ML021910418
| ML021910418 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/02/2002 |
| From: | Pennsylvania Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| EP-PS-105-6 | |
| Download: ML021910418 (82) | |
Text
Jul. 02, 2002 Page I of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2002-3134 USER INFORMATION:
-L*A+/-MWAUnEL B EMPL#:23244 CA#: 0386 Ad~recc: NUCCA2 Phone#: 254-3658 TRANSMITTAL INFORMATION:
- FLAIULAUnEL B 07/02/2002 LOCATION: DOCUMENT CONTROL DESK FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER NUCSA-2)
£HE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
105 - 105 - TSC DOSE CALCULATOR: EMERGENCY PLAN POSITION SPECIFIC PROCEDURE REMOVE MANUAL TABLE OF CONTENTS DATE: 02/27/2002 ADD MANUAL TABLE OF CONTENTS DATE: 07/01/2002 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-105 REPLACE: REV:13 REPLACE: REV:13 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.
TAB 6 EP-PS-1 05-6 EMERGENCY CLASSIFICATION CHECK E0 1.0 TIMING OF CLASSIFICATION E0 1.1 UNUSUAL EVENT An UNUSUAL EVENT shall be declared within 15 minutes of having information necessary to make a declaration.
0 1.2 ALERT An ALERT shall be declared within 15 minutes of having information 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 16, Page 1 of 39
TAB 6 EP-PS-105-6 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 16, Page 2 of 39
TAB 6 EP-PS-105-6 POLICY STATEMENT ON EMERGENCY DECLARATIONS Policy When an emergency action level (EAL) is exceeded but the plant quickly returns below the EAL, the emergency should be declared. If appropriate, the emergency can also be downgraded or terminated at essentially the same time and the Emergency Notification Form can say the emergency was declared and terminated (or downgraded) minutes later.
Example The main steam lines isolate on high radiation due to a large oil intrusion into the vessel. The isolation on high radiation is a trigger to declare an Alert. If it can quickly be determined that the cause was not damage to the fuel and we should not be in an Alert, then the Alert should be declared and terminated with the same notification report.
Basis Declaring the emergency will notify interested offsite personnel and will demonstrate that we recognize that we exceeded an EAL. Immediately terminating or downgrading will avoid activation of company and offsite facilities that are not required for this event.
EP-AD-000-200, Revision 16, Page 3 of 39
TAB 6 EP-PS-105-6 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 16, Page 4 of 39
TAB 6 EP-PS-1 05-6 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE 1 AIRCRAFT/TRAIN ACTIVITY ................................................................ 6 2 CONTROL ROOM EVACUATION .................................................... 7 3 FUEL CLADDING DEGRADATION .................................................... 8 4 G EN ERA L ...................................................................................... 11 5 INJURED/CONTAMINATED PERSONNEL .................................... 12 6 IN-PLANT HIGH RADIATION .......................................................... 13 7 LOSS OF AC POW ER ...................................................................... 14 8 LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS ....... 15 9 LOSS OF DC POW ER ..................................................................... 16 10 LOSS OF DECAY HEAT REMOVAL CAPABILITY ......................... 17 11 LOSS OF REACTIVITY CONTROL .................................................. 18 12 LOSS OF REACTOR VESSEL INVENTORY ................................... 20 13 NATURAL PHENOMENA ............................................................... 22 14 ONSITE FIRE/EXPLOSION ......... ............................. 24 15 RADIOLOGICAL EFFLUENT .......................................................... 26 16 SECURITY EVENT .......................................................................... 30 17 SPENT FUEL RELATED INCIDENT ............................................... 32 18 STEAM LINE BREAK ..................................................................... 34 19 TOXIC/FLAMMABLE GASES .............................................................. 37 20 TECHNICAL SPECIFICATION SAFETY LIMIT ............................... 38 21 DRY FUEL STORAGE ..................................................................... 39 EP-AD-000-200, Revision 16, Page 5 of 39
TAB 6 EP-PS-105-6 1 - AIRCRAFT/TRAIN 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 200°F as indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 1.4 None.
EP-AD-000-200, Revision 16, Page 6 of 39
TAB 6 EP-PS-1 05-6 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 stations.
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 16, Page 7 of 39
TAB 6 EP-PS-105-6 3 - FUEL CLADDING DEGRADATION UNUSUAL EVENT EAL# 3.1 Core degradation as indicated by:
(A orB)
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 !tCi/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 jiCi/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 16, Page 8 of 39
TAB 6 EP-PS-105-6 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 pCi/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 16, Page 9 of 39
TAB 6 EP-PS-1 05-6 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. (1 and.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. (aorborc)
- 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 pCi/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 16, Page 10 of 39
TAB 6 EP-PS-105-6 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 PP&L, 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 16, Page 11 of 39
TAB 6 EP-PS-105-6 5.- INJURED/CONTAMINATED 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 16, Page 12 of 39
TAB 6 EP-PS-1 05-6 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 GB Cc CN
+ + C_ 500 DACA DAC8 DACc DACJ, 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.
EP-AD-000-200, Revision 16, Page 13 of 39
TAB 6 EP-PS-1 05-6 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 0C653.
or B. Failure of all diesel generators to start or synchronize to the emergency buses by indication or annunciation on Panel 0C653.
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 0C653.
and B. Failure of all diesel generators to start or synchronize to the emergency buses by annunciation or indication on Panel 0C653.
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 0C653.
and C. The above conditions exist for greater than 15 minutes.
GENERAL EMERGENCY EAL# 7.4 None.
