Text

to Emergency Plan Implementing Procedure EP-PS-244, Dose Assessment Staffer.
	ML031960066
Person / Time
Site:	Susquehanna
Issue date:	06/24/2003
From:	; Document Control Desk
To:	; Susquehanna
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Jun. 24, 2003 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-29945 USER INFORMATIONio-N Name: RC OSE M) EMPL#:28401 CA#:0363 Address:

Phon 254-3194 TRANSMITTAL INFORMATION:

TO: _ 06/24/2003 LOCATION: DOCUMENT CONTROL DESK . . ...

FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

244 - 244 - DOSE ASSESSMENT STAFFER REMOVE MANUAL TABLE OF CONTENTS DATE: 04/22/2003

ADD MANUAL TABLE OF CONTENTS DATE: 06/23/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-244 REPLACE: REV:6 REPLACE: REV:6 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

(a Tab 1 EP-PS-244-1 SHIFT TAKEOVER CHECKLIST

1. Accident Status: (DASU)

a. Current Emergency Classification: Norie Unusual Event Alert Site AArea General EAL #

b. Affected Unit(s): 1 2 Both None

c. Onsite Emergency Actions: 0 None 0 Local Area Evacuation 0 Site Accountability O Evacuation of non-essential personnel

d. Plant Status:

e. Current PAR:

f. Last transmitted PAR form: Number: Time:

g. Last DEP/BRP Communication Time: _

3. MIDAS Information: (DAST)

a. Accident dose calculation method in use: Menu B Menu C Menu D Menu E-W Menu G

b. Accident Source Term Selection: ATWS Coolant Activity Leak (LOCA) DP-No Fuel Damage (LOCA) Cladding Failure (LOCA) Fuel Melt Fuel Handling Accident (Percent Clad Failure or Fuel Melt: _)

EP-AD-000-217, Revision 3, Page 1 of 2

(. (

Tab 1 EP-PS-244-1 C. Projected Doses (TEDE): @ EPB. _ _2i ml @ lomi

d. Proj. Doses (THY CDE): @ EPB- _ 2_imi @ lomil

e. Has release occurred or is one in progress? Y N If yes: Gaseous Liquid

f. Release type: _ Monitored _ Unmonitored

4. Field Data: (FTD)

a. Status of Monitoring Teams:

Team Name Status

b. Measured Field Dose Rates:

c. Meteorological Conditions:

Wind From Wind Speed Affected Sector Stability Class Precipitation: None L M H EP-AD-000-217, Revision 3, Page 2 of 2

Tab 3 EP-PS-244-3 EMERGENCY CLASSIFICATION CHECK EZ 1.0 TIMING OF CLASSIFICATION 0o 1.1 UNUSUAL EVENT An UNUSUAL EVENT shall be declared within 15 minutes of having information necessary to make a declaration.

01 1.2 ALERT An ALERT shall be declared within 15 minutes of havingliformation necessary to make a declaration.

0 1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY shall be declared within 15 minutes of having information necessary to make a declaration.

El 1.4 GENERAL EMERGENCY A GENERAL EMERGENCY. shall be declared within 15 minutes of having information necessary to make a declaration.

EP-AD-000-200, Revision 19, Page 1 of 38

Tab 3 EP-PS-244-3 CLASSIFICATION OF EMERGENCY CONDITIONS USE OF EMERGENCY CLASSIFICATION MATRIX NOTE: CONFIRM THAT INDICATORS AND/OR ALARMS REFLECT ACTUAL CONDITIONS PRIOR TO TAKING ACTION BASED ON THE INDICATOR OR ALARM.

The matrix is worded in a manner that assumes parameter values indicated are the actual conditions present in the plant.

The matrix is designed to make it possible to precisely classify an abnormal occurrence into the proper emergency classification based on detailed Emergency Action Level (EAL) descriptions.

It is impossible to anticipate every abnormal occurrence. Therefore, before classifying any abnormal occurrence based on the EALs in the matrix, one should verify that the general conditions prevalent in-plant and offsite meet the general class description of the emergency classification. In addition, prior to classification, one should be aware of the ramifications in-plant and particularly offsite of that classification. Special consideration of offsite consequences should be made prior to declaring a GENERAL EMERGENCY.

EP-AD-000-200, Revision 19, Page 2 of 38

Tab 3 EP-PS-244-3 CLASS DESCRIPTIONS UNUSUAL EVENT - Events that are occurring 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 systems occurs.

ALERT - Events that are occurring 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 EPA Protective Action Guideline exposure levels.

SITE AREA EMERGENCY - Events that are occurring or have occurred which involve actual or imminent major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except inside the emergency planning boundary.

GENERAL EMERGENCY - Events that are occurring or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Expectation is that releases will exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary.

EP-AD-000-200, Revision 19, Page 3 of 38

Tab 3 EP-PS-244-3 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE 1 AIRCRAFT/TRAIN ACTIVITY ............................................... 5 2 CONTROL ROOM EVACUATION ................ .............................. 6 3 FUEL CLADDING DEGRADATION .................. ............................ 7 4 GENERAL.................................................................................................... 10 5 INJURED/CONTAMINATED PERSONNEL .............................................. 11 6 IN-PLANT HIGH RADIATION ............................................... 12 7 LOSS OF AC POWER ............................................... 13 8 LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS ................... 14

. 9 LOSS OF DC POWER .............................................. 15 10 LOSS OF DECAY HEAT REMOVAL CAPABILITY ....................................... 16 11 LOSS OF REACTIVITY CONTROL .............................................. 17 12 LOSS OF REACTOR VESSEL INVENTORY .............................................. 19 13 NATURAL PHENOMENA .................................. 21 14 ONSITE FIRE/EXPLOSION ................................. 23 15 RADIOLOGICAL EFFLUENT ................................. 25 16 SECURITY EVENT .................................. 29 17 SPENT FUEL RELATED INCIDENT ................................. 31 18 STEAM LINE BREAK .................................. 33 19 TOXIC/FLAMMABLE GASES ................................. 36 20 TECHNICAL SPECIFICATION SAFETY LIMIT ................................. 37 21 DRY FUEL STORAGE .................................. 38 EP-AD-000-200, Revision 19, Page 4 of 38

Tab 3 EP-PS-244-3 I - AIRCRAFTITRAIN ACTIVITY UNUSUAL EVENT EAL# 1.1 Aircraft crash or train derailment onsite as indicated by:

Visual observation or notification received by control room operator.

ALERT EAL# 1.2 Aircraft or missile strikes a station structure as indicated by:

Direct observation or notification received by control room operator.

SITE AREA EMERGENCY EAL# 1.3 Severe damage to safe shutdown equipment from aircraft crash or missile impact when not in cold shutdown, determined by:

(A and B and C)

A. Direct observation or notification received by control room operator.

and B. Shift Supervisor evaluation.

and C. Reactor Coolant temperature greater than 200OF as indicated on Panel 1C651 (2C651).

GENERAL EMERGENCY EAL# 1.4 None.

EP-AD-000-200, Revision 19, Page 5 of 38

Tab 3 EP-PS-244-3 2 - CONTROL ROOM EVACUATION UNUSUAL EVENT EAL# 2.1 None.

ALERT EAL# 2.2 Control Room evacuation as indicated by:

(A and B)

A. Initiation of control room evacuation procedures.

and B. Establishment of control of shutdown systems from local stat.ons.

SITE AREA EMERGENCY EAL# 2.3 Delayed Control Room Evacuation as indicated by:

(A and B)

A. Initiation of control room evacuation procedures.

and B. Shutdown systems control at local stations not established Within 15 minutes.

GENERAL EMERGENCY EAL# 2.4 None.

EP-AD-000-200, Revision 19, Page 6 of 38

Tab 3 EP-PS-244-3 3 - FUEL CLADDING DEGRADATION UNUSUAL EVENT EAL# 3.1 Core degradation as indicated by:

(A or B)

A. Valid Off-gas Pre-treatment Monitor high radiation alarm annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).

or B. Reactor coolant activity, determined by sample analysis greater than or equal to 2 gCi/cc of 1-131 equivalent.

ALERT EAL# 3.2 Severe fuel cladding degradation as indicated by:

(A or B or C or D)

A. Valid Off-gas Pre-treatment monitor High-High radiation alarm annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).

or B. Valid Reactor coolant activity greater than 300 pLCi/cc of equivalent 1-131, as determined by sample analysis.

or C. Valid Main Steam Line High radiation trip annunciation or indication on Panel 1C651 (2C651).

or D. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 200 R/hr. (An 8R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 7 of 38

Tab 3 EP-PS-244-3 3 - FUEL CLADDING DEGRADATION (continued)

SITE AREA EMERGENCY EAL# 3.3 Severely degraded core as indicated by:

(A or B)

A. Reactor coolant activity greater than 1,000 gCi/cc of equivalent 1-131 as determined by sample analysis.

or B. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 400 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 8 of 38

Tab 3 EP-PS-244-3 3 - FUEL CLADDING DEGRADATION (continued)

GENERAL EMERGENCY EAL# 3.4.a Fuel cladding degradation. Loss of 2 out of 3 fission product barriers (fuel cladding and reactor coolant pressure boundary) with potential loss of the third barrier (primary containment) as indicated by:

(A or B)

A. (land 2)

1. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 400 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

and

2. (a or b or c)

a. Containment pressure greater than 40.4 PSIG, indicated on Panel 1C601 (2C601).

or

b. A visual inspection of the containment indicates a potential for loss of containment (e.g. anchorage or penetration failure, a crack in containment concrete at tendon).

or

c. Other indications of potential or actual loss of primary containment.

or B. (1 and 2)

1. Reactor coolant activity greater than 1,000 +/-lCi/cc of . equivalent 1-131 as determined by sample analysis.

and

2. Actual or potential failure of reactor coolant isolation valves to isolate a coolant leak outside containment as determined by valve position indication on Panel 1C601 (2C601) or visual inspection.

OR EAL# 3.4.b Core melt as indicated by:

(A and B)

A. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 2000 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

and B. Containment high pressure indication or annunciation on Panel 1C601 (2C601).

EP-AD-000-200, Revision 19, Page 9 of 38

Tab 3 EP-PS-244-3 4-GENERAL UNUSUAL EVENT EAL# 4.1 Plant conditions exist that warrant increased awareness on the part of plant operating staff or state and/or local offsite authorities as indicated by:

Events that are occurring 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 systems occurs.

ALERT EAL# 4.2 Other plant conditions exist that warrant precautionary activation of PPL, State, County, and local emergency centers as indicated by:

Events that are occurring 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 EPA Protective Action Guideline exposure levels.

SITE AREA EMERGENCY EAL# 4.3 Other plant conditions exist that warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site as indicated by:

Events that are occurring or have occurred which involve actual or imminent major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except inside the emergency planning boundary.

GENERAL EMERGENCY EAL# 4.4 Other plant conditions exist, from whatever, source, that make release of large amounts of radioactivity in a short time period available as indicated by:

Events that are occurring or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Expectation is that releases will exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary.

EP-AD-000-200, Revision 19, Page 10 of 38

Tab 3 EP-PS-244-3 5.- INJUREDICONTAMINATED PERSONNEL UNUSUAL EVENT EAL# 5.1 Transportation of externally contaminated injured individual from site to offsite medical facility as deemed appropriate by Shift Supervisor.

ALERT EAL# 5.2 None.

SITE AREA EMERGENCY EAL# 5.3 None.

GENERAL EMERGENCY EAL# 5.4 None.

EP-AD-000-200, Revision 19, Page 11 of 38

Tab 3 EP-PS-244-3 6 - IN-PLANT HIGH RADIATION UNUSUAL EVENT EAL# 6.1 Unanticipated or unplanned concentrations of airborne activity exist in normally accessible areas, which are not due to planned maintenance activities, as indicated by:

Concentrations exceed 500 times the DAC values of 10CFR20 Appendix B, Table I values for a single isotope, or for multiple isotopes where CA + C + CC C 500 DACA DAC 8 DACC DACN ALERT EAL# 6.2 Unexpected in-plant high radiation levels or airborne contamination which indicates a severe degradation in the control of radioactive material as indicated by:

Area Radiation Monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).

SITE AREA EMERGENCY EAL# 6.3 None.

GENERAL EMERGENCY EAL# 6.4 None.

N-EP-AD-000-200, Revision 19, Page 12 of 38

Tab 3 EP-PS-244-3 7 - LOSS OF AC POWER UNUSUAL EVENT EAL# 7.1 Loss of offsite power or loss of all onsite AC power supplies as indicated by:

(A or B)

A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.

or B. Failure of all diesel generators to start or synchronize to the emergency buses by indication or annunciation on Panel OC653.

ALERT EAL# 7.2 Loss of all offsite power and all onsite AC power supplies as indicated by:

(A and B)

A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.

and B. Failure of all diesel generators to start or synchronize to the emergency buses by annunciation or indication on Panel OC653.

