2.

Commitments - None

7.

ATTACHMENTS 7.1., Basic Program Flow Diagram 7.2., Determination of Stability Class 7.3., DAPAR Input Sheet

EP-MA-1 10-200 Revision 3 Page 14 of 17 ATTACHMENT I BASIC 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-1 10-200 Revision 3 Page 15 of 17 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, then CONTACT the National Weather Service (NWS) using the icon on designated DAPAR lap-tops/PCs or by calling the numbers listed in the Emergency Response Facility (ERF) Telephone Directory.

REQUEST the following information:

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-360°)

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.

a.

If Surface Wind Speed (in mph) is available, then USE Table 2-1.

b.

If delta temperature (AT), then USE station-specific values contained in Table 2-2 (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 3 Page 16 of 17 ATTACHMENT 2 DETERMINATION OF STABILITY CLASS Page 2 of 2 Table 2-1 t~

on ugt Table 2-2 II

EP-MA-1 10-200 Revision 3 Page 17 of 17 ATTACHMENT 3 DAPAR INPUT SHEET Page 1 of I I

Date:_I I_

Time:

Station - Unit:_

OBTAIN FROM: CR (S TAIA) / TSC (Ops. Communicator) / EOF (Operations Advisor)

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[ North Stack:

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Rx Purge:

[JSouth Stack:

I I Vent Stack:

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[ UNMONITORED

] 3 Torus Vent:

3 Condenser Off-Gas:

[

UNMONITORED I I SRV I ADV:

t ESF Vent:

(3 UNMONITORED DESCRIBE FROM RPV TO RELEASE POINT:

RELEASE DURATION:

[ lNo Release In Progress START TME:

/ STOP TIME:

Total Duration:

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SIPRESSURE:

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HR I 11 2-24 HR5 I [ I >24 HRS I [IINOT APPLICABLE TE ILRUCTIONS F

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[1 FILTERSWORKING I 1I FILTERS NOTWORKING WIG R~DUC11ONS (PWRQNLY~

[I SECONDARYBOILING I Fl SECONDARYSOLID I rI SECONDARYDRY OBTAIN FROM: CR (STA/IA) / TSC (Core/Hydraulic Engr. )IEOF (Techncial Advisor) l REACTOR CORE ACCIDENT

[ JSPENT FUEL ACCIDENT TYPE OF DAMAGE: 1COOLANT(TMII Only) / [JGAP I IMELT FUEL TYPE: [I NEW I [I OLD AMOUNT OF DAMAGE:

FUEL STATUS: [I UNDER WATER I II DRY Wind Speed (mph): _'_

Wind Direction (from):

Stability Class:

Other:

ENCLOSURE 2 LIMERICK GENERATING STATION, UNITS 1 & 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 & 3 THREE MILE ISLAND, UNIT I Docket Nos.

License Nos.

50-352 50-353 50-277 50-278 50-289 NPF-39 NPF-85 DPR-44 DPR-56 DPR-50 EMERGENCY RESPONSE PROCEDURES REPORT INDICES

9/05/2003 PAGE 1

PEACH BOTTOM ATOMIC POWER STATION PROCEDURE INDEX REPORT:

DOC PROC FAC TYPE TYPE PROCEDURE NUMBER 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 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 PROC PROC PROC PROC PROC EP-AA-1000 EP-AA-1007 EP-AA-lOl 1

EP-AA-1 102 EP-AA-l lO 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-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 EP-AA-120-1001 EP-AA-120-1002 EP-AA-121 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-AA-124 EP-AA-125 EP-AA-125-1001 EP-AA-125-1002 EP-AA-125-1003 EP-AA-125-1004 CURR REV NBR 0014 0007 0001 0000 0004 0000 0001 0006 0008 0005 0004 0001 0001 0001 0001 0001 0001 0004 0004 0001 0001 0001 0001 0001 0005 0006 0001 0002 0004 0004 0001 0003 0003 0000 0003 0003 0003 0002 0002 0002 0001 0002 0004 0002 0002 0002 0002 0002 TITLE STANDARIZED RADIOLOGICAL EMERGENCY PLAN RADIOLOGICAL EMERGENCY PLAN ANNEX FOR PEACH BOTTOM ATOMIC POWER STATION EP FUNDAMENTALS ERO FUNDAMENTALS 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 ACTIVIATION 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 ACTIVIATION 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 PUBLIC INFORMATION ORGANIZATION ACTIVATION AND OPERATIONS 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 EMERGENCY RESPONSE FACILITIES AND EQUIPMENT READINESS AUTOMATED CALL-OUT SYSTEM MAINTENANCE 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 ERP READINESS -