EP-AD-000-200, Revision 16, Page 14 of 39
TAB 6 EP-PS-1 05-6 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 or2 or3 or4)
- 1. Low-Low reactor water level indication on Panel lC651-(2C651) followed by ECCS initiation on Panel 1C601 (2C601).
or
- 2. Reactor coolant temperature change greater than 100OF 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-00-200, Revision 16, Page 15 of 39
TAB 6 EP-PS-1 05-6 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 1D612 (2D612), 1D622 (2D622), 1 D632 (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 (2D622), 1D632 (2D632), and 1D642 (2D642) as indicated by trouble alarms on Panel 1C651 (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 16, Page 16 of 39
TAB 6 EP-PS-105-6 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 0 F.
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 2001F 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 290°F indicated on the computer output (MAT 12,13,14,15 or 16).
EP-AD-000-200, Revision 16, Page 17 of 39
TAB 6 EP-PS-1 05-6 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 16, Page 18 of 39
TAB 6 EP-PS-105-6 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 2000 F, 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 16, Page 19 of 39
TAB 6 EP-PS-105-6 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 1C651 (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 orB)
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 1 C601 (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 16, Page 20 of 39
TAB 6 EP-PS-1 05-6 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. (aorborc)
- 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 16, Page 21 of 39
TAB 6 EP-PS-105-6 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 16, Page 22 of 39
TAB 6 EP-PS-1 05-6 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 200°F as indicated on Panel 1C651 (2C651).
and B. (1 or2 or3)
- 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 0C696.
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 16, Page 23 of 39
TAB 6 EP-PS-105-6 14 - ONSITE FIREIEXPLOSION 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:
(Aor 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 equipfnent 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 16, Page 24 of 39
TAB 6 EP-PS-105-6 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 16, Page 25 of 39
TAB 6 EP-PS-105-6 15 - RADIOLOGICAL EFFLUENT UNUSUAL EVENT EAL# 15.1.a Radiological gaseous effluents exceed 2 times the Technical Requirement Limits for 60 minutes or longer as indicated by:
(A or B)
A. Valid Building Vent Stack Monitoring System (SPING) indications on Panel 0C630 or 0C677.
- 1. Noble gases >1.70E+6 g.Ci/min., or
- 2. 1-131 >2.08E+2 laCi/min., or
- 3. Particulate >1.54E+3 4Ci/min., or or B. Confirmed sample analyses for gaseous releases indicating total site release rates exceed:
- 1. Noble gases >1000 mrem/year whole body, or
- 2. Noble gases >6000 mrem/year skin, or
- 3. 1-131, 1-133, H-3, and particulates with half-lives >8 days >3000 mrem/year to any organ (inhalation pathways only).
OR EAL# 15.1.b Radiological liquid effluents exceed Technical Requirement Limits for instantaneous release as indicated by:
Report of radiological liquid effluent exceeding Technical Requirement Limits. This includes effluent sources such as Service Water or RHR Service Water Loops A or B.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 16, Page 26 of 39
TAB 6 EP-PS-105-6 15 - RADIOLOGICAL EFFLUENT (continued)
ALERT EAL# 15.2.a Radiological gaseous effluents exceed 200 times the Technical Requirement Limits for 15 minutes or longer as indicated by:
(A or B)
A. Valid Building Vent Stack Monitoring System (SPING) indications on Panel 0C630 or 0C677.
- 1. Noble gases >1.70E+8 ýtCi/min., or
- 2. 1-131 >2.08E+4 pCi/min., or
- 3. Particulate >1.54E+5 pCi/min.
or B. Confirmed sample analyses for gaseous releases indicating total site release rates exceed:
- 1. Noble gases >1.OE+5 mrem/year whole body, or
- 2. Noble gases >6.OE+5 mrem/year skin, or
- 3. 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 EAL# 15.2.b Radiological liquid effluents exceed 10 times Technical Requirement Limits for instantaneous release as indicated by:
Report of radiological liquid effluent release exceeding 10 times Technical Requirement Limits. This includes effluent sources such as Service Water or RHR Service Water Loops A or B.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 16, Page 27 of 39
TAB 6 EP-PS-105-6 15 - RADIOLOGICAL EFFLUENT (continued)
SITE AREA EMERGENCY EAL# 15.3 Radiological effluent corresponds to greater than 50 mrem W.B.(1) or 250 mrem thyroid(2) for a half-hour or 500 mrem W.B.(0) or 2500 mrem thyroid(2) for 2 minutes at the emergency plan boundary as indicated by:
OR Emergency plan boundary dose is projected to exceed 500 mrem W.B. (1) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as indicated by:
(A or B)
A. Dose projections based on:
(1 or2)
- 1. Building vent stack monitoring system indications on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite.
or B. Dose projections based on:
(1 or2)
- 1. Building vent stack monitoring system indications on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite (CONTINUED ON NEXT PAGE)
(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) Committed Dose Equivalent to the thyroid from radioiodine.
EP-AD-000-200, Revision 16, Page 28 of 39
TAB 6 EP-PS-105-6 15 - RADIOLOGICAL EFFLUENT (continued)
GENERAL EMERGENCY EAL# 15.4 Radiological effluent release corresponds to 1 rem whole body(0) or 5 rem(2) thyroid at the emergency plan boundary as indicated by:
OR Offsite doses are projected to exceed 1 rem whole body(1 ) or 5 rem thyroid(2 ) due to the event as indicated by:
(A or B)
A. Dose projections based on:
(1 or2 or3)
- 1. Building Vent Stack Monitoring System indication on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite.
or
- 3. In-plant conditions.
or B. Dose projections based on:
(1 or2 or3)
- 1. Building Vent Stack Monitoring System indication on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite.
or
- 3. In-plant conditions.