SITE AREA EMERGENCY EAL# 7.3 Loss of all offsite power and loss of all onsite AC power supplies for greater than 15 minutes as indicated by:

(A and B and C)

A. Loss of offsite power.

and B. Failure of all diesel generators to startup or synchronize to the emergency buses by indication or annunciation on OC653.

and C. The above conditions exist for greater than 15 minutes.

GENERALEMERGENCY EAL# 7.4 None.

EP-AD-000-200, Revision 19, Page 13 of 38

Tab 3 EP-PS-244-3 8 - LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS UNUSUAL EVENT EAL# 8.1 None.

ALERT EAL# 8.2 Loss of all control room annunciators as indicated by:

In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer are lost, or insufficient annunciators are available to safely operate the unit(s) without supplemental observation of plant systems.

SITE AREA EMERGENCY EAL# 8.3 All annunciators lost and plant transient initiated while annunciators are lost as indicated by:

(A and B)

A. In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer are lost, or insufficient annunciators are available to safely operate the unit(s) without supplemental observation of plant systems.

and B. (1 or2or3or4)

1. Low-Low reactor water level indication on Panel 1C651- (2C651) followed by ECCS initiation on Panel 1C601 (2C601).

or

2. Reactor coolant temperature change greater than 100°F per hour indication on recorder TR-1 R006 on Panel 1C007 (2C007) (Reactor Building elevation 683').

or

3. High reactor pressure indication on Panel 1C651 (2C651) and followed by scram indication on Panel 1C651 (2C651).

or

4. Any indication that transient has occurred or is in progress.

GENERAL EMERGENCY EAL# 8.4 None.

EP-AD-000-200, Revision 19, Page 14 of 38

Tab 3 EP-PS-244-3 9 - LOSS OF DC POWER UNUSUAL EVENT EAL# 9.1 None.

ALERT EAL# 9.2 Loss of onsite vital DC power as indicated by:

(A and B)

A. Less than 210 volts on the 250 VDC main distribution Panel buses, 1D652 (2D652) and 1D662 (2D662) as indicated by trouble alarms on Panel 1C651 (2C651).

and B. Less than 105 volts on the 125 VDC main distribution buses 0D612 (2D612), 1D622 (2D622), 1D632 (2D632), and 1D642 (2D642) as indicated by trouble alarms on Panel 1C651 (2C651).

NOTE: Buses are not tripped on undervoltage condition.

SITE AREA EMERGENCY EAL# 9.3 Loss of all vital onsite DC power sustained for greater than 15 minutes as indicated by:

(A and B and C)

A. Less than 210 volts on the 250 VDC main distribution Panel buses, 1D652 (2D652) and 1D662 (2D662) as indicated by trouble alarms on Panel 1C651 (2C651).

and B. Less than 105 volts on the 125 VDC main distribution buses 1D612 (2D612), 1D622 (20622), 1D632 (2D632), and 11642 (2D642) as indicated by trouble alarms on Panel I C651 (2C651).

and C. The above condition exists for greater than 15 minutes.

NOTE: Buses are not tripped on undervoltage condition.

GENERAL EMERGENCY EAL# 9.4 None.

EP-AD-000-200, Revision 19, Page 15 of 38

Tab 3 EP-PS-244-3 10 - LOSS OF DECAY HEAT REMOVAL CAPABILITY UNUSUAL EVENT EAL# 10.1 None.

ALERT EAL# 10.2 Inability to remove decay heat while in plant condition 4, inability to maintain the plant in cold shutdown as indicated by:

Inability to maintain reactor coolant temperature less than 200OF with the reactor mode switch in shutdown; exception is when testing per Special Test Exception TS 3.10.1 which allows maximum temperature of 212 0F.

SITE AREA EMERGENCY EAL# 10.3 Inability to remove decay heat while the plant is shutdown as indicated by:

(A and B and C)

A. Reactor Mode switch in shutdown.

and B. Reactor Coolant System temperature greater than 200OF and rising.

and C. Suppression Pool temperature greater than 120OF and rising.

GENERAL EMERGENCY EAL# 10.4 Inability to remove decay heat while the plant is shutdown with possible release of large amounts of radioactivity as indicated by:

(A and B and C)

A. Reactor mode switch in shutdown.

and B. Reactor coolant system temperature greater than 200OF and rising.

and C. Suppression pool temperature greater than 2900 F indicated on the computer output (MAT 12,13,14,15 or 16).

EP-AD-000-200, Revision 19, Page 16 of 38

Tab 3 EP-PS-244-3 11 - LOSS OF REACTIVITY CONTROL UNUSUAL EVENT EAL# 11.1 Inadvertent Criticality as indicated by:

Unexpected increasing neutron flux indication on Panel 1C651 (2C651).

ALERT EAL# 11.2 Failure of the Reactor Protection System or the Alternate Rod Insertion System to initiate and complete a scram that brings the reactor subcritical as indicated by:

(A or B) and (C and D and E)

A. Trip of at least one sub-channel in each trip system (RPS A and RPS B) as indicated by annunciators and trip status lights on Panel 1C651 (2C651).

or B. Trip of both trip systems (ARI A and ARI B) as indicated by annunciators on Panel 1C601 (2C601).

and C. Failure of control rods to insert, confirmed by the full core display indication on Panel 1C651 (2C651) or process computer indications.

and D. Failure to bring the reactor subcritical confirmed by neutron count rate on the neutron monitoring indication on Panel 1C651 (2C651).

and E. Reactor power >5% as indicated on Panel 1C651 (2C651).

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 17 of 38

Tab 3 EP-PS-244-3 11 - LOSS OF REACTIVITY CONTROL (continued)

SITE AREA EMERGENCY EAL# 11.3 Loss of functions needed to bring the reactor subcritical and loss of ability to bring the reactor to cold shutdown as indicated by:

(A and B and C and D)

A. Inability to insert sufficient control rods to bring the reactor subcritical as indicated by count rate on the neutron monitoring instrumentation on Panel 1C651 (2C651).

and B. (1 or2)

Failure of both loops of standby liquid control to inject into the vessel indicated by:

1. Low pump discharge pressure indication on Panel 1C601 (2C601).

or

2. Low flow indication on Panel 1C601 (2C601).

and C. Reactor coolant temperature greater than 2000F, indicated on Panel 1C651 (2C651).

and D. Reactor power >5% indicated on Panel 1C651 (2C651).

GENERAL EMERGENCY EAL# 11.4 Loss of functions needed to bring the reactor subcritical and transient in progress that makes release of large amounts of radioactivity in a short period possible as indicated by:

(A or B) and (C and D)

A. Trip of at least one sub-channel in each trip system (RPS A and RPS B), indicated by annunciation or trip status lights on Panel 1C651 (2C651).

or B. Trip of both systems (ARI A and ARI B) as indicated by annunciators on Panel 1C601 (2C601).

and C. Loss of SLC system capability to inject, indicated by instrumentation on Panel 1C601 (2C601).

and D. Reactor power greater than 25% of rated, indicated on Panel 1C651 (2C651).

EP-AD-000-200, Revision 19, Page 18 of 38

Tab 3 EP-PS-244-3 12 - LOSS OF REACTOR VESSEL INVENTORY UNUSUAL EVENT EAL# 12.1 Valid initiation of an Emergency Core Cooling System (ECCS) System as indicated by:

(A or B)

A. Initiation of an ECCS System and low, low, low reactor water level (-129) annunciation or indication on Panel I C651 (2C651).

or B. Initiation of an ECCS System and High Drywell Pressure annunciation or indication on Panel 1C601 (2C601).

ALERT EAL# 12.2 Reactor coolant system leak rate greater than 50 gpm as indicated by:

(A or B)

A. Drywell floor drain sump A or B Hi-Hi alarm on Panel 1C601 (2C601) and 2 or more drywell floor drain pumps continuously running as indicated on Panel 1C601 (2C601).

or.

B. Other estimates of Reactor coolant system leakage indicating greater than 50 gpm.

SITE AREA EMERGENCY EAL# 12.3 Known loss of coolant accident greater than make-up capacity as indicated by:

Water level below (and failure to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 19 of 38

Tab 3 EP-PS-244-3 12- LOSS OF REACTOR VESSEL INVENTORY (continued)

GENERAL EMERGENCY EAL# 12.4.a Loss of coolant accident with possibility of imminent release of large amounts of radioactivity as indicated by:

Water level below (and failure to return to) top of active fuel for greater than 20 minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

OR EAL# 12.4.b Loss of Reactor Vessel inventory. Loss of 2 out of 3 fission product barriers (fuel cladding & reactor coolant pressure boundary) with potential loss of the third barrier (primary containment), as indicated by:

(A or B)

A. (1 and 2 and 3)

1. High drywell pressure annunciation or indication on Panel 1C601 (2C601).

and

2. (a or b or c)

a. Containment pressure exceeds 40.4 PSIG as indicated on Panel 1C601 (2C601).

or

b. A visual inspection of the containment indicates a potential or actual loss of containment (e.g. anchorage or penetration failure).

or

c. Containment isolation valve(s) fail to close as indicated by valve position indication on Panel 1C601 (2C601).

and

3. Reactor Vessel level drops below (and fails to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

or B. (1 and 2)

1. Failure of reactor pressure vessel isolation valves to isolate coolant break outside containment as indicated by valve position indication on Panel 1C601 (2C601) or visual inspection.

and

2. Reactor vessel level drops below (and fails to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

EP-AD-000-200, Revision 1I9, Page 20 of 38

Tab 3 EP-PS-244-3 13 - NATURAL PHENOMENA UNUSUAL EVENT EAL# 13.1 Natural phenomenon occurrence as indicated by:

(A or B or C)

A. Tornado impact on site.

or B. Hurricane impact on site.

or C. Earthquake detected by seismic instrumentation systems on Panel 0C696.

ALERT EAL# 13.2 Natural Phenomenon Occurrence as indicated by:

(A or B or C)

A. Tornado with reported wind velocities greater than 200 mph impacting on site.*

or B. Reported hurricane or sustained winds greater than 70 mph.*

or C. Earthquake at greater than operating basis earthquake (OBE) levels as indicated on Panel 0C696.

Telephone numbers for the National Weather Bureau are located in the Emergency Telephone Directory.

(CONTINUED ON NEXT PAGE)

-EP-AD-000-200, Revision 19, Page 21 of 38

Tab 3 EP-PS-244-3 13 - NATURAL PHENOMENA (continued)

SITE AREA EMERGENCY EAL# 13.3 Severe natural phenomenon occurrence, with plant not in cold shutdown, as indicated by:

(A and B)

A. Reactor Coolant Temperature greater than 200OF as indicated on Panel 1C651 (2C651).

and B. (1or2or3)

1. Reported hurricane or sustained winds greater than 80 mph.*

or

2. Earthquake with greater than Safe Shutdown Earthquake (SSE) levels as indicated on Panel OC696.

or

3. Tornado with reported wind velocities greater than 220 mph impacting on site.*

GENERAL EMERGENCY EAL# 13.4 None.

Telephone numbers for the National Weather Bureau are located in the Emergency Telephone Directory.

EP-AD-000-200, Revision 19, Page 22 of 38

Tab 3 EP-PS-244-3 14- ONSITE FIRE/EXPLOSION UNUSUAL EVENT EAL# 14.1 Significant fire within the plant as indicated by:

(A and B)

A. Activation of fire brigade by Shift Supervisor.

and B. Duration of fire longer than 15 minutes after time of notification.

OR Explosion inside security protected area, with no significant' damage to station facilities, as indicated by:

Visual observation or notification received by control room operator and Shift Supervisor evaluation.

ALERT EAL# 14.2 On-site Fire/Explosion as indicated by:

(A or B)

A. Fire lasting more than 15 minutes and fire is in the vicinity of equipment required for safe shutdown of the plant and the fire is damaging or is threatening to damage the equipment due to heat, smoke, flame, or other hazard.

or B. (1 and 2)

Explosion damage to facility affecting plant operation as determined by:

1. Direct observation or notification received by control room operator.

and

2. Shift Supervisor observation.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 23 of 38

Tab 3 EP-PS-244-3 14 - ONSITE FIRE/EXPLOSION (continued)

SITE AREA EMERGENCY EAL# 14.3 Damage to safe shutdown equipment due to fire or explosion has occurred when plant is not in cold shutdown, and damage is causing or threatens malfunction of equipment required for safe shutdown of the plant as determined by:

(A and B and C)

A. Direct observation or notification received by control room operator.

and B. Shift Supervisor evaluation.

and C. Reactor Coolant Temperature greater than 200OF as indicated on Panel 1C651 (2C651).

GENERAL EMERGENCY EAL# 14.4 None.

EP-AD-000-200, Revision 19, Page 24 of 38

Tab 3 EP-PS-244-3 15- RADIOLOGICAL EFFLUENT UNUSUAL EVENT EAL# 15.1 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 2 times the Technical Requirements Manual limits for 60 minutes or longer.