PERFORMANCE INDICATORS GUIDANCE EMERGENCY RESPONSE FACILITIES & EQUIPMENT PERFORMANCE INDICATORS EFFECTIVE RESP SYSTEM DATE GROUP NBR 02/20/03 PWE 06/30/03 PWE 12/20/02 12/20/02 02/20/03 08/30/02 12/17/02 05/23/03 05/23/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 05/23/03 02/20/03 05/23/03 08/30/02 02/20/03 08/30/.02 12/20/02 04/30/03 10/18/02 12/20/02 04/30/03 12/20/02 12/20/02 12/20/02 12/20/02 10/18/02 11/12/02 12/20/02 12/20/02 12/20/02 12/20/02 12/20/02 12/20/02 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 PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE

9/05/2003 PAGE 2

PEACH BOTTOM ATOMIC POWER STATION PROCEDURE INDEX REPORT:

FAC PB PB PB PB PB PB PB PB PB PB PB PB P8 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 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 EP EP EP EP EP EP EP EP EP EP EP EP EP PROCEDURE NUMBER EP-AA-125-1004 EP-AA-125-1005 EP-C-2 EP-C-2-1 EP-C-2-2 EP-C-3-1 EXH EP-C-4-1 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-121-1002 EP-MA-121-1004 EP-MA-122 EP-MA-122-1001 EP-MA-122-1002 EP-MA-122-1003 EP-MA-122-1004 EP-MA-123-1001 EP-MA-123-1005 EP-MA-124-1001 EP-MA-125-1002 CURR REV NBR 0002 0000 0008 0001 0001 0000 0000 0000 0000 0004 0000 0000 0000 0000 0000 0000 0000 0002 0003 0001 0001 0004 0000 0000 0000 0002 0002 0000 0000 0000 0000 0002 0000 TITLE GUIDANCE PROBLEM IDENTIFICATION & RESOULTION PERFORMANCE INDICATOR GUIDANCE EMERGENCY PREPAREDNESS CORRECTIVE ACTION PROCESS -

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

CANCELLED -

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

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

CANCELLED -

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

NO REPLACEMENT INTERFACE AGREEMENT FOR OFFSITE ORGANIZATION MATRIX REVIEW -

CANCELLED -

NO REPLACEMENT 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 ALERT NOTIFICATION SYSTEM (ANS) DESCRIPTION, TESTING, MAINTENANCE AND PERFORMANCE TRENDING PROGRAM EMERGENCY PREPAREDNESS ALERT NOTIFICATION SYSTEM (ANS) CONTROL OF EQUIPMENT & OUTAGES 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 KI ASSESSMENT SPREADSHEET TECHNICAL BASIS DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (DAPAR)

PROGRAM TECHNICAL BASIS FOR PEACH BOTTOM ATOMIC POWER STATION FACILITY INVENTORIES AND EQUIPMENT TESTS COLLECTION AND EVALUATION OF DATA FOR INDICATOR E EP.01 "DRILL EXERCISE PERFORMANCE" CANCELLED -

EP-AA-125-1002 EFFECTIVE DATE 12/20/02 12/20/02 07/24/01 03/10/97 12/18/98 04/17/95 03/10/97 03/10/97 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 07/01/03 08/08/03 02/20/03 02/20/03 07/01/03 12/20/02 12/20/02 10/18/02 10/18/02 10/18/02 10/18/02 10/18/02 07/01/03 08/08/03 07/01/03 12/20/02 RESP SYSTEM GROUP NBR PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE PWE

9/05/2003 PAGE 3

PEACH BOTTOM ATOMIC POWER STATION PROCEDURE INDEX REPORT:

DOC FAC TYPE PB PROC PROC TYPE EP PROCEDURE NUMBER EP-MA-125-1003 PB PROC EP EP-MA-125-1004 CURR REV NBR TITLE 0001 COLLECTION AND EVALUATION OF DATA FOR INDICATOR R.EP.02, "EMERGENCY RESPONSE ORGANIZATION PARTICIPATION"" CANCELLED -

