RS-03-124, Revisions to Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedure

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Revisions to Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedure
ML031740078
Person / Time
Site: Dresden, Byron, Braidwood, Clinton, Quad Cities, LaSalle  Constellation icon.png
Issue date: 06/19/2003
From: Jury J
AmerGen Energy Co, Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-03-124
Download: ML031740078 (22)
v • d • e


Text

m Exel n~M An Exe1on/British EneTgy Company www.exeloncorp.com AmerGen Energy Company, LLC uc ear 200 Exelon Way Exelon Generation Suite 345 4300 Winfield Road Kennett Square, PA 19348 Warrenvflle, IL 60555 10 CFR 50, Appendix E RS-03-124 June 19, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Clinton Power Station, Unit 1 Facility Operating License NPF-62 NRC Docket Nos, STN 50-461 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License NPF-1 1 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Quad Cities Nuclear Power Station, Units I and 2 Facility Operating License DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Revisions to the Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedure In accordance with 10 CFR 50, Appendix E, Section V, Implementing Procedures, Exelon Generation Company, LLC (EGC) and AmerGen Energy Company (AmerGen) are submitting changes to Exelon procedure, EP-AA-1 11, Emergency Classification and Protective Action Recommendations, for the Braidwood, Byron, Clinton Power, Dresden Nuclear Power, LaSalle County, and Quad Cities Nuclear Power Stations. The changes to the procedure are a result of

June 19, 2003 U. S. Nuclear Regulatory Commission Page 2 the addition of a generic Protective Action Recommendation flowchart for Three Mile Island and other administrative changes made for clarification purposes. No changes are being implemented that impact the determination of plant or dose-based Protective Action Recommendations for the Mid-West Regional Operating Group stations. These changes were implemented on May 23, 2003, and are being submitted within 30 days of implementation.

Attachment A provides EP-AA-1 11, Revision 6, Emergency Classification and Protective Action Recommendations.

Should you have any questions concerning this letter, please contact Ms. Marcia Lesniak at 630-657-2814.

Respectfully, Keith R. Jury Director Licensing Exelon Generation Company, LLC AmerGen Energy Company, LLC cc:

Regional Administrator NRC Region Ill (two copies)

NRC Senior Resident Inspector Braidwood Station NRC Senior Resident Inspector Byron Station NRC Senior Resident Inspector Clinton Power Station NRC Senior Resident Inspector Dresden Nuclear Power Station NRC Senior Resident Inspector LaSalle County Station NRC Senior Resident Inspector Quad Cities Nuclear Power Station Attachment A Exelon Nuclear Procedure, EP-AA-l 11, Revision 6, Emergency Classification and Protective Action Recommendations.

ATTACHMENT A EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATION

E EP-AA-111 xe t!~Ifl Revision 6 Page 1 of 19 Nuclear Level 2

- Reference Use EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS PURPOSE 1.1 This procedure provides guidance for the classification of an emergency condition.

1.2 This procedure provides guidelines for determining Protective Action Recommendations (PARs) to be made to offsite authorities during a General Emergency.

1.3 This procedure provides guidance for event termination and entry into Recovery.

Emergency Classification REFER to Section 4.1 Downgrading an Emergency Classification REFER to Section 4.2 Transition to Recovery/Termination REFER to Section 4.3 Plant Based PARs REFER to Section 4.4 Dose Based PARs REFER to Section 4.5 Overall PAR Determination REFER to Section 4.6 2.

TERMS AND DEFINITIONS 2.1 Classification Emergency classifications are divided into FIVE (5) categories or conditions, covering the postulated spectrum of emergency situations. The first four (4) emergency classifications are characterized by Emergency Action Levels (EALs) associated with Initiating Conditions and address emergencies of increasing severity. The fifth, the Recovery classification, is unique in that it may be viewed as a phase of the emergency, requiring specific criteria to be met and/or considered prior to its declaration. The classifications are as follows:

2.1.1 Unusual Event - Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs.

2.1.2 Alert - events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guideline (PAG) exposure levels.

EP-AA-111 Revision 6 Page 2 of 19 2.1.3 Site Area Emergency - Events are in progress or have occurred that involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA PAG exposure levels except near the site boundary.