(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) Committed Dose -Equivalent to the thyroid from radioiodine.
EP-AD-000-200, Revision 16, Page 29 of 39
TAB 6 EP-PS-1 05-6 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.
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 16, Page 30 of 39
TAB 6 EP-PS-1 05-6 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-00-200, Revision 16, Page 31 of 39
TAB 6 EP-PS-105-6 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 cc C' >_500 DACA DAC, 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 16, Page 32 of 39
TAB 6 EP-PS-1 05-6 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 or 2)
- 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 16, Page 33 of 39
TAB 6 EP-PS-1 05-6 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 16, Page 34 of 39
TAB 6 EP-PS-105-6 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
or
- f. Other indication of steam leakage from the RCIC system.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 16, Page 35 of 39
TAB 6 EP-PS-105-6 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. (aorborcordoreorf)
- 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
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 16, Page 36 of 39
TAB 6 EP-PS-105-6 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 16, Page 37 of 39
TAB 6 EP-PS-105-6 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 safety 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 16, Page 38 of 39
TAB 6 EP-PS-105-6 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 16, Page 39 of 39
TAB 8 EP-PS-105-8 PP&L 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 4 EMERGENCY EXPOSURE EXTENSIONS 5 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING AN EMERGENCY 8 EMERGENCY EXPOSURE EXTENSION REQUEST FORM and POTASSIUM IODIDE TRACKING FORM can be found immediately following EP-AD-000-125.
EP-AD-000-125, Revision 7, Page 1 of 10
TAB 8 EP-PS-105-8 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK El 1.0 Limits for EMERGENCY doses.
0 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).
El 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 sktn 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 7, Page 2 of 10
TAB 8 EP-PS-1 05-8 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
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 0 3.1 Potassium Iodide 3.1.1 For emergency workers entering areas where a committed dose equivalent, (CDE)(2 ), to the thyroid from radioiodine could be 25 Rem or greater, the Consulting Radiological Physician should provide input concerning the administration and cessation of KI intake. (See Emergency Telephone Directory for telephone number.)
3.1.2 For thyroid exposures that are strongly expected to exceed 25 Rem, (CDE)(2 ), KI doses of 130 mg (100 mg - iodine) per day should be administered.
Unless the EMERGENCY DIRECTOR or RECOVERY MANAGER instructs personnel to do otherwise, the KI tablets should generally be taken as soon as possible after thyroid exposure exceeding 25 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 one or two hours after uptake of radioiodine.
(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 7, Page 3 of 10
TAB 8 EP-PS-105-8 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK 0l 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 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.
El 3.2 Protective measures should be implemented for EOF personnel at the direction of the DOSE ASSESSMENT SUPERVISOR.
El 3.3. Exposures to members of local offsite support groups, (ambulance workers, fire fighters) shall not exceed 500 mrem (TEDE)(1) for the performance of support duties on the site of the Susquehanna SES.
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.
(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 7, Page 4 of 10
TAB 8 EP-PS-105-8 EMERGENCY EXPOSURE EXTENSIONS CHECK 0l
- 1. 'Fill out the attached EMERGENCY EXPOSURE EXTENSION REQUEST Form.
- 2. Review the following factors:
"El Rescue personnel should be volunteers or professional rescuers.
"El Other considerations being equal (e.g., skill, potential need for person on another mission) personnel above the age of 45 are preferred.
"El Rescue personnel should be familiar and briefed with the consequences of exposure.
"El Women capable of reproduction should not take part in an effort requiring EMERGENCY exposure.
"El Use of personnel with high lifetime cumulative exposure should be discouraged.
"El All reasonable measures must be taken to control contamination and internal exposure.
"El Exposure under these conditions shall be limited to once in a lifetime.
"El 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 7, Page 5 of 10
TAB 8 EP-PS-1 05-8 EMERGENCY EXPOSURE EXTENSIONS (continued)
CHECK 0 Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours(a)
Whole Body Absorbed Early Fatalitiesb Whole Body Absorbed Prodromal Effectsc 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.
b Supportive medical treatment may increase the dose at which 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) (deaths per 1,000 persons exposed) (years) 20 to 30 9.1 24 30 to 40 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 APPROVAL ACTIONS FROM TO mrem mrem (TEDE) (TEDE) 4000 <25000 ED and RPC/RM and DASU ALARA REVIEW AND APPLY EMERGENCY EXPOSURE CONSIDERATIONS ALL OF ABOVE AND
>25000 ED and RPC/RM and DASU BRIEFING ON RISKS EP-AD-000-125, Revision 7, Page 6 of 10
TAB 8 EP-PS-1 05-8 EMERGENCY EXPOSURE EXTENSIONS (continued)
CHECK 0
- 5. Ifthe 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.
"El 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:
Notification of the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is required for:
"El Assess the health consequences of all emergency exposures. Consult with a physician to determine the need for and extent of physical and biochemical examinations.
"El Whole body greater than 25 Rem (TEDE) should result in an examination of the exposed person by a physician.
"El If internal exposure is suspected, quantitative measurements should be made immediately. 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 7, Page 7 of 10
TAB 8 EP-PS-1 05-8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECK El 1.0 Evaluate radiological conditions.
0 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 El 1.2 Evaluate personnel status.
1.2.1 Determine available dose under normal administrative dose objectives.
1.2.2 Ifessential, obtain approval from RADIATION PROTECTION
- COORDINATOR/EMERGENCY DIRECTOR for persons expected to exceed administrative objectives.