REPLACED BY EP-AA-125-1003 0000 COLLECTION AND EVAULUATION OF DATA FOR INDIATOR R.EP.03 ALERT

& NOTIFICATION SYSTEM RELIABILITY CANCELLED -

REPLACED BY EP-AA-125-1004 0005 CONTROL OF EP GUIDELINES 0004 EMERGENCY PREPAREDNESS STAFF ORIENTATION CANCELLED -

REPLACED BY TQ-AA-113 0004 CHECKLIST FOR EMERGENCY PREPAREDNESS STAFF ORIENTATION CANCELLED REPLACED BY TQ-AA-113 EFFECTIVE DATE 12/20/02 RESP SYSTEM GROUP NBR PWE PB PROC PB PROC PB PROC EP EP EP EP-UG-O 1 EP-UG-05 EP-UG-05-1 12/20/02 PWE 12/07/98 07/16/03 07/16/03

- END OF REPORT **

9/05/2003 PAGE I

LIMERICK GENERATING STATION PROCEDURE INDEX REPORT:

DOC PROC FAC TYPE TYPE LG LG LG LO LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LO LG LG LG LG LG LO LG LO LG LG LG LG LG LG LG LO 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 PROCEDURE NUMBER EP-AA-1 EP-AA-10 EP-AA-11 EP-AA-1101 EP-AA-1102 EP-AA-110 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-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-l15 EP-AA-120 EP-AA-120-1001 EP-AA-120-1002 EP-AA-121 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-AA-124 EP-AA-125 EP-AA-125-1001 EP-AA-125-1002 EP-AA-125-1003 CURR REV NBR 0000 0001 0001 0001 0000 0004 0000 0001 0006 0008 0005 0004 0001 0001 0001 0001 0001 0001 0004 0004 0001 0001 0001 0001 0001 0005 0006 0001 0002 0004 0004 0001 0003 0003 0000 0003 0003 0003 0002 0002 0002 0001 0002 0004 0002 0002 0002 0002 EFFECTIVE RESP SYSTEM DATE GROUP NBR TITLE EMERGENCY PREPAREDNESS EMERGENCY PREPAREDNESS PROCESS DESCRIPTION OPERATING STATIONS EMERGENCY PREPAREDNESS PROCESS DESCRIPTION EP FUNDAMENTALS ERO FUNDAMENTALS ASSESSMENT OF EMERGENCIES CORE DAMAGE ASSESSMENT (BWR)

CORE DAMAGE ASSESSMENT (PWR)

- - - NO HARDCOPY DIST AT LGS SEE P4****

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 EMERGENCY RESPONSE FACILITIES AND EQUIPMENT READINESS AUTOMATED CALL-OUT SYSTEM MAINTENANCE 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 ERO READINESS -

PERFORMANCE INDICATORS GUIDANCE 10/20/00 12/12/02 12/12/02 12/20/02 12/20/02 02/20/03 08/30/02 12/03/02 05/23/03 05/23/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 02/20/03 05/23/03 02/20/03 05/23/03 08/30/02 02/20/03 08/30/02 12/20/02 05/21/03 10/09/02 12/20/02 05/21/03 12/20/02 12/20/02 12/20/02 12/20/02 10/09/02 11/05/02 12/20/02 12/20/02 12/20/02 12/20/02 12/20/02

9/05/2003 PAGE 2

LIMERICK GENERATING STATION PROCEDURE INDEX REPORT:

FAC 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 DOC TYPE 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 TYPE 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-125-1004 EP-AA-125-1005 EP-MA-110-100 EP-MA-110-200 EP-MA-112-406 EP-MA-113-100 EP-MA-114-100 EP-MA-121-1002 EP-MA-121-1004 EP-MA-122 EP-MA-122-1001 EP-MA-122-1002 EP-MA-122-1003 EP-MA-122-1004 EP-MA-123-1001 EP-MA-123-1004 EP-MA-124-1001 EP-MA-125-1003 CURR REV NBR 0002 0000 0002 0003 0001 0001 0004 0000 0000 0000 0002 0002 0000 0000 0000 0000 0002 0001 TITLE EMERGENCY RESPONSE FACILITIES & EQUIPMENT PERFORMANCE INDICATORS GUIDANCE PROBLEM INDENTIFICATION & RESOLUTION PERFORMANCE INDICATOR GUIDANCE ERO COMPUTER APPLICATIONS DOSE ASSESSMENT MAROG OFFSITE LIAISONS ASSEMBLY AND SITE EVACUATION MAROG NOTIFICATIONS ALERT NOTIFICATION SYSTEM (ANS) DESCRIPTION. TESTING, MAINTENANCE AND PERFORMANCE TRENDING PROGRAM EMERGENCY PREPAREDNESS ALERT NOTIFICATION SYSTEM (ANS) CONTROL OF EQUIPMENT & OUTAGES EXERCISES AND DRILLS SUPERCEDED BY EP-AA-122 DRILL DEVELOPMENT, CONDUCT AND EVALUATION SUPERCEDED BY EP-AA-122-1001 EXERCISE DEVELOPMENT, CONDUCT AND EVALUATION SUPERCEDED BY EP-AA-122-1002 SCHEDULING OF DRILLS AND EXERCISES SUPERCEDED BY EP-AA-122-1003 DEMONSTRATION CRITERIA SUPERCEDED BY EP-AA-122-1004 KI ASSESSMENT SPREADSHEET TECHNICAL BASIS DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (DAPAR)