2.1.4 General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA PAG exposure levels offsite for more than the immediate site area.

2.1.5 Recovery - That period when the emergency phase is over and activities are being taken to return the situation to a normal state (acceptable condition). The plant is under control and no potential for further degradation to the plant or the environment is believed to exist.

2.2 Emergency Action Levels (EALs) - a Pre-determined, Site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be: an instrument reading; an equipment status indicator; a measurable parameter; a discrete, observable event; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

2.3 Emergency Director (ED) - the Director ofthe facility in Command and Control.

One of the following: the Shift Emergency Director (CR), Station Emergency Director (TSC) or the Corporate Emergency Director (EOF).

2.4 EPA Protective Action Guideline - exposure levels determined by the Environmental Protection Agency for the evacuation of the offsite public following a release of radioactive materials. These levels have been established at one (1)

Rem TEDE ~sfive (5) Rem CDE Thyroid.

2.5 Imminent - mitigation actions have been ineffective and trended information indicates that the event or condition will occur within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2.6 Initiating Condition (IC)

- one of a predetermined subset of nuclear power plant conditions where either the potential exists for a radiological emergency, or such an emergency has occurred.

2.7 Potential

- mitigation actions are not effective and trended information indicates that the parameters are outside desirable bands and not stable or improving.

2.8 Protective Action Recommendations (PARs) - PARs are made by Exelon personnel whenever a General Emergency is declared. Additionally, if in the opinion of the Emergency Director, conditions warrant the issuance of PARs, a General Emergency will be declared (Exelon will not issue PARs for any accident classified below a General Emergency).

2.8.1 Offsite protective actions provided in response to a radioactive release include evacuation and taking shelter.

EP-AA-1 11 Revision 6 Page 3 of 19

1. Evacuation is the preferred action unless external conditions impose a greater risk from the evacuation than from the dose received.

2.

Exelon personnel do not have the necessary information to determine whether offsite conditions would require sheltering instead of an evacuation.

Therefore, an effort to base PARs on external factors (such as road conditions, traffic/traffic control, weather or offsite emergency worker response) should not be attempted.

2.8.2 At a minimum, a plant-based PAR to evacuate a 2-mile radius and 5 miles downwind, is issued at the declaration of a General Emergency based on NUREG-0654, Rev.1 Supplement 3. Depending on plant conditions (e.g., a LOSS of ~j[three fission product barriers per the EAL5), a PAR to evacuate a 5-mile radius and 10 miles downwind may be issued instead of the minimum PAR.

At a minimum, a plant-based PAR to evacuate a 5-mile radius is issued at the declaration of a General Emergency. Depending on plant conditions (e.g., a LOSS of~llthree fission product barriers per the EAL5), a PAR to evacuate a 10-mile radius may be issued instead of the minimum PAR.

1. The PAR must be provided to the State, and designated local agencies as applicable, within 15 minutes of (1) the classification of the General Emergency or (2) any change in recommended actions.
2. The PAR must be provided to the NRC as soon as possible and within 60 minutes of (1) the classification ofthe General Emergency or (2) any change in recommended actions.

2.8.3 The Emergency Director may elect to specify PARs for any combinations of

[MWROG] Subareas / [PB/LG] Sectors / [TM I] Radius or the entire EPZ (or beyond) regardless of plant and dose based guidance.

2.8.4 PARs should not be extended based on the results of dose projections unless the postulated release is likely to occur within a short period of time. Plant based PARs are inherently conservative such that expanding the evacuation zone as an added precaution would result in a greater risk from the evacuation than from the radiological consequences of a release. It also would dilute the effectiveness of the offsite resources used to accommodate the evacuation.

2.8.5 Protective actions taken in areas affected by plume deposition following the release are determined and controlled by offsite governmental agencies.

1.

Exelon is not expected to develop offsite recommendations involving ingestion or relocation issues following plume passage.

EP-AA-1 11 Revision 6 Page 4 of 19 2.

Exelon may be requested to provide resources to support the determination of post plume protective actions.

3.

RESPONSIBILITIES 3.1 The Shift Emergency Director (Shift Manager), when in Command and Control (C&C), has the non-delegable responsibility for classification of emergencies and final determination of PARs.