EAL# 15.1(1 or 2 or 3)

1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2.OE+6 gCi/min and that is sustained for 60 minutes or longer.

OR

2. Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary with a release duration of 60 minutes or longer resulting in dose rates of:

a) Noble gases >1000 mremlyear whole body, or b) Noble gases >6000 mremlyear skin, or c) 1-131, 1-133, H-3, and particulates with half lives >8 days >3000 mrem/yearto any organ (inhalation pathways only).

OR

3. Confirmed sample analyses for liquid releases indicates concentrations with a release duration of 60 minutes or longer in excess of two time the Technical Requirements Manual liquid effluent limits.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 25 of 38

Tab 3 EP-PS-244-3 15 - RADIOLOGICAL EFFLUENT (continued)

ALERT EAL# 15.2 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 200 times Technical Requirement Manual limits for 15 minutes or longer.

EAL# 15.2 (1 or 2 or 3)

1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2E+8 4Cimin and that is sustained for 15 minutes or longer.

OR _

2 Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary for 15 minutes or longer resulting in dose rates of:

a) Noble gases >1.OE+5 mrem/year whole body, or b) Noble gases >6.OE+5 mrem/year skin, or c) 1-131, 1-133, H-3, and particulates with half-lives >8 days >3.OE+5 mrem/year to any organ (inhalation pathways only).

OR

3. Confirmed sample analyses for liquid releases indicates concentrations in excess of 200 times the Technical Requirements Manual liquid effluent limits for 15 minutes or longer.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 26 of 38

Tab 3 EP-PS-244-3 15- RADIOLOGICAL EFFLUENT (continued)

SITE AREA EMERGENCY EAL# 15.3 Dose at the Emergency Plan boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mrem whole body TEDE or 500 mrem child thyroid CDE for the actual or projected duration of release.

EAL# 15.3 (1 or 2 or 3 or 4 or 5)

1. Valid Noble Gas vent stack monitor readings(s) that exceeds a total release rate 6.2E8 gCi/min for greater than 15 minutes and Dose Projections are not available.

Note: If the required dose projection cannot be completOd within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).

OR

2. Valid dose assessment using actual meteorology indicates projected doses greater than 100 mrem whole body TEDE or 500 mrem child thyroid CDE at or beyond the EPB.

OR

3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 100 mR/hr.

OR

4. Field survey results indicate Emergency Planning boundary dose rates exceeding 100 mR/hr expected to continue for more than one hour.

OR

5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 500 mrem for one hour of inhalation.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 27 of 38

Tab 3 EP-PS-244-3 15 - RADIOLOGICAL EFFLUENT (continued)

GENERAL EMERGENCY EAL# 15.4 Dose at the Emergency Planning Boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE for the actual or projected duration of the release using actual meteorology.

EAL# 15.4 (1 or 2 or 3 or 4 or 5)

1. Valid Noble Gas vent stack monitor readings(s) that exceed a total release rate of 6.2E9 iCimin for greater that 15 minutes and Dose Projections are not available.

Note: If the required dose projection cannot be completed within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).

OR

2. Valid dose assessment using actual meteorology indicates projected doses greater than 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE at or beyond the EPB.

OR

3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 1000 mR/hr.

OR

4. Field survey results indicate Emergency Planning Boundary dose rates exceeding 1000 mR/hr expected to continue for more than one hour.

OR

5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 5000 mrem for one hour of inhalation.

EP-AD-000-200, Revision 19, Page 28 of 38

Tab 3 EP-PS-244-3 16 - SECURITY EVENT UNUSUAL EVENT EAL# 16.1 Security threat or attempted entry or attempted sabotage as indicated by:

(A or B or C)

A. A report from Security of a security threat, attempted entry, or attempted sabotage of the owner controlled area adjacent to the site.

or B. Any attempted act of sabotage which is deemed legitimate in the judgment of the SHIFT SUPERVISOR/EMERGENCY DIRECTOR, and affects plant operation.

or C. A site specific credible security threat notification.

ALERT EAL# 16.2 Ongoing Security Compromise as indicated by:

(A or B)

A. A report from Security that a security compromise is at the site but no penetration of protected areas has occurred.

or B. Any act of sabotage which results in an actual or potential substantial degradation of the level of safety of the plant as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.

SITE AREA EMERGENCY EAL# 16.3 An ongoing adversary event threatens imminent loss of physical control of plant as indicated by:

(A or B)

A. Report from Security that the security of the plant vital area is threatened by unauthorized (forcible) entry into the protected area.

or B. Any act of sabotage which results in actual or likely major failures of plant functions needed for protection of the public as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 29 of 38

Tab 3 EP-PS-244-3 16 - SECURITY EVENT (continued)

GENERAL EMERGENCY EAL# 16.4 Loss of physical control of facilities as indicated by:

(A or B)

A. Report from Security that a loss of physical control of plant vital areas has occurred.

or B. Any act of sabotage which results in imminent significant cladding failure or fuel melting with a potential for loss of containment integrity or the potential for release of significant amounts of radioactivity in a short time as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.

EP-AD-000-200, Revision 19, Page 30 of 38

Tab 3 EP-PS-244-3 17 - SPENT FUEL RELATED INCIDENT UNUSUAL EVENT EAL# 17.1 Unanticipated or unplanned concentrations of airborne activity exist in normally accessible areas, which is not due to planned maintenance activities, as indicated by:

Concentrations exceed 500 times the DAC values of 10CFR20 Appendix B, Table I values for a single isotope, or full multiple isotopes where

_CA +_ C 8 CC CN > 500 DACA DACB DACC DACN

. ALERT EAL# 17.2 Unexpected in-plant high radiation levels or airborne contamination which indicates a severe fuel handling accident as indicated by:

Refuel floor area radiation monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 31 of 38

Tab 3 EP-PS-244-3 17 - SPENT FUEL RELATED INCIDENT (continued)

SITE AREA EMERGENCY EAL# 17.3.a Major damage to irradiated fuel with actual or clear potential for significant release of radioactive material to the environment as indicated by:

(A and B)

A. Dropping, bumping, or otherwise rough handling of a new OR irradiated fuel bundle with irradiated fuel in the pool.

and B. (1 or2)

1. Refueling floor area radiation monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).

or

2. Reactor Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.

OR EAL# 17.3.b Damage to irradiated fuel due to uncontrolled decrease in the fuel pool level to below the level of the fuel as indicated by:

(A and B)

A. (1 or2)

1. Uncovering of irradiated fuel confirmation by verification of significant leakage from spent fuel pool.

or

2. Visual observation of water level below irradiated fuel in the pool.

and B. (1 or2)

1. Refueling floor area radiation monitor annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).

or

2. Reactor Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.

GENERAL EMERGENCY EAL# 17.4 None.

EP-AD-000-200, Revision 19, Page 32 of 38

Tab 3 EP-PS-244-3 18 - STEAM LINE BREAK UNUSUAL EVENT EAL# 18.1 None.

ALERT EAL# 18.2 MSIV malfunction causing leakage as indicated by:

(A and B)

A. Valid MSIV closure signal or indication on Panel 1C601 (2C601).

and B. (1 or2)

1. Valid Main Steam Line flow indication on Panel 1C652 (2C652).

or

2. Valid Main Steam Line radiation indication on Panel 1C600 (2C600).

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 33 of 38

Tab 3 EP-PS-244-3 18 - STEAM LINE BREAK (continued)

SITE AREA EMERGENCY EAL# 18.3 Steam line break occurs outside of containment without isolation as indicated by:

(A or B or C or D)

A. (1 and 2)

1. Failure of both MSIVs in the line with the leak to close as indicated by position indication on Panel 1C601 (2C601).

and

2. (a orb)

a. High MSL flow annunciation on Panel 1C601 (2C601) or indication on Panel 1C652 (2C652).

or

b. Other indication of main steam leakage outside containment.

or B. (1 and 2)

1. Failure of RCIC steam isolation valves HV-F008 and HV-F007 to close as indicated on Panel 1C601 (2C601).

and

2. (aorborcordoreorf)

a. RCIC steamline pipe routing area high temperature annunciation on Panel 1C601 (2C601), or indication on Panel 1C614 (2C614).

or

b. RCIC equipment area high temperature annunciation on Panel 1C601 (2C601) or indication on Panel 1C614 (2C614).

or

c. RCIC steamline high flow annunciation on Panel 1C601 (2C601).

or

d. RCIC steamline tunnel ventilation high delta temperature annunciation on Panel 1C601 (2C601).

or

e. RCIC turbine exhaust diaphragm high pressure annunciation on Panel 1C601 (2C601).

or

f. Other indication of steam leakage from the RCIC system.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 34 of 38

Tab 3 EP-PS-244-3 18 - STEAM LINE BREAK (continued)

SITE AREA EMERGENCY (continued) or C. (1 and 2)

1. Failure of HPCI steam isolation valves HV-F002 and HV-F003 to close as indicated by position indicator on Panel 1C601 (2C601).

and

2. (a orb orc ord ore orf)

a. HPCI steamline pipe routing area high temperature annunciation on Panel 1C601 (2C601), or indication on Panel 1C614 (2C614).

or

b. HPCI equipment area high temperature annunciation on Panel 1C601 (2C601) or indication on Panel 1C614 (2C614).

or

c. HPCI steamline high flow annunciation on Panel 1C601 (2C601).

or

d. HPCI steamline tunnel ventilation high delta temperature annunciation on Panel 1C601 (2C601).

or

e. HPCI turbine exhaust diaphragm high pressure annunciation on Panel 1C601 (2C601).

or

f. Other indication of steam leakage from the HPCI system.

or D. Any other un-isolatable steam line breaks.

GENERAL EMERGENCY EAL# 18.4 None.

EP-AD-000-200, Revision 19, Page 35 of 38

Tab 3 EP-PS-244-3 19 - TOXIC/FLAMMABLE GASES UNUSUAL EVENT EAL# 19.1 Nearby or onsite release of potentially harmful quantifies of toxic or flammable material as indicated by:

Visual observation or notification received by the control room operator.

ALERT EAL# 19.2 Entry of toxic or flammable gases into the facility, with subsequent habitability problem as indicated by:

Visual observation, direct measurement, or notification received by the control room operator.

SITE AREA EMERGENCY EAL# 19.3 Toxic or flammable gases enter vital areas, restricting access and restricted access constitutes a safety problem, as determined by:

(A and B)

A. Shift Supervisor's evaluation.

and B. Visual observation, direct measurement, or notification received by control room operator.

GENERAL EMERGENCY EAL# 19.4 None.

EP-AD-000-200, Revision 19, Page 36 of 38

Tab 3 EP-PS-244-3 20 - TECHNICAL SPECIFICATION SAFETY LIMIT UNUSUAL EVENT EAL# 20.1 Abnormal occurrences which result in operator complying with any of the Technical Specification SAFETY LIMIT ACTION statements indicated by:

(A or B or C or D)

A. Exceeding THERMAL POWER, low pressure or low flow safety limit 2.1.1.1.

or B. Exceeding THERMAL POWER, high pressure and high flow safety limit 2.1.1.2.

or C. Exceeding REACTOR VESSEL WATER LEVEL safety limit 2.1.1.3.

or D. Exceeding REACTOR COOLANT SYSTEM PRESSURE sarety limit 2.1.2.

ALERT EAL# 20.2 None.

SITE AREA EMERGENCY EAL# 20.3 None.

GENERAL EMERGENCY EAL# 20.4 None.

EP-AD-000-200, Revision 19, Page 37 of 38

Tab 3 EP-PS-244-3 21 - DRY FUEL STORAGE UNUSUAL EVENT EAL# 21.1.a. Situations are occurring or have occurred during the transport of the irradiated spent fuel to the onsite storage facility, which jeopardize the integrity of the spent fuel or its container as indicated by:

(A or B)

A. Radiological readings exceed 2 R/hour at the external surface of any transfer cask or horizontal storage module.

or B. Radiological readings exceed 1 R/hour one foot away from the external surface of any transfer cask or horizontal storage module.

OR EAL# 21.1.b. Situations are occurring or have occurred at the irradiated spent fuel storage facility, which jeopardize the integrity of the dry cask storage system as indicated by:

(A or B)

A. Radiological readings exceed 2 R/hour at the external surface of any transfer cask or horizontal storage module.

or B. Radiological readings exceed 1 R/hour one foot away from the external surface of any transfer cask or horizontal storage module.

ALERT EAL# 21.2 None.

SITE AREA EMERGENCY EAL# 21.3 None.

GENERAL EMERGENCY EAL# 21.4 None EP-AD-000-200, Revision 19, Page 38 of 38

Tab 6 EP-PS-244-6 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE TABLE OF CONTENTS SECTION PAGE 1.0 EMERGENCY DOSE LIMITS 2 2.0 EMERGENCY EXPOSURE/ACCIDENTAL OVEREXPOSURE 3 3.0 PROTECTIVE ACTIONS 3 4.0 EMERGENCY EXPOSURE NOTIFICATION AND HEALTH CONSEQUENCE INVESTIGATION 7 EMERGENCY EXPOSURE EXTENSIONS 8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING AN EMERGENCY 12 NOTE: EMERGENCY EXPOSURE EXTENSION REQUEST FORM and POTASSIUM IODIDE TRACKING FORM can be found as Forms EP-AD-000-1 35 and EP-AD-000-141, respectively.