PROGRAM TECHNICAL BASIS FOR LIMERICK GENERATING STATION FACILITY INVENTORIES AND EQUIPMENT TESTS COLLECTION AND EVALUATION OF DATA FOR INDICATOR R.EP.02, "EMERGENCY RESPONSE ORGANIZATION PARTICIPATION" SUPERCEDED BY EP-AA-125-1003 CANCELLED 4/03/92 (SUPERCEDED BY ERP-200)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-200 APP.1)

CANCELLED 04/03/92 (SUPERCEDED BY ERP-101)

CANCELLED INCORPORATED INTO EP100 &EP112 CANCELLED INCORPORATED INTO EP100 & EP112 CANCELLED INCORPORATED INTO EP100 & EP112 CANCELLED INCORPORATED INTO EP100 & EP112 CANCELLED INCORPORATED INTO EP100 & EP112 CANCELLED INCORPORATED INTO EP100 & EP112 CANCELLED INCORPORATED INTO EP100 & EP112 CANCELLED INCORPORATED INTO EP100 & 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-1200)

CANCELLED (4/3/92) INCORPORATED INTO ERP-800 CANCELLED 04/03/92 (SUPERCEDED BY ERP-230)

CANCELLED 04/03/92 (SUPERCEDED BYERP-C-1200)

CANCELLEDt08/20/90)

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

EFFECTIVE DATE 12/20/02 12/20/02 07/01/03 0O/08/08 02/20/03 02/20/03 07/01/03 12/20/02 12/20/02 12/20/02 10/09/02 10/09/02 10/09/02 10/09/02 07/01/03 08/08/03 07/01/03 12/20/02 RESP SYSTEM GROUP NBR EP-100 EP-100-1 APP.

EP-101 EP-102 EP-102 APP.1 EP-103 EP-103 APP.1 EP-104 EP-104 APP.1 EP-105 EP-105 APP.1 EP-106 EP-110 EP-112 EP-120 EP-201 EP-202 EP-203 EP-204 EP-208 0003 0003 0013 0015 0010 0018 0009 0017 0009 0017 0009 0009 0015 0006 0009 0012 0012 0012 0001 0015 LWE LWE LWE LWE LWE LWE LWE LWE LWE

9/05/2003 PAGE 3

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-210 0016 CANCELLED (4/3/92) INCORPORATED INTO ERP-300 LG PROC EP EP-211 0009 CANCELLED (4/3/92) INCORPORATED INTO ERP-340 LG PROC EP EP-220 0000 CANCELLED LWE LG PROC EP EP-221 0000 CANCELLED LWE LG PROC EP EP-222 0000 CANCELLED LWE LG PROC EP EP-225 0003 CANCELLED 04/03/92 (SUPERCEDED BY ERP-700)

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 LWE LG PROC EP EP-233 0010 CANCELLED (3/22/91)

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 LWE LG PROC EP EP-241 0014 CANCELLED 04/03/92 (SUPERCEDED BY ERP-410)

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-600 LG PROC EP EP-251 0005 CANCELLED (4/3/92) INCORPORATED INTO ERP-620 LG PROC EP EP-252 0016 CANCELLED 04/03/92 (SUPERCEDED BY ERP-500)