3.2 The Station Emergency Director, when in Command and Control, has the non-delegable responsibility for classification of emergencies and final determination of PARs.

3.3 The Corporate Emergency Director, when in Command and Control, has the non-delegable responsibility for final determination of PARs. Classification remains with the Station Emergency Director.

3.4 The TSC groups (e.g., Technical Support, Operations, Facility Support, RP/Chemistry) are responsible for monitoring and assessing conditions within their areas in support of classification.

3.5 The Shift Emergency Director (CR) I TechnicalManager (TSC) or Technical Support Manager (EOF), in the facility with the Emergency Director having Command and Control, is responsible for evaluating the plant-based PARs from the PAR flowcharts.

3.6 The designated Shift Dose Assessor (CR) I Radiation Protection Manager (TSC) / Radiation Protection Manager (EOF), in the facility with the Emergency Director having Command and Control, is responsible for evaluating the dose-based PARs from the results of the dose assessment analyses and field team surveys/samples.

EP-AA-111 Revision 6 PageS of 19 4.

MAIN BODY 4.1 Emergency Classification NOTE: Once indication of an abnormal condition is available, classification declaration must be made within 15 minutes. This time is available to ensure that the classification and subsequent actions associated with the classification, if warranted, are appropriate. It does not allow a delay of 15 minutes if the classification is recognized to be necessary. It is meant to provide sufficient time to accurately assess the emergency conditions and then evaluate the need for an emergency classification based on the assessment performed.

The decision to downgrade or terminate the event and enter Recovery is NOT time dependent.

NOTE: If the event escalates to a higher classification before the notification can be made for an initial (or previous) declaration, the time requirements in the previous note restart and notification for the first classification is not made.

4.1.1 When an abnormal condition is being evaluated, REFER to the appropriate Station EAL Matrix and PERFORM the following:

1. IDENTIFY the Unit Mode for the state of the plant prior to the abnormal condition (Operating Modes are identified in respective EALs).
2. REVIEW the Initiating Conditions (ICs) applicable to the operating mode as follows.

A. Starting with the highest (General Emergency) classification level on the left side of the matrix and continue to the lowest (Unusual Event) classification level on the right side of the matrix.

B. IF more than one IC applies to the event, SELECT the highest IC that may be applicable (from all of the ICs that were determined to have been met).

NOTE: Classification is made on a Unit basis. For events affecting both Units, the highest classification on either Unit is used for notification.

3.

REVIEW the EAL Threshold Values for the IC.

A. IF the EAL Threshold Values have been met or exceeded, THEN:

NOTE the EAL number associated with the IC.

DECLARE the event.

RETURN to the appropriate EP-AA-1 12 ERO position checklist and immediately begin notifications.

EP-AA-1 11 Revision 6 Page 6 of 19 B. IF the EAL Threshold Values have not been met or exceeded, THEN return to the appropriate EP-AA-112 ERO position checklist.

4.2 Downgrading an Emergency Classification 4.2.1 An Alert Classification may be downgraded to an Unusual Event if conditions warrant.

4.2.2 A Site Area Emergency or General Emergency shall ~

be downgraded to a lower classification.

1. A Site Area Emergency Classification, once declared, shall remain in effect until a General Emergency Classification is warranted or until such time as conditions warrant exiting to Recovery.
2. A General Emergency Classification, once declared, shall remain in effect until such time as conditions warrant exiting to Recovery.

4.3 Transition to Recovery/Termination 4.3.1 Complete the Termination/Recovery Checklist (Attachment 1).

1.

If conditions will allow for the termination of the emergency and entry into Recovery, exit this procedure and enter EP-AA-1 15, Recovery from a Classified Event.

2.

If conditions do not support termination of the emergency and entry into Recovery, continue following the guidance provided in Section 4.1.1.