EP-AD-000-125, Revision 9, Page 1 of 13

Tab 6 EP-PS-244-6 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0 1.0 Limits for EMERGENCY doses.

Q 1.1 An EMERGENCY DOSE AUTHORIZATION (see EMERGENCY EXPOSURE EXTENSIONS) may be granted in order to protect facilities, and or equipment to substantially limit the escape of radioactive effluents or control fires. The maximum planned doses are:

1.1.1 Whole body (TEDE)(1) dose shall not exceed 10 rem.

1.1.2 Dose to any organ (CDE)( 2 ), including the skin and extremity (SDE)(3), shall not exceed 100 rem.

1.1.3 Dose to the lens of the eye shall not exceed 30 rem (LDE)<4).

o 1.2 An EMERGENCY dose authorization may be granted for life-saving actions or protection of large populations. The maximum doses are:

1.2.1 Planned whole body (TEDE)(1 ) doses shall not exceed 25 rem.

1.2.2 Planned dose to any organ (CDE)(2), including skin and extremity doses, shall not exceed 250 rem.

1.2.3 Dose to the lens of the eye shall not exceed 75 rem (LDE)(4).

1.3 RARE situations may occur in which a dose GREATER THAN those specified in SECTION 1.2 above for emergency dose would be unavoidable to carry out a lifesaving operation or to avoid extensive exposure of large populations. It is not possible to prejudge the risk that one should be allowed to take to save lives of others, therefore no upper limit has been established.

(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.

(2) The Committed Dose Equivalent to the thyroid from radioiodine.

(3) Shallow Dose Equivalent.

(4) Lens Dose Equivalent.

EP-AD-000-125, Revision 9, Page 2 of 13

Tab 6 EP-PS-244-6 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0 2.0 For any EMERGENCY EXPOSURE OR ACCIDENTAL OVEREXPOSURE, the assessment actions in step 2 of the EMERGENCY EXPOSURE EXTENSIONS must be performed.

3.0 PROTECTIVE ACTIONS a 3.1 Potassium Iodide 3.1.1 For thyroid doses that are strongly expected to exceed 10 rem (CDE) (2), ingestion of a KI dose of 130 mg (100mg - iodine) should be recommended, except as noted in paragraph 3.1.2, to personnel whose emergency assignment or qualifications do not allow other protective measures to be taken (e.g. respiratory protection, evacuation, relocation, etc.) to maintain the dose to the thyroid at less than 10 rem.

NOTE: HHS/FDA guidance is that adults over 40 years of age need take KI only in the case of a projected large internal radiation dose to the thyroid ( > 500 rem) to prevent hypothyroidism; the guidance is 10 rem for adults over age 18 to age 40.

3.1.2 KI should not be administered to any emergency worker who:

a. does not concur with its use, or

b. has a known allergic reaction to iodine and/or foods containing iodine such as shellfish, or

c. has been directed by their Physician or Pharmacist to avoid ingestion of iodine and/or foods containing iodine such as shellfish.

(2) The Committed Dose Equivalent to the thyroid from radioiodine.

EP-AD-000-125, Revision 9, Page 3 of 13

Tab 6 EP-PS-244-6 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0 3.1.3 Onsite issuance of KI for iodine prophylaxis requires the approval of the EMERGENCY DIRECTOR. Issuance to EOF and FIELD EMERGENCY MONITORING/SAMPLING TEAM personnel requires the approval of the RECOVERY MANAGER when the EOF has relieved the TSC of emergency management activities.

The EMERGENCY DIRECTOR will approve issuance prior to that time. These approvals must be documented on the POTASSIUM IODIDE (KI) TRACKING FORM.

3.1.4 Unless the EMERGENCY DIRECTOR or RECOVERY MANAGER instructs personnel to do otherwise, the EI tablets should generally be taken as soon as possible after thyroid dose exceeding 10 rem CDE (2) is projected.

NOTE: Stable iodine (KI) is most effective when administered immediately prior to exposure to radioiodine. Significant blockage of the thyroid dose can be provided by administration within a few hours after uptake of radioiodine.

3.15 In the event a significant exposure to the thyroid is projected to continue over a period of several days the CONSULTING RADIOLOGICAL PHYSICIAN should be requested to provide a recommended KI dosage for subsequent KI usage. (See Emergency Telephone Directory for telephone number.)

3.16 Until input/advice from the CONSULTING RADIOLOGICAL PHYSICIAN is available, a quarter of a tablet should be taken on days of exposure that follow the day on which the initial full tablet dose (130 mg) was taken.

3.17 If a worker expresses concern with the use of KI and/or is unsure if it will interact with his/her current medication,

a. the CONSULTING RADIOLOGICAL PHYSICIAN should be requested to provide input/advice to the individual concerning the administration and cessation of KI use prior to its ingestion by the individual. (See Emergency Telephone Directory for telephone number.)

(2) The Committed Dose Equivalent to the thyroid from radioiodine.

EP-AD-000-125, Revision 9, Page 4 of 13

Tab 6 EP-PS-244-6 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0

b. control and track workers' dose, to limit their projected thyroid dose to 40 rem total organ dose. As warranted, ensure adjusted RWP controls and dose extensions are in place.

3.1.8 Should the projected dose to the thyroid not exceed 10 rem CDE (2)but the worker expresses the strong desire to use KI, the worker may do so at his/her own risk. In such case, the RPC or DASU as appropriate will inform the worker of the potential risks and benefits as described below and will recommend the person contact the CONSULTING RADIOLOGICAL PHYSICIAN for further guidance.

NOTE: Radiation exposure to the thyroid glands of adults does not appear to lead to cancer but has been shown to cause other deterministic effects (such as hypothyroidism resulting from thyroid ablation) from very high radiation doses to the thyroid.

For persons over 40 years of age, HHS/FDA recommends KI only for projected doses to the thyroid of above 500 rem, to prevent hypothyroidism.

The National Council on Radiation Protection and Measurement (NCRP Report No. 55) concludes that the risk of adverse effects from use of KI is on the order of 5 in 10 million.

In some cases, hyperthyroidism (excessive functional activity of the thyroid gland) is possible.

Those most at.risk are patients with thyroid pathologies. This is most common in patients with goiter. This complication can be serious when the person also has heart disease. The risk of adverse effects is higher in adults of age 45 years and older, due to the frequency of diagnosed and sub-clinical thyroid disease and the use of certain prescription pharmaceuticals that would lead to a drug interaction.

(2) The Committed Dose Equivalent to the thyroid from radioiodine.

EP-AD-000-125, Revision 9, Page 5 of 13

Tab 6 EP-PS-244-6 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0 HHS/FDA observes that short-term administration of KI at thyroid blocking doses is safe. The risks of stable iodine administration include sialadenitis (an inflammation of the salivary gland), gastrointestinal disturbances, allergic reactions, and minor rashes.

Other risks may apply if repeated doses of KI are ingested.

3.1.9 If the individual states the intent to take KI absent a projected dose of 10 rem (CDE)(2) or more, the RPC or DASU will document in his/her logbook that individual's intent, that information on risks and benefits was described to the individual, and the statement that the individual was notified that ingestion was at the individual's own risk.

3.1.10 For an injured and/or contaminated worker sent to a hospital for treatment, the patient will be under the care of the attending physician. As such, plant procedures no longer apply and KI issuance will be at the discretion of the attending physician. The physician can rely on a senior Health Physics Technician Level II or Health Physics Management to provide the in-plant radiological data on which to base their decision.

O 3.2 Protective measures should be implemented for EOF personnel at the direction of the DOSE ASSESSMENT SUPERVISOR, within the bounds of RWPs #8001 and #8002. Consultation with and approval by the RPC is needed for RWP revisions.

o 3.3 Exposures to members of local offsite support groups, (ambulance workers, fire fighters) shall not exceed 500 mrem (TEDE)(') for the performance of support duties on the site of the Susquehanna SES.

12) The Committed Dose Equivalent to the thyroid from radioiodine.

The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.

EP-AD-000-125, Revision 9, Page 6 of 13

Tab 6 EP-PS-244-6 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0 4.0 EMERGENCY EXPOSURE NOTIFICATIONS AND A HEALTH CONSEQUENCE INVESTIGATION must be conducted for any emergency exposure as outlined in step 6 of the Emergency Exposure Extensions.

NOTE: Reference for section 3.1 are as follows:

1. HHS/FDA Guidance-Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies, December 2001.

2. LeGuen, B. et.al., French Approach for the Distribution of Iodine Tablets in the Vicinity of Nuclear Power Plants, Health Physics 2002.

3. PEMA, Report to the REPAC from the Potassium Iodide Working Group, January 2001.

EP-AD-000-125, Revision 9, Page 7 of 13

Tab 6 EP-PS-244-6 EMERGENCY EXPOSURE EXTENSIONS CHECK 0

1. Fill out the attached EMERGENCY EXPOSURE EXTENSION REQUEST Form.

2. Review the following factors:

o Rescue personnel should be volunteers or professional rescuers.

o Other considerations being equal (e.g., skill, potential need for person on another mission) personnel above the age of 45 are preferred.

O Rescue personnel should be familiar and briefed with the consequences of exposure.

o Women capable of reproduction should not take part in an effort requiring EMERGENCY exposure.

o Use of personnel with high lifetime cumulative exposure should be discouraged.

o All reasonable measures must be taken to control contamination and internal exposure.

O Exposure under these conditions shall be limited to once in a lifetime.

O For exposures greater than 25 rem whole body (TEDE), the persons undertaking any emergency operation in which the dose will exceed 25 rem to the whole body (TEDE) should do so only on a voluntary basis and with full awareness of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects.

See the following two tables for general information concerning Health Effects &

Cancer Risks.

EP-AD-000-125, Revision 9, Page 8 of 13

Tab 6 EP-PS-244-6 EMERGENCY EXPOSURE EXTENSIONS CHECK 0 Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours Whole Body Absorbed Early Fatalities~"b Whole Body Absorbed Prodromal Effects(c)

Dose (rad) (percent) Dose (rad) (percent affected) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 (a) Risks will be lower for protracted exposure periods.

° Supportive medical treatment may increase the dose at wilch these frequencies occur by approximately 50 percent.

(c) Symptoms (nausea, vomiting) which occur within a few hours after exposure to large doses of radiation and which usually precede more serious health effects.

Approximate Cancer Risk to Average Individuals from 25 Rem Effective Dose Equivalent Delivered Promptly Average Years of Life Lost If Age at Exposure Approximate Risk of Premature Death Premature Death Occurs (years)

(years) (deaths per 1,000 persons exposed) -er (years) 20 to 30 9.1 24 30to40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11

3. Review the HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES which is attached.

4. Obtain appropriate approval signatures as outlined in the table below.

EXTENSION FROM l TO mren (TEDE) mrer (TEDE) APPROVAL ACTIONS 4000 <25000 (ED or RM) and RPC ALARA REVIEW AND APPLY EMERGENCY EXPOSURE CONSIDERATIONS

>25000 (ED or RM) and RPC ALL OF ABOVE AND BRIEFING ON RISKS EP-AD-000-125, Revision 9, Page 9 of 13

Tab 6 EP-PS-244-6 EMERGENCY EXPOSURE EXTENSIONS CHECK 0

5. If the Emergency Dose Extension is for greater that 4 rem (TEDE), have the volunteer sign the EMERGENCY EXPOSURE REQUEST Form acknowledging that they are a volunteer and are fully aware of the radiological risks of acute and delayed effects.

6. Upon completion of the activity requiring the Emergency Exposure perform the following:

O Collect, process, and evaluate personnel dosimetry devices when technically appropriate.

O Investigate the circumstances of all emergency exposures and confirm the dose received.

O Notify the NRC of emergency exposure as follows:

Immediate notification of the NRC is required for:

a. Exposure of the whole body of greater than 25 rem (TEDE); or

b. Exposure of the skin of the whole body of greater than 150 rem (SDE); or

c. Exposure of the extremities of greater than 375 rem (SDE).

Notification of the NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is required for:

a. Exposure of the whole body of greater than 5 rem (TEDE); or

b. Exposure of the skin of the whole body of greater than 30 rem (SDE); or

c. Exposure of the extremities of greater than 75 rem (SDE).

O Assess the health consequences of all emergency exposures. Consult with a physician to determine the need for and extent of physical and biochemical examinations.

o Whole body greater than 25 rem (TEDE) should result in an examination of the exposed person by a physician.

o If internal exposure is suspected, quantitative measurements should be made as soon as reasonably feasible. Bioassays are required based on the following:

Nasal smear or facial contamination greater than 1,000 cpm above background.