LG PROC EP EP-253 0000 CANCELLED LWE LG PROC EP EP-254 0005 CANCELLED (4/3/92) INCORPORATED INTO ERP-630 LG PROC EP EP-255 0005 CANCELLED (4/3/92) INCORPORATED INTO ERP-260 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 LWE LG PROC EP EP-261 0010 CANCELLED 04/03/92 (SUPERCEDED BY ERP-800)

LG PROC EP EP-272 0000 CANCELLED LWE LG PROC EP EP-273 0000 CANCELLED LWE LG PROC EP EP-275 0000 CANCELLED LWE 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)

LG PROC EP EP-280 0021 CANCELLED(11/13/90)

LG PROC EP EP-282 0016 CANCELLED (8/13/91)

LG PROC EP EP-284 0013 CANCELLED (B/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)

9/05/2003 PAGE 4

LIMERICK GENERATING STATION PROCEDURE INDEX REPORT:

DOC PROC FAC TYPE TYPE CURR REV NBR TITLE 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 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-307 EP-312 EP-313 EP-314 EP-315 EP-316 EP-317 EP-318 EP-319 EP-320 EP-321 EP-322 EP-322 APP.9 EP-324 EP-324 APP. 5 EP-324 APP.6 EP-325 EP-327 EP-328 EP-330 EP-333 EP-401 EP-410 EP-500 END OF REPORT *0 EFFECTIVE RESP SYSTEM DATE GROUP NBR 0004 0011 0007 0003 0009 0004 0014 0004 0002 0002 0003 0000 0001 0000 0000 0000 0010 0002 0000 0007 0002 0005 0013 0002 CANCELLED 04/03/92 (SUPERCEDED BY ERP-C-1500)

CANCELLED (4/3/92) INCORPORATED INTO ERP-350 CANCELLED (4/3/92) INCORPORATED INTO ERP-660 CANCELLED(01/03/91)

CANCELLED CANCELLED CANCELLED (4/3/92) INCORPORATED INTO ERP-370 CANCELLED (4/3/92) INCORPORATED INTO ERP-350 CANCELLED CANCELLED(09/21/90)

CANCELLED(O9/21/90)

CANCELLED(09/21/90)

CANCELLED(11/05/90)

CANCELLED (4/3/92) INCORPORATED INTO ERP-300 CANCELLED (4/3/92) INCORPORATED INTO ERP-300 CANCELLED (4/3/92) INCORPORATED INTO ERP-300 CANCELLED (4/3/92) INCORPORATED INTO ERP-370 CANCELLED (4/2/92) INCORPORATED INTO ERP-370 CANCELLED (4/2/92) INCORPORATED INTO ERP-370 CANCELLED (4/2/92) INCORPORATED INTO ERP-640 CANCELLED (4/3/92) INCORPORATED INTO ERP-360 CANCELLED (4/3/92) INCORPORATED INTO ERP-650 CANCELLED 04/03/92 (SUPERCEDED BY ERP-C-1900)

CANCELLED LWE LWE LWE LWE LWE LWE LWE LWE

9/4/03 7:19:36 AM EXELON POLICIES AND DIRECTIVES PROCEDURE NUMBER EP-AA-1 REV EFFDATE SITE 0 2000-10-20 TMI1 PROCEDURE TITLE EMERGENCY PREPAREDNESS TC NUMBER LEVEL N/A

914/03 7:19:38 AM EMERGENCY PLAN IMPLEMENTING PROCEDURE / DOCUMENT PROCEDURE NUMBER EP-M-1 10 EP-AA-1 10-301 EP-AA-1 10-302 EP-AA-111 REV 4

0 1

6 EFFDATE 2003-03-28 2003-03-28 2003-03-28 2003-05-23 SITE TMI1 TMI1 TMI1 TMI1 PROCEDURE TITLE 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 TC NUMBER LEVEL 2

2 2

2 EP-AA-1 12 8 2003-05-23 TMII 2

EP-AA-1 12-1 00 EP-AA-1 12-200 EP-AA-1 12-201 EP-AA-1 12-202 EP-AA-1 12-203 EP-M-1 12-204 EP-AA-1 12-205 EP-AA-1 12-206 EP-AA-1 12-300 5

4 1

1 1

1 4

2003-03-28 2003-03-28 2003-03-28 2003-03-28 2003-03-28 2003-03-28 2003-03-28 2003-03-28 2003-03-28 TMI1 TMI1 TMI1 TMI1 TMI1 TMI1 TMI1 TMI1 TMI1 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 TECHINICAL SUPPORT GROUP EP-AA-1 12-400 EP-AA-1 12-401 EP-AA-1 12-402 EP-AA-1 12-403 EP-AA-1 12-404 4 2003-03-28 TMI1 1