1.2.3 Follow criteria in PP&L 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-000-125, Revision 7, Page 8 of 10
TAB 8 EP-PS-105-8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES (continued)
CHECK 0 0 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.
0l 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.
O 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 7, Page 9 of 10
TAB 8 EP-PS-105-8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES (continued)
CHECK [I 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 7, Page 10 of 10
TAB 9 EP-PS-1 05-9 METNENT DATA ACQUISITION OPTIONS The following are sources of meteorological and ventilation data at Susquehanna SES:
A. ACQUISITION OF METNENT DATA FROM THE PICSY TERMINAL
[ENTER].
- 2. All required meteorological and ventilation (MET/VENT) inputs for the MIDAS dose projections can be obtained by selecting the METNENT DATA display option on the E-PLAN menu.
- a. Vent and Primary Met Tower Data is displayed on page 1 of this display.
- b. Use the PAGE FORWARD command if the Back-up Tower data is required.
- c. Should neither the Primary or Back-up Tower be available, obtain the Downriver Tower data as follows:
- 1) Click on the E-PLAN MENU button at the top right hand corner of the MET/VENT DATA screen.
- 2) On the E-Plan menu select and click on the MET DATA screen.
- 3) Obtain the Downriver Tower wind speed (Point ID VMS05B), wind direction (Point ID VMX09B), and sigma theta (Point ID VMXI0B).
- 4) Return to the E-Plan menu by clicking on the E-PLAN MENU button at the bottom right hand corner of the MET DATA screen.
- d. Other options - see Step 6 below.
- 3. If the Primary Met Tower AT data is not available, determine the wind speed corrected stability class as follows:
- a. Determine the initial (uncorrected) stability class using the measured value of sigma theta and the Supplemental Meteorological Information Table 1 (or page 2 of the PICSY screen).
- b. Determine the wind speed corrected stability classification using the initial classification, the measured wind speed, and, as appropriate, either Table 2 or Table 3.
EP-AD-000-124, Revision 19, Page 1 of 8
TAB 9 EP-PS-105-9
- 4. The PICSY QUALITY CODES for the display colors are as follows:
YELLOW: DATA ACCEPTABLE RED: DATA EXCEEDS WARNING LIMIT MAGENTA: DATA EXCEEDS ALARM SETPOINT WHITE: DATA SUSPECT
- 5. If a hard copy printout of the information is required you may either:
- a. Select the PRINT option using the pull down menu (screen copy takes approximately 3 minutes to complete); or
- b. Initiate the METNENT DATA LOG option as follows:
- 1) On the E-PLAN menu, select the FREE FORMAT LOG MENU.
- 2) To activate the TSC log, press [Fl], [22], and [ENTER].
To activate the EOF log, press [Fl], [9], and [ENTER].
NOTE: Be sure to read the log description because there are 2 logs for the TSC and 2 logs for the EOF.
- 3) The log will start printing at the next quarter hour.
- 4) To deactivate the TSC log, press [F3], [22], and [ENTER].
To deactivate the EOF log, press [F3], [9], and [ENTER].
- 6. If historical METNENT information is required, refer to the following instructions:
- a. At command line, type: GD AMETVENTI and [ENTER].
- b. Group point display for that display file will come up. Press the [F3] key for history. (See bottom of screen for F key menu.) A dialog box will appear.
- c. The work file name to be used is ARCHIVE.D, which is the default for that field.
- d. Enter the desired retrieval time. (Enter 15 for the delta time to receive a fifteen-minute period. Click on OK.)
- e. Group point display will return with 1 or 2 point values.
EP-AD-000-124, Revision 19, Page 2 of 8
TAB 9 EP-PS-1 05-9
- f. Press the [F4] key if you want to step slowly through the data. Press the [F5]
key if you want to step quickly through the data. (See bottom of screen for F key menu for more options.)
- g. The group' point display will return to real time when history is complete. A message at the top of the screen will alert you that it is returning to real time.
- 6. To exit the menu, select the [ESC] key.
B. Site-specific meteorological information can be obtained by contacting either ABS Consulting or the National Weather Service (NWS).
- 1. ABS Consulting ABS Consulting is the primary meteorological contractor for the Susquehanna Steam Electric Station (SSES). ABS Consulting has the ability to interrogate the primary and backup meteorological towers on a real-time basis and provide short and long-term weather forecasts for the site and surrounding area.
ABS Consulting provides this emergency service to PPL ONLY during normal working hours. The SSES Project Manager's name, phone number and mailing address are as follows:
ABS Consulting Mark Abrams (301) 907-9100 (301) 907-0050 (Fax)
ABS Consulting Suite 620 East 7315 Wisconsin Avenue Bethesda, MD 20814
- 2. NATIONAL WEATHER SERVICE The National Weather Service's (NWS) primary meteorological support responsibility for a radiological emergency at SSES resides with the NWS office at Binghamton, New York. In the event the Binghamton office is unable to provide this support, the designated backup is the NWS office in State College, Pennsylvania.
EP-AD-000-124, Revision 19, Page 3 of 8
TAB 9 EP-PS-1 05-9 The role of the local NWS office is to provide weather information and forecasts in support of emergency response activities at SSES. The NWS can be consulted over the telephone if data interpretations, assessment, or forecasting assistance are needed.
This information will include the following:
"* Forecasts at current time and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of:
a.. 10-meter and 60-meter wind speed and wind direction,
- b. Precipitation rate in inches per 15 minutes, and,
- c. Boundary layer atmospheric stability described as STABLE, UNSTABLE, or NEUTRAL.