4.4 Plant-Based Protective Action Recommendations (PARs) 4.4.1 Upon declaration of a General Emergency, EVALUATE the results of the plant-based PARs using the following attachments:

, Braidwood Plant-Based PAR Flowchart

, Byron Station Plant-Based PAR Flowchart

, Dresden Station Plant-Based PAR Flowchart

, LaSalle Station Plant-Based PAR Flowchart

, Quad Cities Station Plant-Based PAR Flowchart

, Clinton Station Plant-Based PAR Flowchart

, Limerick/Peach Bottom Plant-Based PAR Flowchart

, Three Mile Island Plant-Based PAR Flowchart 4.4.2 Continue to EVALUATE plant based PARs as Fission Product Barrier status or wind direction changes.

EP-AA-1 11 Revision 6 Page 7 of 19 4.5 Dose Assessment Based Protective Action Recommendations (PARs)

NOTE: If radiation monitor readings provide sufficient data for assessment, it is NOT appropriate to wait for field monitoring data to become available to confirm or expand a PAR within the 10-mile EPZ, NOTE: Many assumptions exist in dose assessment calculations, involving both source term and meteorological

factors, which make computer predictions over long distances highly questionable.

4.5.1 Dose projections are NOT required to support the decision process in the plant-based PAR Flowcharts. However, it is expected that a dose projection be performed as soon as possible by the facility in Command and Control at a General Emergency with a release in progress per EP-MW(MA)-110-200.

4.5.2 From the Control Room:

1.

If a release is in progress at a General Emergency classification, and time permits, then PERFORM an offsite dose assessment using the Quick Assessment dose model option.

4.5.3 From the TSC or EOF:

1.

PERFORM dose projections, using the Full Assessment dose model option, to determine whether the plant-based protective actions are adequate using the following methods as applicable:

2.

Monitored Release:

A. IF dose assessment results indicate the need to recommend actions beyond 10 miles, then DISPATCH Field Monitoring Teams to downwind areas to verify the calculated exposure rates prior to issuing PARs outside the 10 mile EPZ.

B. If a release is in progress, then ASSESS the calculated impact to determine whether the plant based PARs are adequate.

C. If a release is not in progress, then USE current meteorological and core damage data to project effluent monitor threshold values that would require 2, 5, and 10 mile evacuations.

RE-ESTABLISH threshold values whenever meteorological conditions or core damage assessment values change.

EP-AA-1 11 Revision 6 Page 8 of 19

3. Containment Leakage/Failure:

A.

If a release is in progress, THEN assess the calculated impact to determine whether the plant based PARs are adequate.

B. If a release is not in progress, then USE current meteorological and core damage data on various scenarios (design leakage, failure to isolate, catastrophic failure) to project the dose consequences and determine whether the plant based PARs are adequate.

4.

Field Survey Analysis: Actual field readings from Field Teams should be compared to dose assessment results and used as a dose projection method to validate calculated PARs and to determine whether the plant or release based protective actions are adequate.

5.

Release Point Analysis: Actual sample data from monitored or unmonitored release points should be utilized in conjunction with other dose assessment and projection methods to validate calculated PARs and to determine whether the plant based protective actions are adequate.

4.6 Overall Protective Action Recommendations (PARs) 4.6.1 EVALUATE the results of the plant based PARs and determine which Subareas/Sectors are to be evacuated.

TMI If projected or actual dose is determined to be> 1 Rem TEDE or 5 Rem CDE Thyroid at or beyond 5 miles, then EXTEND the minimum plant-based PAR to a 10-mile radius.

4.6.2 IF a release is in progress, THEN:

1. EVALUATE the results of the dose based PARs and determine if EPA Protective Action Guides (EPA PAGs) of 1 Rem TEDE or 5 Rem CDE Thyroid are exceeded and if additional Subareas/Sectors/Area require evacuation.
2. ADD any Subarea/Sector/Area requiring evacuation as determined by dose assessment to the plant based PARs.

4.6.3 IF no release is in progress, THEN:

1.

PERFORM dose projections on possible conditions as time permits to determine if PAGs could be exceeded.

2. CONSIDER adding any Subareas/Sectors/Areas requiring evacuation as determined by dose projection to the plant based PARs.

EP-AA-1 11 Revision 6 Page 9 of 19 4.6.4 COMBINE the results of the plant based and appropriate dose based PARs onto the State/Local notification form.

4.6.5 RETAIN any copies of plant and/or dose based PAR reports (Attachments 1-9 or dose code printouts).

5.