Greater than 4 DAC-HRS in a day or less, or 20 DAC-HRS in a week or less.

EP-AD-000-125, Revision 9, Page 10 of 13

Tab 6 EP-PS-244-6 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECKO 1.0 Evaluate radiological conditions.

1.1 Obtain detailed survey data to ascertain:

1.1.1 Beta-Gamma radiation levels 1.1.2 Need for neutron measurements 1.1.3 Contamination levels and protective clothing requirements 1.1.4 Airborne radioactive materials 1.1.5 Variability of conditions over space and time 1.2 Evaluate personnel status.

1.2.1 Determine available dose under normal administrative dose objectives.

1.2.2 If essential, obtain approval from RADIATION PROTECTION COORDINATOR/EMERGENCY DIRECTOR for persons expected to exceed administrative objectives.

1.2.3 Follow criteria in PPL Emergency Personnel Dose Assessment and Protective Action Recommendation Guide when emergency exposures are deemed appropriate by EMERGENCY DIRECTOR.

1.2.4 Assess individual's history of exposure to airborne materials.

1.2.5 Assess individual's skills in relation to proposed task.

1.2.6 Assess individual's lifetime exposure history.

EP-AD-000-1 25, Revision 9, Page 11 of 13

Tab 6 EP-PS-244-6 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECK D 1.3 Determine proper type and placement of dosimeters.

1.3.1 Evaluate need for additional whole body dosimeters.

NOTE: For emergency exposures above 4 rem, the placement of several dosimeters on an individual is recommended to determine spatial distribution of dose to the Individual.

1.3.2 Evaluate need and placement of extremity dosimeters.

1.3.3 Evaluate need for additional dosimetry devices such as high range self-reading dosimeters, electronic dosimeters, and neutron dosimeters.

1.3.4 Evaluate need for time keeping.

1.4 Determine proper respirator equipment required to perform task.

NOTE: For tasks expected to last more than several hours, consider need for relief of team members.

1.5 Review the following ALARA items:

NOTE: The detail and scope of ALARA reviews are to be commensurate with the magnitude of doses expected, numbers of people involved, and urgency of required task.

1.5.1 Consider the trend of exposures vs. the importance of the task:

a. Important and critical task with rising exposure rates will require the dispatch of teams as quickly as possible to reduce exposures.

b. Unimportant or less critical task could be delayed until exposure rates begin to trend downward.

EP-AD-000-125, Revision 9, Page 12 of 13

Tab6 EP-PS-244-6 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECK O 1.5.2 When time permits the following should be included in the ALARA review:

a. Consider the use of remote handling devices or other special tools.

b. Consider the use of portable shielding.

c. Consider the need for mock-ups or other practice exercises.

d. Assess the number of people required to assure all have essential productive roles.

e. Consider the magnitude of doses received by team members in transit to work location.

EP-AD-000-125, Revision 9, Page 13 of 13

Tab 7 EP-PS-244-7 MIDAS OPERATING PROCEDURE TABLE OF CONTENTS SECTION PAGE A. INTRODUCTION/SYSTEM STARTUP 2 B. MENU B: FORWARD CALCULATIONS 4 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS 10 D. MENU D: DEFAULT ACCIDENT CALCULATIONS 14 E. MENU E-W: BACK CALCULATIONS 17 F. MENU G: BLOWOUT PANEL CALCULATIONS 23 G. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE

SUMMARY

REPORT 29 H. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES 33 I. ACCIDENT DESCRIPTIONS 34 EP-AD-000-1 12, Revision 21, Page I of 40

Tab 7 EP-PS-244-7 A. INTRODUCTIONISYSTEM STARTUP

1. The following conventions are used in this procedure to describe computer operations:

a. Bold, upper case text (i.e., CURRENT DATE), denotes text which appears on the screen.

b. Underlined, uppercase text (i.e., LOGIN) denotes text to be typed.

c. Bracketed, upper case text (i.e., [ENTER]), denotes special keys which are to be pressed.

d. Most mouse selections can be made with a single click.

Single click RESET to cancel previous screen selections.

Double click RESET to back out of present menu.

Double click to EXIT menu.

2. The met and vent spreadsheet will appear with all of the meteorological and ventilation release rate parameters across the top of the page. The current time period is highlighted in the left-hand column. The first time interval is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before the current time and the last time interval is 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months after the current time.

3. All required meteorological and ventilation data for MIDAS can be obtained using the METNENT DATA ACQUISITION OPTIONS tab.

4. To start MIDAS on a DOS computer:

a. Tum ON each component (monitor, computer, and printer) of the computer system on which MIDAS is loaded.

b. At the MIDAS logon screen, enter the password MIDAS and [ENTER].

c. At the MIDAS MAIN MENU screen, select A: MIDAS (Dose Calculator) and [ENTER].

d. The system will then display the CURRENT DATE. If the date is correct, press (ENTER]. If this date is incorrect, type the correct date using the format which is illustrated in the prompt and press [ENTER].

e. The system will then display the CURRENT TIME, which is stored in the computer system's clock (24-hour clock format). If the time is correct, press [ENTER]. If this time is incorrect, type the correct time using the format which is illustrated in the prompt and press [ENTER].

EP-AD-000-1 12, Revision 21, Page 2 of 40

Tab 7 EP-PS-244-7

f. The MIDAS logon screen will now appear for 20 seconds.

g. The ACCIDENT MENU SELECTION screen will appear. Select the appropriate calculation option and CONFIRM your selection.

5. To exit MIDAS on a DOS computer, double-click EXIT on each menu screen that appears. At the SECURITY MENU, press [F8] to log off.

6. To start MIDAS on a Windows computer:

a. Turn on each component (monitor, computer, and printer) of the computer system on which MIDAS is loaded.

b. At the WINDOWS LOGIN Screen, press [CANCELI.

c. On the System Desktop, double click on the MIDAS Icon.

d. The system will then display the CURRENT DATE. If the date is correct, press [ENTER]. If the date is incorrect, type the correct date using the format which is illustrated in the prompt and press [ENTER].

e. The system will then display the CURRENT TIME, which is stored in the computer system's clock (24-hour clock format). If the date is correct, press [ENTER]. If the date is incorrect, type the correct time using the format which is illustrated in the prompt and press [ENTER].

f. The MIDAS logon screen will now appear for a short time.

9. The ACCIDENT MENU SELECTION screen will appear. Select the appropriate calculation option and CONFIRM your selection.

7. To exit MIDAS on a Windows computer, double-clock EXIT on each menu screen that appears until you return to the System Desktop.

a. On the System Desktop, select START, SHUTDOWN, SHUTDOWN THE COMPUTER, and press [YES].

EP-AD-000-1 12, Revision 21, Page 3 of 40

Tab 7 EP-PS-244-7 B. MENU B: FORWARD CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

TIME OF REACTOR SHUTDOWN RELEASE START TIME DURATION OF RELEASE

PROJECTION TIME

ACCIDENT SOURCE TERM SELECTION MET DATA 10 M WIND SPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE VENT DATA SITE TOTAL NOBLE GAS RELEASE RATES SITE TOTAL 1-131 RELEASE RATES (if available from Chemistry or as directed by RPC/DASU)

SITE TOTAL PARTICULATE RELEASE RATES (if available from Chemistry or as directed by RPCIDASU)

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM, OR

b. If you have already initiated calculations and wish to modify either the existing met spreadsheet file or vent spreadsheet, select CURRENT SCENARIO EDIT and CONFIRM.

NOTE: CURRENT SCENARIO EDIT will include releases/doses from previous time steps, if applicable.

c. Other options are available in the lower right hand section of the display if you wish to RESET or change your initial selection or EXIT the screen.

EP-AD-000-1 12, Revision 21, Page 4 of 40

Tab 7 EP-PS-244-7

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page. Place the cursor on the data period corresponding to the start of release. Input the following met data:

NOTE 1: If the met data remains the same for successive time periods, the operator need only enter the met data once. MIDAS will persist the data to future time periods automatically.

NOTE 2: If a value is to be repeated in a field it can still be manually copied down the spreadsheet using the K (copy last) key while that value is highlighted.

a. In the column labeled IOM SPD, enter the wind speed from the 10 meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE: If the primary meteorological tower-data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

If the primary meteorological tower wind speed remains at "zero" during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.

b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION - (zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR IHEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

EP-AD-000-1 12, Revision 21, Page 5 of 40

Tab 7 EP-PS-244-7

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. The vent (GASEOUS VENT AND FLOW) spreadsheet will appear next. Enter current vent data. The data entry for each 15-minute period is as follows:

NOTE: Vent data may be entered in a regular numerical presentation (10000) or in scientific notation (1.OE+04).

a. In the column labeled TOT NG RELEASE, enter the site total noble gas release rate in j+/-Cimin.

b. In the column labeled TOT 1-131 RELEASE, enter the site total 1-131 release rate in ,uCi/min. Unless valid data is available from Chemistry or data is authorized for use by the RPC/DASU, the 1-131 release rate should be calculated as follows:

TOT NG RELEASE (IiCi/min)/1000 = TOT 1-131 RELEASE (IiCi/min)

c. In the column labeled TOT P RELEASE, enter the site total particulate release rate in gtCimin. Unless valid data is available from Chemistry or data is authorized for use by the RPC/DASU, the particulate release rate should be calculated as follows:

TOT NG RELEASE (giCi/min)/10,000 = TOT P RELEASE (p.Ci/min)

d. When the data entry is complete, press the X key to save the information and exit the spreadsheet.

EP-AD-000-1 12, Revision 21, Page 6 of 40

Tab 7 EP-PS-244-7

5. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM. Select RESET if you wish to change your previous selection.

If no specific information on the type of release is available from Engineering, use the following as a guide in the selection of appropriate accident source term.

a. Obtain Reactor Power from Engineering, Operations, or as follows:

1) From PICSY, select Unit #1 or Unit #2 formats to view affected unit.

2) Type STA and press [ENTER].

3) "Reactor Power" is in the top left section.

4) Click on MET VENT to return to the Met/Vent data display.

b. If the reactor is operating at or greater than 10% power, select the ATWS source term.

c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.

d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.

6. The RELEASE TIMING SELECTION screen will appear next. There are three lines to the screen.

a. On Line 1, select TRIP DATE (date and time of reactor trip). Using the calendar wheel, enter the appropriate date and time of reactor trip.

CONFIRM to close the calendar wheel.

1) The time of reactor trip must be equal to or earlier than the START OF RELEASE.

2) The time of reactor trip can be set up to roughly one year (8,190 hours0.0022 days 0.0528 hours 3.141534e-4 weeks 7.2295e-5 months ) prior to the START OF RELEASE.

EP-AD-000-1 12, Revision 21, Page 7 of 40

Tab 7 EP-PS-244-7 NOTE (1): MIDAS assumes the reactor must be shutdown before a release can occur. The TRIP DATE triggers the start of decay for the accident mix.

NOTE (2): Even during an ATWS, where a release is in progress and the reactor has not shut down, a TRIP DATE must be entered to run MIDAS. It is recommended the same date and time for the START OF RELEASE be used for the TRIP DATE. Entering a date and time for reactor trip has no impact on decay of the ATWS mix.

b. On Line 2, select START OF RELEASE. Using the calendar wheel, enter the appropriate date and time of the start of release. CONFIRM to close the calendar wheel.

1) If START NEW SCENARIO was selected-,4he START OF RELEASE date/time entered should be the current date/time at which you are starting the calculation.

2) If CURRENT SCENARIO EDIT was selected, the previously entered START OF RELEASE should still be used, if met/vent date have been entered for each 15-minute period since that START OF RELEASE. Otherwise, select RESET until START NEW SCENARIO is selected.

NOTE: The START OF RELEASE is defined as the date and time of the first vent data entry.

c. On Line 3, select REMAINING DURATION of the release. Using the numpad enter the duration of release, in minutes, and select EN or press

[ENTER] to close the numpad. If the duration of release is not known, use the default of 360 minutes.

NOTE: The REMAINING DURATION (DURATION OF RELEASE) can use forecasted or persisted data for up to 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months into the future.

d. Select CONFIRM to continue with the calculation or RESET to change any of your previous choices.

I 1.

EP-AD-000-1 12, Revision 21, Page 8 of 40

Tab 7 EP-PS-244-7

7. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

NOTE: The 0.25-hour projection time should be used with extreme caution. Projected doses can be substantially underestimated.

b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable-only when estimated dose rates from the current release period alone are requested by the RPC/DASU.

8. After the calculations have completed, the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART REPORT.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.

EP-AD-000-1 12, Revision 21, Page 9 of 40

Tab 7 EP-PS-244-7 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

RELEASE PATHWAY

CORE CONDITION, INCLUDING PERCENT OF CLAD FAILURE OR FUEL MELT

CONTAINMENT CONDITIONS

FILTRATION

PROJECTION TIME MET DATA

10 M WIND SPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE

1. The EVENT TREE NUREG-1228 SELECTION screen will appear.

a. Using information provided by Engineering Support or Operations, select one cell in each row of the menu. When a cell in the current row is selected, the next row then appears.