"* Estimates of current 10-meter and 60-meter wind speed and wind direction in the event of complete loss of onsite and offsite meteorological instrumentation.
" General weather forecast from current time to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with special emphasis on significant weather occurrences such as major changes in wind speed, wind direction or synoptic weather patterns.
"* Periodic weather updates at time intervals dictated by the on-going weather and emergency situation.
NOTE: The NWS should ONLY be contacted when meteorological support from ABS Consulting is not available (i.e., weekends, holidays, and during the overnight hours).
Whenever contacting the NWS, be sure to provide the following information:
- Name, Title, Facility, and Location
- Reason for the call
- Status of the Emergency
- Return telephone number EP-AD-000-124, Revision 19, Page 4 of 8
TAB 9 EP-PS-105-9 The following telephone numbers are UNLISTED and should only be used for EMERGENCY situations.
PRIMARY CONTACT NWS EMERGENCY METEOROLOGICAL SUPPORT OFFICE National Weather Service Office Binghamton Regional Airport 32 Dawes Drive Johnson City, NY 13795 (607) 798-6625 (607) 729-7629 (607) 798-6624 (Fax)
BACKUP CONTACT NWS EMERGENCY METEOROLOGICAL SUPPORT OFFICE National Weather Service Office 227 W. Beaver Avenue, Suite 402 State College, PA 16801 (814) 237-1152 (814) 237-1153 (814) 234-9703 (Fax)
EP-AD-000-124, Revision 19, Page 5 of 8
TAB 9 EP-PS-105-9 PLANT COMPUTER METEOROLOGICAL DATA POINT IDENTIFIERS METEOROLOGICAL PARAMETER PRIMARY TOWER - east M U 10m Wind Direction degrees 15 minutes 10m Wind Speed vma06 mph 15 minutes Delta T "A" vma0l °C/50m 15 minutes Delta T "B" vma02 0C/50m 15 minutes 60m Wind Direction vma04 degrees 15 minutes 60m Wind Speed vma07 mph 15 minutes 10m Sigma Theta vmal0 degrees 15 minutes 60m Sigma Theta vmx24 degrees 15 minutes Precipitation Rate vma09 in/hr 15 minutes Ambient Temperature vmt08b OF 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> m U I BACKUP TOWER - across from the SSES Learning Center.
10m Wind Direction vma05 degrees 15 minutes 10m Wind Speed vma08 mph 15 minutes 1Dm Sigma Theta vma12 degrees 15 minutes DOWNRIVER TOWER - on Route 93just east of Nescopeck.
1Om Wind Direction vmx09b degrees 2 minutes**
1Dm Wind Speed vmsO5b mph
- 2 minutes**
10m Sigma Theta vmxl0b degrees 2 minutes**
- Letters are given here in lower case to differentiate the letter o from the number 0.
EP-AD-000-124, Revision 19, Page 6 of 8
TAB 9 EP-PS-1 05-9 SUPPLEMENTARY METEOROLOGICAL INFORMATION TABLES TABLE 1 ATMOSPHERIC STABILITY CLASSIFICATION Stability Class Delta (Alternate) Plume Width Temperature Sigma Theta @ 10 miles % of Hrs at Code Title (°C/50m) (degrees) (miles) SSES A Very Unstable <-.95 >_22.5 5.7 6 B Unstable -.94 to -.85 17.5 to 22.4 4.3 3 C Slightly Unstable -.84 to -.75 12.5 to 17.4 3.3 4 D Neutral -.74 to -.25 7.5 to 12.4 2.3 35 E Slightly Stable -.24 to .75 3.8 to 7.4 1.6 32 F Stable .76 to 2.0 2.1 to 3.7 1.1 12 G Very Stable >2.0 <2.1 .75 8 TABLE 2 TABLE 3 DAYTIME NIGHTTIME (08:00 to 18:00) (18:00 to 08:00)
Initial Stability Class/ FINAL Initial Stability Class/ FINAL Wind Speed (MPH) VALUE Wind Speed (MPH) VALUE A A Wind Speed < 7 A 6 < Wind Speed F 7:< Wind Speed < 9 B 6 < Wind Speed < 8 E 9 < Wind Speed < 13 C Wind Speed > 8 D Wind Speed > 13 D
-B B
9 < Wind Speed B 5 < Wind Speed F 9 < Wind Speed < 13 C 5 <Wind Speed < 7 E Wind Speed > 13 D Wind Speed _>7 D C C 13 < Wind Speed C 5 < Wind Speed E Wind Speed > 13 D Wind Speed > 5 D D, E, F, G D Any wind speed. D Any wind speed. D E
11 < Wind Speed E Wind Speed _> 11 D Example: If wind speed is 9 mph and sigma F,G theta is 18 degrees @ 10 a.m., the initial 7 < Wind Speed F stability class from Table I is "B" and the wind speed corrected stability class from Table 2 is 7< Wind Speed < 11 E
".C".