1 1

1 2003-03-28 2003-03-28 2003-03-28 2003-03-28 TMI1 TMI1 TMI1 TMI1

9/4/03 7:21:19 AM EMERGENCY PLAN IMPLEMENTING PROCEDURE / DOCUMENT PROCEDURE NUMBER EP-AA-1 12-405 EP-AA-1 12-500 EP-M-1 12-600 REV 1

5 6

EFFDATE SITE 2003-03-28 TMI1 2003-03-28 TMI1 2003-05-23 TMI1 PROCEDURE TITLE EOF PROTECTIVE MEASURES GROUP EMERGENCY ENVIRONMENTAL MONITORING PUBLIC INFORMATION ORGANIZATION ACTIVATION AND OPERATIONS TC NUMBER LEVEL 2

2 2

EP-AA-1 12-601 EP-AA-1 12-602 EP-AA-1 13 EP-AA-1 14 EP-AA-1 15 EP-AA-1 20 EP-AA-1 21 1

2 4

4 1

3 3

EP-AA-1 22 EP-M-1 23 EP-M-1 24 EP-M-1 25 3

2 4

2 2003-03-28 TMI1 2003-05-23 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2002-12-20 TMII 2003-07-01 TMI1 2003-08-08 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-07-01 TMI1 2002-12-02 TMI1 2002-07-12 TMI1 EMERGENCY NEWS CENTER (ENC) OPERATIONS JPIC ACTIVATION AND OPERATION PERSONNEL PROTECTIVE ACTIONS NOTIFICATIONS RECOVERY FROM A CLASSIFIED EVENT EMERGENCY PLAN ADMINISTRATION EMERGENCY RESPONSE FACILITIES AND EQUIPMENT READINESS DRILLS AND EXERCISES COMPUTER PROGRAMS INVENTORIES AND SURVEILLANCES EMERGENCY PREPAREDNESS SELF EVALUATION PROCESS ERO COMPUTER APPLICATIONS DOSE ASSESSMENT MAROG OFFSITE LUAISONS ASSEMBLY AND SITE EVACUATION MAROG NOTIFICATIONS ADDITIONAL ASSISTANCE AND NOTIFICATION CONTAMINATED INJURIES 2

2 2

EP-MA-110-1 00 EP-MA-1 10-200 EP-MA-1 12-406 EP-MA-1 13-1 00 EP-MA-1 14-1 00 EPIP-TMI-.06 EPIP-TMI-.16 2

3 1

1 4

43 11 2

2 2

3 2

9/4/03 7:21:21 AM PROCEDURE NUMBER EPIP-TMI-.19 REV 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE / DOCUMENT EFFDATE SITE PROCEDURE TITLE 2000-10-20 TMI1 EMERGENCY DOSIMETRY / SECURITY BADGE ISSUANCE TC NUMBER LEVEL 2

TEP-ADM-1300.01 TEP-ADM-1300.02 TEP-ADM-1 300.04 11 10 9

2003-03-28 TMI1 2001-03-01 TMI1 2002-05-10 TMI1 MAINTAINING EMERGENCY PREPAREDNESS EMERGENCY PREPAREDNESS TRAINING ADMINISTRATION OF THE TMI INITIAL RESPONSE AND EMERGENCY SUPPORT ORGANIZATION DUTY ROSTER 2

3 3

TEP-ADM-1 300.05 13 2003-08-08 TMI1 EMERGENCY EQUIPMENT READINESS 2

9/4/03 7:21:33 AM EMERGENCY PREPAREDNESS PROCEDURE PROCEDURE NUMBER TEP-SUR-1 310.01 TEP-SUR-1 310.05 TEP-SUR-1 310.10 REV EFFDATE SITE 11 2003-03-28 TMI1 5 2003-03-28 TMI1 5 2001-11-13 TMI1 PROCEDURE TITLE EMERGENCY COMMUNICATIONS TEST PROCEDURE VERIFICATION OF EMERGENCY PREPAREDNESS AIDS PROCEDURE CHANGE NOTIFICATION TC NUMBER LEVEL 2