NOTE: Event tree menu selections, which include a definition of plant release parameters, are included (Section I) for each NUREG-1228 accident release scenario.

b. Using information provided by Engineering Support, select percent clad failure or percent fuel melt as follows:

(1) Left-click on percent clad failure (fuel melt).

(2) Using the numpad on the screen, input the percent clad failure (fuel melt) provided by Engineering Support, the EN (ENTER).

(3) CONFIRM your entry if correct. If incorrect, re-perform steps (1) and (2).

c. CONFIRM entries to continue with the calculation or RESET if you wish to change any of your selections. You may also double-click EXIT to return to the ACCIDENT MENU SELECTION screen.

EP-AD-000-1 12, Revision 21, Page 10 of 40

Tab 7 EP-PS-244-7

2. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM.

b. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

3. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 1DM SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

If the primary meteorological tower wind speed remains at "zero" during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.

b. In the column labeled 1DM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). DMde the PICSY precipitation rate (incheslhr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION Q(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY EP-AD-000-1 12, Revision 21, Page 11 of 40

Tab 7 EP-PS-244-7

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

.a. If this screen appears, select RESET until you have returned to the METIVENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

5. The PPL

SUMMARY

DATA SELECTION screen allows-the user to select different options for the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

NOTE: The 1-hour projection time should be used with caution.

Projected doses can be underestimated.

b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.-

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current release period alone are requested by the RPC/DASU.

6. After the calculations have completed, the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

EP-AD-00O-1 12, Revision 21, Page 12 of 40

Tab 7 EP-PS-244-7

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE (1): If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.

NOTE (2): Engineering Support or Operations concurrence with the selections may be documented by their representatives' signatures on the printout.

EP-AD-000-1 12, Revision 21, Page 13 of 40

Tab 7 EP-PS-244-7 D. MENU D: DEFAULT ACCIDENT CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

MET DATA

10 M WIND SPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE SOURCE TERM ACCIDENT SOURCE TERM SELECTION

. PERCENT OF CLAD FAILURE OR FUEL MELT PROJECTION TIME

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM.

b. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 1OM SPD, enter the wind speed from the 1 -meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

If the primary meteorological tower wind speed remains at

'zero' during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.

EP-AD-000-1 12, Revision 21, Page 14 of 40

Tab 7 EP-PS-244-7

b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (incheslhr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION Q(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR IHEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. If this screen appears, select RESET until you have returned to the METIVENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.

5. A PERCENT FAILURE FOR LOCA screen will appear if the clad failure or fuel melt accident source term is selected. Input the percent of clad failure or fuel melt using the numpad and CONFIRM.

EP-AD-000-1 12, Revision 21, Page 15 of 40

Tab 7 EP-PS-244-7

6. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

NOTE: The 1-hour projection time should be used with caution.

Projected doses can be underestimated.

b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current release-period alone are requested by the RPCIDASU.

7. After the calculations have completed, the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double dick EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.

EP-AD-000-1 12, Revision 21, Page 16 of 40

Tab 7 EP-PS-244-7 E. MENU E-W: BACK CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

TIME OF REACTOR SHUTDOWN

RELEASE START TIME

DURATION OF RELEASE

ACCIDENT SOURCE TERM SELECTION

PROJECTION TIME MET DATA

0 M WIND SPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE FIELD DATA

3 FT (CW) SURVEY METER READING

DISTANCE FROM PLANT

IODINE CARTRIDGE NET CPM, IODINE CONCENTRATION IiCi/cc, OR DEFAULT IODINE MIX

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM.

b. If you have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

EP-AD-000-1 12, Revision 21, Page 17 of 40

Tab 7 EP-PS-244-7

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

If the primary meteorological tower wind speed remains at

'zero" during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.

b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN115M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION O(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

EP-AD-000-1 12, Revision 21, Page 18 of 40

Tab 7 EP-PS-244-7

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. If this screen appears, select RESET until you have returned to the MET/VENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.

If no specific information on the type of release is available-from Engineering, use the following as a guide in the selection of an appropriate accident source term:

a. Obtain Reactor Power from Engineering, Operations, or as follows:

1) From PICSY, select Unit #1 or Unit #2 formats to view affected unit.

2) Type STA and press [ENTER].

3) "Reactor Power" is in the top left section.

4) Click on MET VENT to return to the Metlent data display.

b. If the reactor is operating at or greater than 10% power, select the ATWS source term.

c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.

d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.

EP-AD-000-1 12, Revision 21, Page 19 of 40

Tab7 EP-PS-244-7

5. The next screen is the FIELD MONITOR PARAMETER SELECTION screen.

Select the appropriate cells and input the information requested using the numpad on the screen or enter the data using the computer keyboard. Once the data entry is complete, CONFIRM to continue with the calculation.

a. Enter Field Team or ERMS Fixed Monitor gamma (EDE) dose rate whichever is appropriate.

b. Enter the distance of the Field Team or Fixed Monitor from the plant as noted on the RMS Report or for the on-site team as noted on Table 4 of EP-AD-000-124.

c. If iodine air sample data is available, enter either the IODINE CARTRIDGE reading in net counts per minute or an IODINE CONCENTRATION value in dCilcc. A zero (0) value may be entered for the net count per minute or piCi/cc measurementrif indicated.

d. If iodine data is not available, select the DEFAULT MIX option to characterize the iodine source term.

6. On the RELEASE TIMING SELECTION screen, enter the estimated remaining duration for the release, then CONFIRM. If the duration of release is not known, use the default of 360 minutes.

7. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

NOTE: The 1-hour projection time should be used with caution.

Projected doses can be underestimated.

b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current release period alone are requested by the RPC/DASU.

EP-AD-000-1 12, Revision 21, Page 20 of 40

Tab 7 EP-PS-244-7

8. After the calculations have completed, the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.

e. Remote Monitoring System perimeter monitoring location dose rates can be displayed by MIDAS using the perimeter monitoring dose rate screen option.

NOTE: The displayed values are only numeric dose estimates based-on MIDAS calculations. They are not "real-time" readings from the perimeter monitor system.

Directions for accessing the MIDAS perimeter monitor dose rate screen option are as follows:

1) At the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET screen, select CONTINUE.

2) On the next screen select MORE REPORTS.

3) From the MORE REPORTS SELECTION screen, select FM GAMMA DOSE RATE PLOT and CONFIRM.

4) From the REPORT PARAMETER SELECTION screen, choose the appropriate projection time and CONFIRM.

5) From the MAP SELECTION screen, select MAP SCALE and input 1.25 miles, then CONFIRM.

EP-AD-000-1 12, Revision 21, Page 21 of 40

Tab 7 EP-PS-244-7

6) On the next screen, select MAP FEATURES.

7) On the next screen, select CALCULATED PERIMETER MON DOSE RATES and CONFIRM.

8) To exit, select CONTINUE, MORE REPORTS, and EXIT.

EP-AD-000-1 12, Revision 21, Page 22 of 40

Tab 7 EP-PS-244-7 F. MENU G: BLOWOUT PANEL CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

TIME OF REACTOR SHUTDOWN

RELEASE START TIME

PROJECTION TIME

BLOWOUT PANEL ASSUMED TO HAVE LIFTED (RELEASE PATHWAY)

CORE CONDITION, INCLUDING PERCENT OF CLAD FAILURE OR CORE MELT MET DATA

10 M WIND SPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE

1. The MET/VENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM, OR

b. If you have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO-EDIT and CONFIRM.

NOTE: CURRENT SCENARIO EDIT will include releases/doses from previous time steps, if applicable.

c. Other options are available in the lower right hand section of the display if you wish to RESET or change your initial selection or EXIT the screen.

. EP-AD-000-1 12, Revision 21, Page 23 of 40

Tab 7 EP-PS-244-7

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page. Place the cursor on the data period corresponding to the start of release. Input the following met data:

NOTE 1: If the met data remains the same for successive time periods, the operator need only enter the met data once. MIDAS will persist the data to future time periods automatically.

NOTE 2: If a value is to be repeated in a field it can still be manually copied down the spreadsheet using the K (copy last) key while that value is highlighted.

a. In the column labeled 1OM SPD, enter the wind speed from the 10 meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE: If the primary meteorological tower-data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

If the primary meteorological tower wind speed remains at Nzeron during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.

b. In the column labeled 1DM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.

d. In the column labeled IRAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION Q(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

EP-AD-000-1 12, Revision 21, Page 24 of 40

Tab 7 EP-PS-244-7

3. The BLOWOUT PANEL SELECTION screen will appear.

NOTE: Blowout panel locations are shown on Figure 1 of this procedure tab.

a. Using information provided by Engineering Support or Operations, select one cell in each row of the menu. When a cell in the current row is selected, the next row then appears.

b. CONFIRM entries to continue with the calculation or RESET if you wish to change any of your selections. You may also double-click EXIT to return to the ACCIDENT MENU SELECTION screen.

c. On the PERCENT CLAD FAILURE (or PERCENT FUEL MELT) screen, using information provided by Engineering Support, select percent clad failure or percent fuel melt as follows:

(1) Left-click on percent clad failure (fuel melt).

(2) Using the numpad on the screen, input the percent clad failure (fuel melt) provided by Engineering Support, then EN (ENTER).

(3) CONFIRM your entry if correct. If incorrect, re-perform steps (1) and (2).

NOTE: Release rates used by MIDAS are those shown in Table 1 of this procedure tab, multiplied by the percent clad failure (fuel melt. entered, expressed as a fraction (e.g., the multiplier for 50% fuel melt would be 0.5).

4. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. Missing information will be indicated by a black box (with white lettering) in the left-hand column.

(1) Left-click on the black box in the left column.

(2) Using the numpad on the screen, input the response to the missing data.

(3) Repeat steps (1) and (2) to supply any other required information.

(4) CONFIRM your entry if correct. If incorrect, re-perform steps (1) and (2) for the data in error.

EP-AD-000-1 12, Revision 21, Page 25 of 40

Tab7 EP-PS-244-7

5. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

NOTE: The 0.25-hour projection time should be used with extreme caution. Projected doses can be substantially underestimated.

b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current release period alone are requested by the RPCIDASU.

6. After the calculations have completed, the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET, be sure to fill in the required information documenting the name of the dose calculator.and approver.

EP-AD-000-1 12, Revision 21, Page 26 of 40

Tab 7 EP-PS-244-7 FIGURE 1 EP-AD-000-1 12, Revision 21, Page 27 of 40

Tab 7 EP-PS-244-7 TABLE 1 EVALUATION OF UNMONITORED RELEASES FROM STATION BLOWOUT PANELS DIRECTIONS

1. Select the appropriate station blowout panel location.

2. Select an appropriate accident source term mix.

3. Use the corresponding design base release rates for input into MENU B.

4. Enter the release rates for one (1) fifteen-minute time period.

NOTE: If Clad Failure or Fuel Melt mixes are selected, multiply the site total noble gas, 1-131, and particulate release rates by the appropriate fraction of clad failure or fuel melt prior to entering the values onto the vent spreadsheet (e.g., the multiplier for 50% FUEL MELT would be 0.5).

1 1 BLOWOUT PANEL LOCATION [31 DESIGN BASIS (SITE TOTAL) RELEASE RATES l NOBLE GAS 1-131 PARTICULATE RCIC PUMP ROOM (pCi/min) (uC~min) (PC~min) 12 1 ACCIDENT SOURCE TERM Normal Reactor Coolant Activity 1.2E+02* 1.8E+02 1.1 E+03 (LOCA) Reactor Depressurization-No FD 2.6E+06 8.4E+04 2.2E+04 (LOCA) 100% Clad Failure 2.1E+09 2.4E+08 9.1E+07 (LOCA) 100% Fuel Melt 4.3E+10 1.3E+09 1.7E+09 HPCI PUMP ROOM (pCimin) (pC~min) (pCi/min)

Normal Reactor Coolant Activity 2.IE+03 1 3.2E+03 1.9E+04 (LOCA) Reactor Depressurization-No FDl 4.6E+07 1.5E+06 3.8E+05 (LOCA) 100% Clad Failure 3.7E+10 4.3E+09 1.6E+09

,(LOCA) 100% Fuel Melt 7.5E+1 1 2.3E+10 3.OE+10 HPCIJRCIC ROUTING AREA (pCVmin) (Ci/min) (pC/min)

Normal Reactor Coolant Activity 3.2E+03* I 4.9E+03 2.9E+04 (LOCA) Reactor Depressurization-No FD 7.OE+07 2.2E+06 5.8E+05 (LOCA) 100% Clad Failure 5.7E+10 6.5E+09 2.4E+09 (LOCA) 100% Fuel Melt 1.IE+12 3.5E+10 4.6E+10 RWCU PENETRATION ROOM (pCi/min) (pCi/min) (pCVmin) l Normal Reactor Coolant Activity 7.3E+03- 5.8E+03 6.6E+04 (LOCA) Reactor Depressurization-No FD 1.6E+08 2.6E+06 1.3E+06 (LOCA) 100% Clad Failure 1.3E+1 1 7.6E+09 5.5E+09 (LOCA) 100% Fuel Melt 2.6E+12 4.1E+10 1.0E+11 RBtTB MAIN STEAM TUNNEL (pCmin) (,Cmin) (pCi/min)

Normal Reactor Coolant Activity 2.6E+04- 3.9E+04 2.3E+05 (LOCA) Reactor Depressurization-No FD 5.6E+08 1.8E+07 4.7E+06 (LOCA) 100% Clad Failure 4.6E+11 5.2E+10 1.9E+10 (LOCA) 100% Fuel Melt 9.1E+12 2.8E+11 3.7E+11 FD = FUEL DAMAGE Value less than the TRM limit for noble gas release rate.