DOCUMENTATION None 6.

REFERENCES None 7.

ATTACHMENTS, Termination/Recovery Checklist, Braidwood Plant-Based PAR Flowchart, Byron Plant-Based PAR Flowchart, Dresden Plant-Based PAR Flowchart, LaSalle Plant-Based PAR Flowchart, Quad Cities Plant-Based PAR Flowchart, Clinton Plant-Based PAR Flowchart, Limerick/Peach Bottom Plant-Based PAR Flowchart, Three Mile Island Plant-Based PAR Flowchart

EP-AA-111 Revision 6 Page 10 of 19 ATTACHMENT I TERMINATION/RECOVERY CHECKLIST Page 1 of 2 True False Conditions no longer meet an Emergency Action Level and it appears unlikely that conditions will deteriorate.

List any EAL(s) which is/are still exceeded and a justification as to why a state of emergency is no longer applicable:

2.

All required notifications for entry into the Recovery Phase have been prepared per EP-AA-114 (NRC) and EP-MW(MA)-114-100.

STOP for Unusual Event.

CONTINUE for Alert, Site Area and General Emergency classifications 3.

Plant releases of radioactive materials to the environment are

~

U under control (within Tech Specs) or have ceased and the potential for a uncontrolled radioactive release is acceptably low.

4.

The radioactive plume has dissipated and plume tracking is no longer required. The only environmental assessment activities in progress are those necessary to determine the extent of deposition resulting from passage of the plume.

5.

In-plant radiation levels are stable or decreasing, and acceptable given the plant conditions.

6.

The reactor is in a stable shutdown condition and long-term core cooling is available.

7.

The integrity of the Reactor Containment Building is within Technical Specification limits.

EP-AA-1I1 Revision 6 Page 11 of 19 ATTACHMENT I TERMINATION/RECOVERY CHECKLIST Page 2 of 2 True False 8.

The operability and integrity of radioactive waste systems, U

U decontamination facilities, power supplies, electrical equipment and plant instrumentation including radiation monitoring equipment is acceptable.

9.

Any fire, flood, earthquake or similar emergency condition or threat U

U to security no longer exists.

10.

Any contaminated injured person has been treated and/or U

U transported to a medical care facility.

11.

Offsite conditions do not unreasonably limit access of outside U

U support to the station and qualified personnel and support services are available.

12.

Discussions have been held with Federal, State and County U

U agencies and agreement has been reached and coordination established to terminate the emergency.

It is not necessary that all responses listed above be TRUE; however, all items must be considered prior to event termination or entry into Recovery. For example, it is possible that some conditions remain which exceed an Emergency Action Level following a severe accident but entry into Recovery is appropriate. Additionally, other significant items not included on this list may warrant consideration such as severe weather.

Comments:

Approved: _______________________________________

Date/Time:

Emergency Director (in C&C of event classification)

ATTACHMENT 2 EP-AA-I II Revision 6 Page 12 of 19 BRAIDWOOD PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency Declared?

4, Yes Loss of FUEL Fission Product Barrier 4,

Yes Loss of RCS Fission Product Barrier 4,

Yes Loss of CONTAINMENT Fission Product Barrier 4,

Yes I Evacuate 5 Mile Radius & 10 L

Miles Downwind.

I No I

No I

No j

1N0 5 Mile Radius, 10 Miles Downwind WD (from)

Subareas 014°to 027°1,2,3,6,7,10,11,14,15 028°to 056°1,2,3,6,7, 10, 11, 14, 15, 16 057°to 073°1,2,3,6,7,10,11,12,14,15,16 074°to 083°1,2,3,6,7, 10, 11, 12, 14, 16 084°to 093°1,2,3,6, 7, 10, 11, 12, 14 094°to 104°1,2,3,6,7,8,10,11,12,14 105°to 121°1,2,3,4,6,7,8, 10, 11, 12, 14 122°to 149°1,2, 3,4,6, 7, 8, 10, 11, 14 150°to 163°1,2,3,4,6,7,10,11,14 164°to 181°1,2, 3,4, 5,6,7, 10, 11, 14 182°to 210°1,2,3,5,6,7,10,11,14 211°to 242°1,2,3,5,6,7, 10, 11, 13, 14 243°to 274°1,2,3,6,7,10,11,13,14 275°to 307°1,2,3,6,7,9,10,11,13,14 308°to 013°1,2,3,6,7,9,10,11,14 2 Mile Radius, 5 Miles Downwind WD (from)