Wind Speed > 11 D EP-AD-000-124, Revision 19, Page 7 of 8
TAB 9 EP-PS-105-9 TABLE 4 WIND SECTORS AND DISTANCES Wind From Affected Affected EPB* On-Site Team Site Boundary % of Hrs Sector Degrees Sector Sector Distance (mi) Distance,(mi) Distance (mi) Affected SSES 348-11 N S 0.34 0.25 0.38 6 12 - 33 NNE SSW 0.34 0.37 0.39 9 34- 56 NE SW 0.34 0.33 0.61 12 57-78 ENE WSW 0.34 0.39 1.22 11 79-101 E W 0.34 0.37 1.03 6 102-123 ESE WNW 0.34 0.41 0.61 4 124-146 SE NW 0.34 0.35 0.66 4 147 - 168 SSE NNW 0.34 0.29 0.59 4 169-191 S N 0.34 0.29 0.59 5 192-213 SSW NNE 0.34 0.39 0.78 7 214-236 SW NE 0.34 0.42 0.58 11 237 - 258 WSW ENE 0.34 0.52 0.49 7 259 - 281 W E 0.34 0.45 0.48 4 282 - 303 WNW ESE 0.34 0.18 0.50 3 304 - 326 NW SE 0.34 0.20 0.43 3 326 - 348 NNW SSE 0.34 0.20 0.41 5
"-PE aistances establisned at Exclusion Area Boundary distance of 1800 ft.
EP-AD-000-124, Revision 19, Page 8 of 8
TAB 11 EP-PS-105-11 MIDAS OPERATING PROCEDURE TABLE OF CONTENTS A. INTRODUCTION/SYSTEM STARTUP 2
" AIRBORNE DOSE ASSESSMENT FLOWCHART 4
"* EVALUATION OF UNMONITORED RELEASES FROM STATION BLOWOUT PANELS 5
"* SSES BLOWOUT PANEL LOCATIONS 6 B. MENU B: FORWARD CALCULATIONS 7 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS 12 D. MENU D: DEFAULT ACCIDENT CALCULATIONS 15 E. MENU E-W: BACK CALCULATIONS 18 F. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE
SUMMARY
REPORT 24 EP-AD-000-1 12, Revision 17, Page 1 of 24
TAB 11 EP-PS-105-11 A. INTRODUCTION/SYSTEM 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before the current time and the last time interval is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 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:
- a. Turn 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. Ifthe date is correct, press [ENTER]. Ifthis 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]. Ifthis 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 17, Page 2 of 24
TAB 11 EP-PS-1 05-11
- f. The MIDAS logon screen will now appear for 20 seconds.
- g. The ACCIDENT MENU SELECTION screen will appear. Use the AIRBORNE DOSE ASSESSMENT FLOWCHART to select the appropriate calculation option and CONFIRM your selection.
- 5. To exit MIDAS, double-click EXIT on each menu screen that appears. At the SECURITY MENU, press [F8] to log off.
EP-AD-000-1 12, Revision 17, Page 3 of 24
TAB 11 EP-PS-1 05-11 AIRBORNE DOSE ASSESSMENT FLOW CHART MONITOR CONDITIONS PLANT STATUS/PROGNOSIS ONSITE RAD CONDITIONS STATUS OF RELEASE DOSE PROJECTIONS WEATHER CONDITIONS OCCURRED OR ONE IS IN PROGRESS IF ANY OF THESE HAVE BEEN EXCEEDED:
SPING SITE TOTAL RELEASE RATES NOBLE GAS: 8.51 E+05 uCi/min 1-131: 1.04E+02 uCi/min PARTICULATES: 7.72E+02 uCi/min REVISED: 10/13/2000 NO Select Iseec MENU B t MENU E-W DETERMINE RELEASE RAT.ES FROM THE BLOWOUT PANEL TABLE, USE THEM FOR A MENU B CALCULATION l EP-AD-000-112, Revision 17, Page 4 of 24
TAB 11 EP-PS-105-11 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] BLOWOUT PANEL LOCATION 3 ]DESIGN BASIS (SITE TOTAL) RELEASE RATES NOBLE GAS 1-131 PARTICULATE RCIC PUMP ROOM (pCi/min) (plCi/min) (pjCi/min)
[2 ] 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 2.1 E+09 2.4E+08 9.1 E+07 (LOCA) 100% Fuel Melt 4.3E+1 0 1.3E+09 1.7E+09 HPCI PUMP ROOM (pCi/min) (pCi/min) (pCi/min)
Normal Reactor Coolant Activity 2.1 E+03* 3.2E+03 1.9E+04 (LOCA) Reactor Depressurization-No FD 4.6E+07 1.5E+06 3.8E+05 (LOCA) 100% Clad Failure 3.7E+1 0 4.3E+09 1.6E+09 (LOCA) 100% Fuel Melt 7.5E+1 1 2.3E+1 0 3.0E+1 0 HPCI/RCIC ROUTING AREA (pCi/min) (pCVmin) (pCi/min)
Normal Reactor Coolant Activity 3.2E+03" 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 1.1 E+12 3.5E+10 4.6E+10 RWCU PENETRATION ROOM (OCi/min) (pCi/min) (IpCi/min)
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 4.1 E+1 0 1.0E+1 1 RB/TB MAIN STEAM TUNNEL (pCimin) (ijCi/min) (JCi/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+1 1 5.2E+1 0 1.9E+1 0 (LOCA) 100% Fuel Melt 9.1 E+1 2 2.8E+1 1 3.7E+1 1 FD = FUEL DAMAGE
- Value less than that defining a release (See previous page).
REFERENCE:
EC-RADN-1 018, Evaluation of Unmonitored Releases from Station Blowout Panels, Revision 2, File R2-1.
EP-AD-000-1 12, Revision 17, Page 5 of 24
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TAB 11 EP-PS-1 05-11 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 0 10 M WIND SPEED 0 10 M WIND DIRECTION 0 STABILITY CLASS 0 PRECIPITATION RATE VENT DATA
"* SITE TOTAL NOBLE GAS RELEASE RATES
"* SITE TOTAL 1-131 RELEASE RATES
"* SITE TOTAL PARTICULATE RELEASE RATES
- 1. The METNENT DATA CONTROL TABLE screen will appear.