REFERENCE:

EC-RADN-1018, Evaluation of Unmonitored Releases from Station Blowout Panels, Revision 1, File R2-1.

EP-AD-000-1 12, Revision 21, Page 28 of 40

Tab 7 EP-PS-244-7 G. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE ASSESSMENT

SUMMARY

SHEET

1. CALCULATION TYPE Menu option chosen for the calculation. Examples are Forward Calculation or Event Tree Calculation.

2. CURRENT TIME PERIOD Current meteorological time period used for dose projections provided on quarter hour increments to match met spreadsheet entries.

3. WEATHER CONDITIONS Meteorological data (wind speed, wind direction, affectedsector, stability class, and precipitation rate) used for the summary report dose projections.

4. REACTOR SHUTDOWN TIME Date and time of reactor shutdown.

5. RELEASE START TIME This is the date and time of first dose calculation as indicated by the first positive vent release rate value entered on the vent data spreadsheet or if the vent spreadsheet is not used, the date and time of the calculation..

NOTE: For MENU C: EVENT TREE NUREG-1228 CALCULATIONS, MENU D: DEFAULT CALCULATIONS, and MENU E-W: BACK CALCULATIONS, it is conservatively assumed that the date and time of reactor shutdown is concurrent with the start of release.

6. PROJECTION TIME This is the time X hours into the future, starting from the beginning of the current meteorological time period. OX' is the number of hours the user chooses as the projection time (e.g., 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ).

7. REMAINING DURATION This is the remaining duration of the release for the calculation type chosen. For Event Tree calculations, that is always 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and for Blowout Panel calculations, 0.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months .

EP-AD-000-1 12, Revision 21, Page 29 of 40

Tab 7 EP-PS-244-7

8. SOURCE TERM (for Forward and Back Calculations)

Identifies the source term used for the current dose projection summary report calculations. Choice of six options:

ATWS-Normal Reactor Coolant Activity (UNDECAYED)

Normal Reactor Coolant Activity (DECAYED)

(LOCA) Coolant Activity Leak with Depressurization Spike-No Fuel Damage (LOCA) Cladding Failure-Gap Release

(LOCA) Fuel Melt-Early In-Vessel Release

Fuel Handling Accident

9. RELEASE CONDITIONS This section lists the release rates used in the calculation. The values are taken from user input for Forward calculations, inferred from usdr input of event conditions (Event Tree, Default, and Blowout Panel calculations, or inferred from user input of measured data in the field (Back calculations).

10. Content of this section varies by Calculation Type. The objective is to provide information about the assumptions used to infer the Release Conditions for the calculation or to provide additional information about the Release Conditions.

For Forward Calculations, isotopic release ratios are provided. These may be compared to default ratios and used to infer plant conditions, for example, status of filtration.

For Event Tree, Default, and Blowout Panel Calculations; event or default conditions are listed. From those conditions, Release Conditions are inferred.

For Back Calculations, measured field data are listed. From those data, Release Conditions are inferred.

11. DOSE RATE PROJECTIONS This table provides the TEDE, EDE, and THYROID CDE dose rates calculated at the OSCAR and EPB distances. These rate calculations are based on a variable projection/integration period for the current affected sector or peak sector (the usual user selection).

EP-AD-000-1 12, Revision 21, Page 30 of 40

Tab 7 EP-PS-244-7

12. INTEGRATED DOSE PROJECTIONS This table provides a TEDE and THYROID CDE dose projection calculated at the EPB, 2-mile, and 10-mile distances for varying projection times. The projection time will appear in the header line e.g., 4 HOUR INTEGRATED DOSE PROJECTION. The sector designation for this dose projection is based on the maximum calculated dose determined from all sixteen sectors for the given projection time (peak sector option, usually the user's choice) or the calculated dose for the current affected sector. Information for distances between 10 and 50 miles is available using the "More Reports" feature.

13. PERFORMEDIAPPROVED The sign-off for calculation results is done for documentation purposes. The intended "approval" does not necessarily mean an independent verification of each input to the calculation but more an interactive discussion between the RPC/HP Level II Dose Calculator and/or DASU/DAST (or dose calculator) to ensure the calculated results are reasonable based on current plant and environmental information.

This sign-off process should occur before the calculated results are used for any emergency classification determinations or protective action recommendations.

EP-AD-000-1 12, Revision 21, Page 31 of 40

Tab 7 EP-PS-244-7

'p

I U~~~~~~~~&nI w F Is~~~~~~~~~P1C6 EP-AD-00O-1 12, Revision 21, Page 32 of 40

Tab 7 EP-PS-244-7 H. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES

1. From the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET screen, select CONTINUE and, on the next page, MORE REPORTS.

2. Select TEDE 4-DAY DOSE REPORT or THYROID CDE DOSE REPORT, depending on which PAR guide has been exceeded at the 10-mile distance.

3. On the REPORT PARAMETER SELECTION screen, select PROJECTION TIME until the appropriate PROJECTION TIME (0.25, 4, 6, or 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ) is displayed on the screen; then select CONFIRM.

NOTE: The 0.25-hour projection time should be used with extreme caution. Projected doses can be substantially underestimated.

4. The screen will now display projected doses at the EPB and at 2, 5,10, 25, and 50 miles. To obtain finer increments of distance, select CONTINUE until the desired range of distances is displayed.

NOTE: An objective is to determine the approximate distance from the plant at which dose projections are less than 1 rem TEDE and 5 rem THYROID CDE. A PAR is then likely to be issued to the next furthest 5-mile distance increment from the plant Example: A PAR for distances to 30 miles may be selected if projected doses become less than the PAG values (1 rem TEDE, 5 rem THYROID CDE) between 25 and 30 miles from the plant EP-AD-000-1 12, Revision 21, Page 33 of 40

Tab 7 EP-PS-244-7 ACCIDENT DESCRIPTIONS DEFAULT ACCIDENT DESCRIPTIONS (MENU B AND MENU D)

1. NORMAL REACTOR COOLANT ACTIVITY This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system with no damage to the fuel and no activity spiking. The source term for this accident is normal reactor coolant system liquid and steam activity.

2. LOCA (RX DP-NO FD)

This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system. Depcessurization of the primary coolant system is assumed, resulting in an activity spike in the reactor coolant. The source term for this accident is normal reactor coolant liquid and steam activity plus the depressurization activity spike. There is no fuel damage.

3. LOCA (CLAD FAILURE)

This accident scenario is defined as a Loss-of-Coolant Accident.which results in damage to the reactor fuel cladding. The source term for this accident is normal reactor coolant liquid and steam activity and a percentage of the activity in the fuel clad gap. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.

4. LOCA (FUEL MELT)

This accident scenario is defined as a Loss-of-Coolant Accident which results in damage to the reactor fuel. The source term for this accident is normal reactor coolant liquid and steam activity and a percentage of the activity in the reactor fuel. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.

5. FUEL HANDLING ACCIDENT This accident scenario is defined as a fuel handling accident which results in the release of spent fuel activity. The source term for this accident is spent fuel gap activity assuming a decay time after shutdown of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

EP-AD-00O-1 12, Revision 21, Page 34 of 40

Tab 7 EP-PS-244-7

6. ATWS This accident scenario is used for releases from a reactor unit continuing to operate at or greater than 10% power. The source term for this accident is normal reactor coolant system liquid and steam activity. The source term is undecayed; that is, no reactor trip is assumed to have occurred.

NOTE (1): For Menu D calculations, design basis assumptions are utilized.

For example, design basis leakage rates are assumed and iodine filtration efficiency of 99% is assumed in those pathways for which filters are in place.

NOTE (2): The source term for Menu D accident types is fixed. Release rate is calculated by MIDAS by dividing the total activity released by a predetermined release duration (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all but fuel handling accidents, for which release duration is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

NUREG 1228 EVENT TREE ACCIDENT TYPES (MENU C)

1. LOCA- DRYWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release into the drywell which bypasses the suppression pool for which filtration of activity-by the Standby Gas Treatment System takes place before release to the environment.

2. LOCA - WETWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release through the suppression pool for which filtration of activity by the Standby Gas Treatment System takes place before release to the environment.

3. LOCA - CONTAINMENT BYPASS RELEASE This accident is a Loss-of-Coolant Accident with an activity release to the environment that bypasses the containment and the Standby Gas Treatment System.

4. ZIRCALLOY FIRE IN ONE THREE MONTH OLD BATCH This accident is a zircalloy fire in spent fuel that results in an activity release similar to a core melt. It assumes that the activity is filtered by the Standby Gas Treatment System prior to release.

EP-AD-000-1 12, Revision 21, Page 35 of 40

Tab 7 EP-PS-244-7

5. SPENT FUEL GAP RELEASE This accident is a release of fuel gap activity from the spent fuel pool with treatment by the Standby Gas Treatment System prior to release.

NOTE: Menu C (from NUREG-1228 Event Tree Analyses) is used to relatively quickly provide a bounding estimate of offsite dose, for situations where there are substantial uncertainties in prediction of source term and any resultant doses.

EP-AD-000-1 12, Revision 21, Page 36 of 40

Tab 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR DRYWELL RELEASE CONTAINMENT DRYWELL WE1WELL BYPASS SPENT FUEL RELEASE RELEASE RELEASE POOL RELEASE (Clad Failure) (Fuel Melt) (Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN lI SPRAY ON SPRAY OFF l Status of Drywell Containment Spray HOLDUP TIME HOLDUP TIME Drywell Holdup Time:

<1 HOUR 2-12 HOURS Time from Rerease CATASTROPHIC (DEFAULT) into Containment to CONTAINMENT Start of Release into FAILURE Environment(1 )

LEAK RATE LEAK RATE DESIGN DESIGN LEAK RATE 100%/DAY 100%/DAY LEAK RATE LEAK RATE 100%/HOUR UNFILTERED FILTERED UNFILTERED FILTERED Catastrophic Failure to Isolate Containment 1%/Day Containment Failure (1) HOLDUP TIME is defined as drywell holdup time prior to release to the environment During this time period, credit is taken for drywell airborne activity removal due to plateout by natural processes and water sprays prior to release to the environment.

EP-AD-000-1 12, Revision 21, Page 37 of 40

Tab 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR WETWELL RELEASE CONTAINMENT DRYWELL WETWELL SPENT FUEL BYPASS RELEASE RELEASE POOL RELEASE RELEASE (Clad Failure) (Fuel Melt) (Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN I SATURATED I SUB-COOLED Conditions in Suppression Pool HOLDUP TIME HOLDUP TIME Wetwell Holdup Time:

<1 HOUR 2-12 HOURS Time from Release CATASTROPHIC (DEFAULT) into Wetwell to Start CONTAINMENT of Release into FAILURE Environment(')

ILEAK RATE DESIGN DESIGN LEAK RATE LEAK RATE 100%/oDAY LEAK RATE LEAK RATE 100%/HOUR 100%/DAY FILTERED UNFILTERED FILTERED Catastrophic Failure to Isolate Containment 1%/Day Containment Failure (1) HOLDUP TIME is defined as wetwell holdup time prior to release to the environment.

During this time period, credit is taken for wetwell airborne activity removal due to plateout by natural processes and water sprays prior to release to the environment.

EP-AD-000-1 12, Revision 21, Page 38 of 40

Tab 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR CONTAINMENT BYPASS RELEASE WETWELL RELEASE j CONTAINMENT BYPASS RELEASE I

(Clad Failure) (Fuel Melt) (Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN I UNFILTERED I I FILTERED I Is Release Filtered?