Subareas 024°to 043°1,10,14 044°to 059°1, 10, 11, 14 060°to 112°1,10,11 113°to 136°1,7, 10, 11 137°to 153°1 7 10 154°to 179°1 2 7 10 180°to 204°1 2 10 205°to 236°1 2 3 10 237°to 289°1 3 10 290°to 329°1 3 6 10 330°to 354°1, 6, 10 355°to 023°1,6,10,14 NOTE: Ensure dose are evaluate based d when PARs a

release is in progress.

_1

ATTACHMENT 3 EP-AA-1 11 Revision 6 Page 13 of 19 BYRON PLANT-BASED PAR FLOWCHART Page I of I General Emergency Declared?

4, Yes Loss of FUEL Fission Product Barrier 4,

Yes Loss of RCS Fission Product Barrier 4,

Yes Loss of CONTAINMENT Fission Product Barrier 4,

Yes fivacuate 5 Mile Radius & 10 Miles Downwind.

5 Mile Radius, 10 Miles Downwind WD (from)

Subareas 022° to 051° 14, 17, 19, 20, 23, 25 052° to 082° 12, 14, 17, 19, 20, 23, 25 083° to 100°12, 17, 19, 20, 23, 25 101° to 125° 10, 12, 17, 19, 20, 23, 25 126° to 139° 10, 17, 19, 20, 23, 25 140° to 171°10, 17, 19, 20, 23, 25, 40 172° to 209° 17, 19, 20, 23, 25, 40 210° to 220°17, 19, 20, 23, 25, 39, 40 221° to 252°17, 19, 20, 23, 25, 27, 39 253° to 264°17, 19, 20, 23, 25, 27 265° to 285°17, 19, 20, 23, 25, 27, 28 286° to 326°17, 19, 20, 23, 25, 28 327° to 021°17, 19, 20, 23, 25 2 Mile Radius, 5 Miles Downwind WD (from)

Subareas 008° to 068° 19, 20, 23 069° to 128°19, 23 129° to 227°17,19,23 228° to 288°19,23 289° to 345°19, 23, 25 346° to 007° 19, 20, 23, 25 NOTE: Ensure dose based are evaluated when PARs a

release is in progress.

INo I

~

No jNo J

1N0

ATTACHMENT 4 EP-AA-1 11 Revision 6 Page 14 of 19 DRESDEN PLANT-BASED PAR FLOWCHART Page I of I General Emergency Declared?

4, Yes Loss of FUEL Fission Product Barrier 4,

Yes I

No Loss of RCS Fission Product Barrier 4,

Yes Loss of CONTAINMENT Fission Product Barrier 4,

Yes Evacuate 5 Mile Radius & 10 L

Miles Downwind.

I 5 Mile Radius, 10 Miles Downwind WD (from)

Subareas 002°to 026°1,3,4,7,9,10,11,12 027°to 044°1,3,4,7,8,9, 11, 12 045°to 068°1, 3, 4, 7, 8, 9, 12 069°to 083°1, 2, 3, 4, 5, 7, 8, 9, 12 084°to 092°1,2,3,4,5,7,9, 12 093°to 112°1,2,3,4,7,9,12 113°to 143°1,2,3,4,6,7,9, 12 144°to 177°1,3,4,6,7,9, 12 178°to 199°1, 3, 4, 6, 7, 9, 12, 13 200°to 225°1,3,4,7,9, 12, 13 226°to 249°1,3,4,7,9, 12, 13, 14 250°to 266°1,3,4,7,9, 12, 14 267°to 286°1,3,4,7,9, 12, 14, 15 287°to 321°1, 3,4,7,9, 12, 15 322°to 344°1,3,4,7,9, 12, 15, 16 345°to 353°1,3,4,7,9, 10, 12, 15, 16 354°to 001°1, 3, 4, 7, 9, 10, 12, 16 2 Mile Radius, 5 Miles Downwind WD (from)

Subareas 002°to 046°1 3. 4 7 047°to 182°1 3.4 183°to 292°1 3 4 12 293°to 299°1 3 4 300°to 338°1 3 4 9 339°to 001°1,3,4,7,9 NOTE:

Ensure dose based PARs are evaluated when a release is in progress.