3 3

9/4/03 7:22:11 AM EXELON TRAINING AND REFERENCE MATERIAL PROCEDURE NUMBER EP-M-1 000 EP-AA-1 009 REV 14 1

EFFDATE SITE 2003-03-28 TMI1 2003-05-23 TMI1 EP-AA-1 1 01 EP-AA-1 102 EP-AA-1 20-1 001 EP-AA-1 20-1002 EP-AA-1 21 -1 001 EP-AA-1 22-1 001 EP-AA-1 22-1002 1

0 3

2 2

2003-03-28 TMI1 2003-03-28 TMI1 2003-05-09 TMI1 2003-03-28 TMI1 2003-05-09 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2003-03-28 TMI1 2002-12-20 TMI1 2002-12-20 TMI1 EP-AA-1 22-1003 EP-AA-1 22-1004 EP-M-1 25-1 001 EP-AA-1 25-1002 2

1 2

2 PROCEDURE TITLE STANDARDIZED RADIOLOGICAL EMERGENCY PLAN EXELON NUCLEAR RADIOLOGICAL EMERGENCY PLAN ANNEX FOR THREE MILE ISLAND (TMI) STATION EP FUNDAMENTALS ERO FUNDAMENTALS 10 CFR 50.54(Q) CHANGE EVALUATION STORM / EVENT RESTORATION AUTOMATED CALL-OUT SYSTEM MAINTENANCE DRILL DEVELOPMENT CONDUCT AND EVALUATION EXERCISE DEVELOPMENT CONDUCT AND EVALUATION SCHEDULING OF DRILLS AND EXERCISES.

DEMONSTRATION CRITERIA EP PERFORMANCE INDICATOR GUIDANCE ERO PERFORMANCE - PERFORMANCE INDICATORS GUIDANCE ERO READINESS - PERFORMANCE INDICATORS GUIDANCE EMERGENCY RESPONSE FACILITIES & EQUIPMENT PERFORMANCE INDICATORS GUIDANCE PROBLEM IDENTIFICATION AND RESOLUTION PERFORMANCE INDICATOR GUIDANCE ALERT NOTIFICATION SYSTEM (ANS) DESCRIPTION TESTING MAINTENANCE AND PERFORMANCE TRENDING PROGRAM EMERGENCY PREPAREDNESS ALERT NOTIFICATION SYSTEM (ANS) CONTROL OF EQUIPMENT & OUTAGES KI ASSESSMENT SPREADSHEET TECHNICAL BASIS N/A N/A N/A N/A N/A N/A N/A TC NUMBER LEVEL N/A 2

N/A N/A 2

2 EP-AA-1 25-1003 EP-AA-1 25-1004 EP-AA-1 25-1005 EP-MA-1 21-1002 EP-MA-1 21-1004 2 2003-03-28 TMI1 2 2002-12-20 TMI1 0 2002-12-20 TMI1 0 2003-03-28 TMI1 0 2003-03-28 TMI1 N/A N/A 2

N/A N/A EP-MA-1 23-1 001 0 2003-07-01 TM11 N/A

9/4/03 7:22:22 AM PROCEDURE NUMBER EP-MA-1 23-1002 EP-MA-1 24-1001 EP-MA-1 25-1002 EP-MA-1 25-1003 EXELON TRAINING AND REFERENCE MATERIAL REV EFFDATE SITE PROCEDURE TITLE 0 2003-08-08 TMI1 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (DAPAR) PROGRAM TECHNICAL BASIS FOR TMI STATION 2 2003-07-01 TMI1 FACILITY INVENTORIES AND EQUIPMENT TESTS N/A 2001-06-21 TMI1 COLLECTION AND EVALUATION OF DATA FOR INDICATOR R.EP.01 DRILL AND EXERCISE PERFORMANCE 2 2002-12-20 TMI1 ERO READINESS - PERFORMANCE INDICATORS GUIDANCE TC NUMBER LEVEL N/A N/A N/A 2

9/4/03 7:23:12 AM PROCEDURE NUMBER EP-AA-1 0 EP-AA-1 1 REV EFFDATE SITE 1 2002-12-06 TMI1 1 2002-12-06 TMI1 EXELON DEPARTMENT DESCRIPTIONS PROCEDURE TITLE EMERGENCY PREPAREDNESS PROCESS DESCRIPTION OPERATING STATIONS EMERGENCY PREPAREDNESS PROCESS DESCRIPTION TC NUMBER LEVEL N/A N/A

ML032591165

Text

Subject:

2.1. DAPAR

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