- a. Select START NEW SCENARIO and then CONFIRM, OR
- b. Ifyou have already initiated calculations and wish to modify either the existing met spreadsheet file or vent spreadsheet, 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 or change your initial selection or EXIT the screen.
- 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:
EP-AD-000-1 12, Revision 17, Page 7 of 24
TAB 11 EP-PS-1 05-11 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: Any time historical data is being used in MIDAS (i.e., met and vent data entered into the spreadsheets within the two-hour period up to and including the current time), all met and vent data must be manually entered over all affected time periods up to and including the current time.
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 10M SPD, enter the wind speed from the 10 meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).
NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
- 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 0(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.
- 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.
EP-AD-000-112, Revision 17, Page 8 of 24
TAB 11 EP-PS-105-11
- 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 vent data from the START OF RELEASE. 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 jgCi/min.
- b. In the column labeled TOT 1-131 RELEASE, enter the site total 1-131 release rate in gCi/min.
- c. In the column labeled TOT P RELEASE, enter the site total particulate release rate in gCi/min.
- d. When the data entry is complete, press the X key to save the information and exit the spreadsheet.
- 5. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM. Sel6ct RESET if you wish to change your previous selection.
If no specific information on the type opf release is available from Engineering, use the following as a guide in the selection of appropirate accident source term.
- a. From PICSY, obtain readings for the Containment High Range Radiation Monitors (CHRM). These are computer points MAR01 and MAR02, and obtain the current reactor power level.
- b. Ensure the CHRM values are within reasonable agreement; if not, use the higher value.
- c. Ifthe reactor is operating at greater than 10% power, select the ATWS source term.
- d. With the reactor at less than 10% power and if the CHRM reading is less than 5 R/hr, select Normal Rx Coolant Activity.
EP-AD-000-112, Revision 17, Page 9 of 24
TAB 11 EP-PS-105-11
- f. If the CHRM reading is greater than 200 R/hr but less than 2000 R/hr, select LOCA (Clad Failure).
- g. If the CHRM reading is great than 2000 R/hr, select LOCA (Fuel Melt).
- h. 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 <br />0.0528 hours <br />3.141534e-4 weeks <br />7.2295e-5 months <br />) prior to the START OF RELEASE.
- 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 DATE. Using the calendar wheel, enter the appropriate date and time of the start of release.
CONFIRM to close the calendar wheel.
NOTE: The START OF RELEASE is defined as the date and time of the first vent data entry. This time range includes the two-hour period prior to and including the current time.
EP-AD-000-1 12, Revision 17, Page 10 of 24
TAB 11 EP-PS-105-11
- c. On Line 3, select REMAINING DURATION. Using the NUMPAD enter the duration of release, in minutes, and select EN or press [ENTER] to close the numpad. Ifthe 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 <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> into the future.
- d. Select CONFIRM to continue with the calculation or RESET to change any of your previous choices.
- 7. The PP&L
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE
SUMMARY
REPORT.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
- b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. Ifyou 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 CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.
- 8. After the calculations have completed, the MIDAS DOSE
SUMMARY
REPORT will be displayed on the screen.
- a. Ifyou want to select a different projection time or sector designation from the PP&L
SUMMARY
DATA SELECTION screen, select RESTART REPORT.
- b. Ifyou wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.
- c. Ifyou 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: Ifa hard-copy printout is made of the.MIDAS DOSE
SUMMARY
REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.
EP-AD-000-1 12, Revision 17, Page 11 of 24
TAB 11 EP-PS-1 05-11 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
"* CONTAINMENT CONDITIONS
"* FILTRATION
"* PROJECTION TIME MET DATA S10 MWIND 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.
- b. [PRINT SCREEN] when final selections are made on the EVENT TREE NUREG-1228 SELECTION screen to document the calculation inputs.
- 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.
- 2. 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 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 17, Page 12 of 24
TAB 11 EP-PS-1 05-11
- 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 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).
NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
- b. In the column labeled 1OM 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 0(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.
- 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 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.
EP-AD-000-112, Revision 17, Page 13 of 24
TAB 11 EP-PS-105-11
- 5. The PP&L
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE
SUMMARY
REPORT.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
- b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; 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 CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.
- 6. After the calculations have completed, the MIDAS DOSE
SUMMARY
REPORT will be displayed on the screen.
- a. If you want to select a different projection time or sector designation from the PP&L
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
SUMMARY
REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.
EP-AD-000-112, Revision 17, Page 14 of 24
TAB 11 EP-PS-1 05-11 D. MENU D: DEFAULT ACCIDENT CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.
MET DATA
- 10 MWINDSPEED
- 10 M WIND DIRECTION e 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. 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.
- 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 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
- b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).
EP-AD-000-112, Revision 17, Page 15 of 24
TAB 11 EP-PS-105-11
- 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) ifthe 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 0(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.
- 3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.
- a. Ifthis 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. 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.
- 6. The PP&L
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE
SUMMARY
REPORT.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
- b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. Ifyou wish to change any of your previous choices, select RESET.
EP-AD-000-1 12, Revision 17, Page 16 of 24
TAB 11 EP-PS-105-11 NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.
- 7. After the calculations have completed, the MIDAS DOSE
SUMMARY
REPORT will be displayed on the screen.
- a. Ifyou want to select a different projection time or sector designation from the PP&L
SUMMARY
DATA SELECTION screen, select RESTART
-PROGRAM.