I I

ATTACHMENT 5 EP-AA-1II Revision 6 Page 15 of 19 LASALLE PLANT-BASED PAR FLOWCHART Page 1 of I j-~

~No I

Th~

4, Yes Evacuate 5 Mile Radius & 10 L

Miles Downwind.

5 Mile Radius, 10 Miles Downwind WD (from)

Subareas 002°to 026°1 2 3 4 5 027°to 056°I 2 3 4 057°to 076°1 2 3 4 7 077°to 096°1 2 3 7 097°to 116°1 2 3 7 8 117°to 121°1,2,3,8 122°to 149°1,2,3,8,11 150°to 178°1, 2, 3, 10, 11 179°to 197°1,2,3, 10 198°to 218°1, 2, 3, 6, 10 219°to 233°1,2,3,6,9,10 234°to 242°1, 2, 3, 6, 9, 13 243°to 265°1, 2, 3, 9, 13 266°to 281°1, 2, 3, 13 282°to 316°1,2,3, 13, 17 317°to 342°1, 2, 3, 5, 17 343°to 001°1, 2, 3, 5 2 Mile Radius, 5 Miles Downwind WD (from)

Subareas 019°to 035°1.2.3 036°to 168°1 3

169°to 301°1 302°to 018°1, 2 NOTE:

Ensure dose based PARs are evaluated when a release is in progress.

General Emergency Declared?

I No I

4, Yes Loss of FUEL Fission Product Barrier 4,

Yes Loss of RCS Fission Product Barrier 4,

Yes Loss of CONTAINMENT Fission Product Barrier

ATTACHMENT 6 EP-AA-I II Revision 6 Page 16 of 19 QUAD CITIES PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency No Declared?

I 4,

Yes Loss of FUEL Fission I....!5L.

Product Barrier 4,

Yes Loss of RCS Fission Product Barrier 4,

Yes I

No Loss of CONTAINMENT No Fission Product Barrier Yes Evacuate SMile Radius & 10 Miles Downwind.

5 Mile Radius, 10 Miles Downwind WD (from)

Illinois Iowa 002° to 025° 1, 2, 3, 6 1, 2, 3, 4, 5, 6, 12 026° to 031° 1,2,3 1,2, 3,4, 5,6, 12 032° to 049° 1,2,3 1,2,3,4,5,6,10,12 050° to 058° 1, 2, 3 1, 2, 3,4, 5,6, 8, 10, 12 059° to 075° 1, 2, 3 1, 2, 3, 4, 5, 6, 8, 10 076° to 087° 1,2,3 1,2, 3, 4, 5, 6,8 088° to 106° 1,2,3 1,2, 3, 4, 5, 6, 7,8 107° to 116° 1,2,3 1,2,3,4,5,6,7 117° to 146° 1,2,3 1,2, 3, 4, 5, 6, 7,9 147° to 169° 1,2,3 1,2,3,4,5,6,9 170° to 186° 1,2,3 1,2,3,4,5,6,9,11 187° to 215° 1,2,3 1,2,3,4,5,6,11 216° to 229° 1,2,3,4 1,2, 3,4, 5,6, 11 230° to 239° 1,2,3,4 1,2, 3, 4, 5,6 240° to 267° 1, 2, 3, 4, 5 1, 2, 3, 4, 5, 6 268° to 296° 1,2,3,5 1,2, 3, 4, 5,6 297° to 318° 1,2,3,5,6 1,2,3,4,5,6 319° to 001° 1,2,3,6 1,2,3,4,5,6

_1 I

4 WD (from)

Illinois Iowa 009° to 024° 1,3 1,2,6 025° to 029° 1,3 1,2,4,6 030° to 081° 1 1,2,4,6 082° to 090° 1 1, 2, 3, 4,6 091° to 116° 1 1,2,3,4 117° to 165° 1 1,2,3 166° to 186° 1 1235 187° to 215° 1 125 216° to 240° 12 125 241° to 289° 12 12 290° to 318° I, 2, 3 1, 2 319° to 008° 1,3 1,2 NOTE:

Ensure dose based PARs are evaluated when a release is in progress.