RELEASE RATE RELEASE RATE TYPICAL DESIGN Release Rate, in 100%/HOUR 100Yo/DAY RELEASE RATE Terms of Percent of Core Inventory Catastrophic Failure to Isolate 1%/Day Containment Failure Containment EP-AD-000-1 12, Revision 21, Page 39 of 40

Tab 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR SPENT FUEL POOL RELEASE CONTAINMENT WE1WELL SPENT FUEL BYPASS RELEASE POOL RELEASE RELEASE ZIRCALLOY FIRE GAP RELEASE GAP RELEASE Condition of Spent IN ONE 3 MONTH FROM ONE FROM 15 Fuel OLD BATCH 3 MONTH OLD BATCHES BATCH (TOTAL POOL)

SPRAY OFF Status of Containment Spray (Default) into Pool HOLDUP TIME HOLDUP TIME Time from Release

<1 HOUR 2-12 HOURS from Fuel to Start of Release into CATASTROPHIC FAILURE OF (DEFAULT) Environment(')

REACTOR BUILDING LEAK RATE LEAK RATE LEAK RATE Release Rate, in 100%/HOUR 100%/DAY 100%/DAY Terms of Percent of UNFILTERED FILTERED Source Inventory Catastrophic Failure of Secondary Containment

(') HOLDUP TIME for a spent fuel pool release is defined as reactor building holdup time prior to release to the environment. During this time period, credit is taken for reactor building airborne activity removal due to plateout by natural processes and water sprays prior to release to the environment.

EP-AD-000-1 12, Revision 21, Page 40 of 40

Tab 11 EP-PS-244-1 1 PAR AIRBORNE RELEASES NOTES:

1. PA4 CAN BE USED TO REFER TO PROCEDURE STEPS FOR MORE DETAILED INFORMATION ON THE ACTION TO BE TAKEN.

2. DOSE PROJECTIONS DO NOT INCLUDE DOSE ALREADY RECEIVED.

3. TEDE - WHOLE BODY (TEDE) IS THE SUM OF EFFECTIVE DOSE EQUIVALENT RESULTING FROM EXPOSURE TO EXTERNAL SOURCES. THE COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) FROM ALL SIGNIFICANT INHALATION PATHWAYS AND THE DOSE DUE TO GROUND DEPOSmON.

4. CDE - COMMITTED DOSE EQUIVALENT TO THE CHILD THYROID.

EP-AD-000-126, Revision 10, Page 1 of 6

Tab 11 EP-PS-244-1 1 PAR LIQUID RELEASES EC Values RADIONUCLIDE (pCIml) l Co-60 3E'6 Sr-91 21 4 Mo-99 2E 4 To-132 9E4 1-131 IE4 1-133 7E4 1-134 4E 4 1-135 3E4 Cs-134 l E7 Cs-136 l E I Cs-137 l 1E' I Ba-139 2E4 I Ba-140 SE'G Ba-141 3E4 Np-239 2E- I I

I I

I NOTES:

1. PL4 CAN BE USED TO REFER TO PROCEDURE STEPS FOR MORE DETAILED INFORMATiON ON THE ACTION TO BE TAKEN.

2. CALLS TO DANVILLE ARE COURTESY INFORMATION CALLS ONLY.

PROTECTIVE ACTION RECOMMENDATION CALLS MUST BE MADE BY DEPIBRP.

Yes RAD PERSONNEL NOTIFY DEPIBRP FOR DOWNSTREAM USERS TO DIVERT WATER SUPPLY &ESTIMATED TIME OF ARRIVAL OF RELEASE AT DANVILLE PL-9 EP-AD-000-126, Revision 10, Page 2 of 6

Tab 11 EP-PS-244-1 1 PUBLIC PROTECTIVE ACTION RECOMMENDATION GUIDE AIRBORNE RELEASES 0 PA-1 MONITOR CONDITIONS FOR PAR APPLICATION The following conditions should be continuously evaluated to determine if a PAR should be implemented or changed:

Plant status and prognosis for changes in conditions

Onsite radiological conditions

Status of actual or potential radioactive releases

Offsite dose projections or actual offsite radiological conditions

Escalation in Emergency Classification (i.e., General)

(Go to PA-2)

PA-2 HAS A GENERAL EMERGENCY BEEN DECtARED?-

O YES - If a GENERAL EMERGENCY has been declared, a PAR must be made within 15 minutes of the emergency declaration. The PAR requirement is found in NUREG-0654. (Go to PA-3)

O NO- If a GENERAL EMERGENCY has not been declared, continue to monitor plant status, parameter trends, and prognosis for termination or escalation of the event. (Go to PA-1)

PA-3 IS THERE AVALID DOSE PROJECTION INDICATING DOSES OF 2 I REM TEDE OR > 5 REM CDE CHILD THYROID AT A DISTANCE OF > 2 MILES?

o YES- Ifthe projected doses at 2 miles are 2 1 REM TEDE or >5 REM CDE child thyroid, then full evacuation (0-10 miles) is recommended.

(Go to PA-5)

O NOIUNKNOWN- (Go to PA-4)

O PA-4 RECOMMEND EVACUATION 0-2 MILES; SHELTER 2-10 MILES Limited Evacuation (0-2 miles) and sheltering is appropriate for events that are significant enough to cause a General Emergency classification and dose projections are low, unknown, or below full evacuation guidelines.

O PA-5 EVACUATE 0-10 MILES Full evacuation of members of the general public is recommended at this point based on the emergency classification and dose projections.

EP-AD-000-1 26, Revision 10, Page 3 of 6

Tab 11 EP-PS-244-1 1 LIQUID L PL-1 ENTRY This section is entered when there are indications of a potential unplanned radioactive liquid release.

Indications of potential unplanned releases include:

an unisolable radwaste tank release

leaks to cooling tower basin

leak to spray pond (Go to PL-2)

O PL-2 CHEMISTRY/ENVIRONMENTAL SAMPLINGDIRECTOR (ESD)

TAKES AND ANALYZES SAMPLE (Go to PL-3)

PL-3 IS THERE AN UNPLANNED RELEASE TO THE RIVER?

ol . YES - An unplanned release to the river has occurred when event-related radioactive materials are released to the river that are not controlled by the release methodologies described in the ODCM and applicable Chemistry procedures.

(Go to PL-4) o NO- If there is no unplanned release to the river, then no notifications are required and monitoring should continue.

o PL-4 RAD PERSONNEL NOTIFY DEPIBRP THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to BRP will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF.

DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.

(Go to PL-5)

EP-AD-000-1 26, Revision 10, Page 4 of 6

Tab 11 EP-PS-244-1 1 LIQUID (CONT'D)

PL-5 IS RELEASE 2 TECHNICAL REQUIREMENTS LIMITS (AT THE RELEASE POINT)?

L YES- Releases are at or greater than Technical Requirements limits when Chemistry determines that the limits are exceeded based on methodologies described in the ODCM and applicable Chemistry procedures.

(Go to PL-6) 0 NO- If the release is < Technical Requirements limits, then no further notifications are required and monitoring should continue.

O PL-6 RAD PERSONNEL NOTIFY DANVILLE THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to Danville will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF.

DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.

(Go to PL-7)

OI PL-7 CHEM/FTD EVALUATES RELEASE VERSUS PAGs The results of the sample analysis are compared to the PAGs for radionuclides in drinking water. The analysis calculates the expected concentration at Danville, taking into account the dilution afforded by the river.

PL-8 DOES RELEASE EXCEED PAGs (AT DANVILLE)?

0 YES - Ifa single isotope exceeds its effluent concentration (EC) value or the sum of EC fractions exceeds 0.85, then a protective action recommendation should be made for downstream water users (e.g.,

Danville) to DIVERT DRINKING WATER supply to a backup supply or terminate user intake until the release has passed.

(Go to PL-9) 0 NO- If the PAGs are not exceeded, monitoring should continue and the State should be notified that no PAR for the liquid release is required.

(Go to PL-10)

EP-AD-000-1 26, Revision 10, Page 5 of 6

Tab 11 EP-PS-244-1 1 LIQUID (CoNT'D) 0 PL-9 RAD PERSONNEL NOTIFY DEPIBRP OF PARP Depending on which facility is activated, the PAR notification to DEP/BRP will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF. The PAR FORM shall be used to document the PAR.

DO NOT COMMUNICATE THE PROTECTIVE ACTION RECOMMENDATION TO DANVILLE. THE DEP/BRP IS RESPONSIBLE FOR THIS COMMUNICATION AND ANY COMMUNICATION TO OTHER DRINKING WATER SUPPLIERS OR WATER USERS.

O PL-10 RAD PERSONNEL NOTIFY DEPIBRP No PAR is required. Depending on which facility is activated, the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF shall notify DEP/BRP that no PAR is required.

EP-AD-000-126, Revision 10, Page 6 of 6

Tab 13 EP-PS-244-1 3 RADIOLOGICAL DOSE ASSESSMENT PHONE LOG This form is intended for communication of dose assessment results from the TSC to the EOF (or EOF to TSC) when a facility is unable to transmit a copy of the MIDAS DOSE ASSESSMENT

SUMMARY

SHEET. HIGH PRIORITY items (1-6) are required inputs for the dose assessments. LOW PRIORITY items (7-10) are highly desired but not essential. The LOW PRIORITY items may be omitted if time constraints exist.

' HIGH'PRIORITY4

1. CURRENT (15) MINUTE CALCULATION TIME PERIOD DATE TIME

2. ivwvtNITS U' '-EPB(MREM)V` MILE (MREM' 1OLE

.1REM)' I, TEDE l l '

THY CDE __ _ _ _

.. .. . . . y I TIMEi t .

3. [DATE -I I I I

REACTOR SHUTDOWN I

Ii II START OF RELEASE

4. ACCIDENT MENU SELECTION o MENU B: FORWARD CALCULATIONS OR 0 MENU G: BLOWOUT PANEL CALCULATIONS (MONITORED RELEASE or BLOWOUT PANEL CALCULATION) o MENU E-W: BACK CALCULATIONS FIELD MONITOR PARAMETER SELECTION l FIELD MONITOR READING (MR/HR)

DISTANCE FROM PLANT (MILES)

IODINE CARTRIDGE NETCPM l l CVcc l J lDEFAULT MIX

5. SOURCE TERM CHARACTERIZATION BLOWOUT PANEL LIFTED:

0 ATWS 0 NORMAL RX COOLANT ACTIVITY E3 RCIC PUMP ROOM 0 LOCA (RX DP-NO FD) 03 HPCI PUMP ROOM 0 LOCA (CLAD FAILURE) 03 HPCIIRCIC ROUTING AREA 13 0 LOCA (FUEL MELT) 03 RWCU PENETRATION ROOM 0 FUEL HANDLING ACCIDENT RB/TB MAIN STEAM TUNNEL

6. (REMAINING) DURATION OF RELEASE I J (MINUTES)

EP-AD-000-099, Revision 1, Page 1 of 2

Tab 13 EP-PS-244-1 3 Im r. AC~~wLOVV PRIORTYi' 4.ov'1 .<w .Xeo .c

7. , S1TE1~OTAL RELEASE ~> XATES Measured or Default NOBLE GAS _ _

1-131 PARTICULATES

8. PROJECTION TIME (IF OTHER THAN 6 HOURS) 9.

10 m WIND SPEED l [(MPH) 10 m WIND DIRECTION (DEG FROM)-

STABILITY CLASS (DEG C)

RAIN (IN115 MINUTES)

10. K ,,. B D 6<7Ei DSE R-3ATES i -. i' 3 MREMIHR l SECTOR EDE I l CDE ll EP-AD-000-099, Revision 1, Page 2 of 2

Tab 16 EP-PS-244-1 6 PICSY VENT RELEASE RATES GUIDELINES SITE TOTAL RELEASE RATES ILCimin RELEASE UNUSUAL EVENT ALERT EAL

Reference:

N/A 15.1 15.2 as read in PICSY for 60 min as read in PICSY NOBLE GAS: Any noticeable increase 2.OOE+ra- 2.00E+8 above pre-event values EP-AD-000-088, Revision 1, Page 1 of 1

Tab 19 EP-PS-244-1 9 IDENTIFICATION OF RELEASE IN PROGRESS There is a radiological release in progress if ANY of the following are true:

1.0 Any release rates above Technical Specifications or Technical Requirements Manual limits, OR 2.0 Entry into the Emergency Plan for the listed EALs:

3.0 Fuel Clad Degradation

15.0 Radiological Effluents

. 17.0 Spent Fuel Related Incident

18.0 Steam Line Break

21 Dry Fuel Storage, AND the DSC has been breached, OR 3.0 The Shift Manager/ED/RM has reason to believe that an unmonitored release is in progress even though plant indications are otherwise normal, OR 4.0 Initiation of the Standby Gas Treatment System for treatment of activity within containment, OR 5.0 Any radiological release above normal levels to the environment, detected by effluent monitors 5.1 or environmental monitoring, 5.2 and attributable to a declared event.

5.3 Normal levels are the highest reading in the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the emergency, excluding the current peak value. The Dose Assessment Staff is not required to determine this quantitatively. Dose Assessment Staff should identify a release in progress if:

release rates are visibly higher than known data prior to the start of the event, OR

information is received from Operations that release rates are above normal levels and are attributable to a declared event.

5.4 Field monitoring readings above instrument lower limits of detection or RMS readings yielding unanticipated alarms.

EP-AD-000-51 1, Revision 0, Page 1 of 1

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