- b. Ifyou wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.
- c. Ifyou 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
SUMMARY
REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.
EP-AD-000-1 12, Revision 17, Page 17 of 24
TAB 11 EP-PS-105-11 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
- 10 M WIND SPEED 0 10 M WIND DIRECTION 0 STABILITY CLASS
- PRECIPITATION RATE FIELD DATA
- 3 FT (CW) SURVEY METER READING 0 DISTANCE FROM PLANT 0 IODINE CARTRIDGE NET CPM OR DEFAULT IODINE MIX
- 1. The METNENT DATA CONTROL TABLE screen will appear.
- a. Select START NEW SCENARIO and then CONFIRM.
- b. Ifyou 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.
- 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).
EP-AD-000-112, Revision 17, Page 18 of 24
TAB 11 EP-PS-1 05-11 NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
- b. In the column labeled IOM 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 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.
- 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. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.
- 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.
EP-AD-000-1 12, Revision 17, Page 19 of 24
TAB 11 EP-PS-1 05-11
- a. If air sample data is available, enter either the IODINE CARTRIDGE reading in net counts per minute or an IODINE CONCENTRATION value in gCi/cc. A zero (0) value may be entered for the net count per minute or the jCi/cc measurement, if indicated.
- b. Select the DEFAULT MIX option if you wish to characterize the iodine source term when air sample data is not available.
- 6. On the RELEASE TIMING SELECTION screen, enter the estimated remaining duration for the release, then CONFIRM. If the duration of release is hot known, use the default of 360 minutes.
- 7. The PP&L
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE
SUMMARY
REPORT.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
- b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; 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 CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.
- 8. After the calculations have completed, the MIDAS DOSE
SUMMARY
REPORT will be displayed on the screen.
- a. If you want to select a different projection time or sector designation from the PP&L
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
SUMMARY
REPORT, be sure to fill in the required information documenting EP-AD-000-1 12, Revision 17, Page 20 of 24
TAB 11 EP-PS-105-11 the name of the dose calculator, reviewer, and date the calculation was performed.
- 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
SUMMARY
REPORT 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.
- 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 17, Page 21 of 24
TAB 11 EP-PS-105-11 F. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE
SUMMARY
REPORT
- 1. PRINT DATE/TIME Date and time MIDAS DOSE
SUMMARY
REPORT was printed.
- 2. CURRENT TIME PERIOD Current meteorological time period used for dose projections provided on quarter hour increments to match met spreadsheet entries.
- 3. REACTOR SHUTDOWN Date and time of reactor shutdown.
- 4. START OF RELEASE 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 met data used for the current projection period.
NOTE: For MENU C: NR-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.
- 5. MENU SELECTION Identifies the dose calculation option used for the current dose projection summary report. Choice of four options:
"* MENU B: FORWARD CALCULATIONS
"* MENU C: NR-1228 CALCULATIONS
- MENU D: DEFAULT CALCULATIONS
- MENU E-W: BACK CALCULATIONS
- 6. SOURCE TERM 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)
EP-AD-000-1 12, Revision 17, Page 22 of 24
TAB 11 EP-PS-105-11
"* (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
- 7. MET DATA Meteorological data (wind speed, wind direction, stability class, and precipitation rate) used for the summary report dose projections.
- 8. CURRENT AFFECTED SECTOR OR PEAK SECTOR DOSE RATES 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.
- 9. PROJECTED DOSES This table provides a TEDE and THYROID CDE dose projection calculated at the OSCAR, EPB, 2-mile, and 10-mile distances for varying projection times.
The projection time will appear in the header line e.g., 4 HOUR PROJECTED DOSES on the MIDAS DOSE
SUMMARY
REPORT. The sector designation for this dose projection is based on the maximum calculated dose determined from all sixteen sectors for the given projection time.
- 10. CALCULATED/REVIEWED BY The sign-off for review of calculation results is done for documentation purposes. The intended review 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 review should occur before the calculated results are used for any emergency classification determinations or protective action recommendations.
- 11. COMMENTS Section added to provide space for additional statements of qualification or background information pertaining to the dose projections.
EP-AD-000-1 12, Revision 17, Page 23 of 24
TAB 11 EP-PS-105-11 MIDAS DOSE
SUMMARY
REPORT DATE/TIME: 8/19/97 11:25 CURRENT TIME PERIOD: 8/19/97 11:30 G PRINT MIDAS DOSE
SUMMARY
REPORT REACTOR SHUTDOWN: 8/19/97 18:53 MIND SPEED (MPH):. 5.
START OF RELEASE: 8/19/97 19:53 WIND FROM (DEG): 129 (ESE)
M-%
MENU SELECTION: FORWARD CALCULATIONS STABILITY CLASS: D SOURCE TERM: LOCA (CLAD FAILURE) PRECIPITATION: NO CURRENT (SITE TOTAL) RELEASE RATE (uCi/Min)
NOBLE GAS 1-131 PARTICULATES 6.98E+89 9.96E+81 9.96E+81 LOCUTONT " OSCA CTORDO RATES iiMT *P n UEA £ DOSE RATE AFFECTED DOSE RATE AFFECTED (Mrem/hr) SECTOR (rn'em/hr) SECTOR TEDE RATE 883.42 NNW 775.99 NNW EDE RATE 883.42 775.98 THY CDE 3.22 9.16 RATE CALCULATED BY: DATE:
REUIEWED BY: DATE:
COMMENTS:
RESTART 1~EIINUE EP-AD-000-1 12, Revision 17, Page 24 of 24