2 Mile Radius, 5 Miles Downwind

ATTACHMENT 7 EP-AA-I II Revision 6 Page 17 of 19 CLINTON PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency Declared?

Yes Loss of FUEL Fission No Product Barrier Loss of RCS Fission 1

No Product Barrier 4,

Yes Yes I

5 Mile Radius, 10 Miles Downwind WD (from)

Subareas 021°to 048°1 5 6 049°to 066°1 6 067°to 090°1 6 7 091°to 094°1 7 095°to 132°1 7 8 133°to 157°1 2 8 158°to 196°1 2 197°to 228°1 2 3 229°to 251°1 3 252°to 281°1 3 4 282°to 308°1 4 309°to 338°1 4 5 339°to 020°1, 5 4

NOTE: Ensure dose based PARs are evaluated when a release is in progress.

I 4,

Yes Loss of CONTAINMENT Fission Product Barrier

ATTACHMENT 8 EP-AA-III Revision 6 Page 18 of 19 General Emergency No Declared?

Yes LOSS of FUEL Fission No Product Barrier Yes LOSS of RCS Fission No Product Barrier Yes LOSS of CONTAINMENT No Fission Product Barrier Yes TEvacuate 2 Mile Radius & 5 Miles Downwind.

NOTE:

Ensure dose-based PARs are evaluated when a release is in progress.

REFER to EP-AA-l 11, Section 4.5.1.

WIND DIRECTION (FROM)

DOWNWIND SECTOR(S)*

WIND DIRECTION (FROM)

DOWNWIND SECTOR(S)*

355 to 005 SSEIS /55W 175 to 185 NNW/N /NNE 006to017 SSEIS!SSW/SW 186to 197 NNWIN!NNEINE 018to027 S/SSW/SW 198to207 N/NNE/NE 028 to 039 S /SSWISWIWSW 208to 219 N /NNE/ NE/ENE 040 to 050 SSW /SW / WSW 220 to 230 NNE / NE / ENE 051 to 062 SSW/SWIWSW/W 231 to 242 NNE / NE! ENEI E 063 to 072 Sw, WSW / W 243 to 252 NE / ENE I E 073 to 084 SW/WSW/W/WNW 253 to 264 NE / ENE I El ESE 085 to 095 WSW / WI WNW 265 to 275 ENE/ El ESE 096 to 107 WSW/W/WNW/NW 276 to 287 ENE/EIESE/SE 108 to 117 W/ WNW I NW 288 to 297 E / ESE / SE 118to129 W/WNW/NWINNW 298to309 EIESE!SEISSE 130to140 WNW/NWINNW 310to320 ESEISE/SSE 141 to 152 WNW/NWINNWIN 321 to 332 ESEISEISSEIS 153 to 162 NW/ NNW /N 333 to 342 SE I SSE IS 163 to 174 NW/NNW/ NI NNE 343 to 354 SE/SSE/S /55W

  • BOLD refers to affected Sector(s). These sectors are based on dose model stability class D, and in some cases, an extra sector was included for conservatism.

LIMERICK/PEACH BOTTOM PLANT-BASED PAR FLOWCHART Page 1 of I 4,

1N0 I

EP-AA-1 II Revision 6 Page 19 of 19 ATTACHMENT 9 THREE MILE ISLAND PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency Declared?

1 YES LOSS of FUEL CLAD Fission Product Barrier?

YES LOSS of REACTOR COOLANT SYSTEM Fission Product Barrier?

YES LOSS of PRIMARY CONTAINMENT Fission Product Barrier?

(LOSS of ALL ~Baniers)

EVACuATE 10-Mile Radius YES

~NO No PAR Required j.

NOTE:

Ensure dose-based PARs are evaluated when a release is in progress.

REFER to EP-AA-lll, Section 4.5.1.

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