ML033230287
| ML033230287 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/13/2003 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033230287 (39) | |
Text
Nov. 13, 2003 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-54596 USER TNFOM~ N:bmr'_
GERLAC OSE M EMPL#:28401 CA#: 0363 Ad s UCSA2 hone#: 254-TRANSMITTAL INFORMATION:
TO: -- - - 11/13/2003 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:
127 - 127 - TECHNICAL SUPPORT CENTER (TSC)
COMMUNICATOR: EMERGENCY PLAN-POSITION SPECIFIC PROCEDURE REMOVE MANUAL TABLE OF CONTENTS DATE: 10/30/2003 ADD MANUAL TABLE OF CONTENTS DATE: 11/12/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-127 REPLACE: REV:16 REPLACE: REV:16 REMOVE: PCAF 2003-1482 REV: N/A REMOVE: PCAF 2003-1553 REV: N/A REMOVE: PCAF 2003-1641 REV: N/A ADD: PCAF 2003-1482 REV: N/A ADD: PCAF 2003-1553 REV: N/A ADD: PCAF 2003-1641 REV: N/A 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, Al14S
Tab 4 EP-PS-127-4 EMERGENCY CLASSIFICATION CHECK E 1.0 TIMING OF CLASSIFICATION Cl 1.1 UNUSUAL EVENT An UNUSUAL EVENT shall be declared within 15 minutes of having information necessary to make a declaration.
El 1.2 ALERT An ALERT shall be declared within 15 minutes of having-information necessary to make a declaration.
El 1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY shall be declared within 15 minutes of having information necessary to make a declaration.
E 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 21, Page 1 of 38
Tab 4 EP-PS-127-4 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 21, Page 2 of 38
- . Tab 4 EP-PS-1 27-4 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 21, Page 3 of 38
Tab4 EP-PS-127-4 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE 1 AIRCRAFT/TRAIN ACTIVITY ..................................... ; . 5 2 CONTROL ROOM EVACUATION ...................................... : . 6 3 FUEL CLADDING DEGRADATION ..................................... : . 7 4 GENERAL .................................... 10 5 INJURED/CONTAMINATED PERSONNEL .11 6 IN-PLANT HIGH RADIATION ..................................... - 12 7 LOSS OF AC POWER .13 8 LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS .14 9 LOSS OF DC POWER .15 10 LOSS OF DECAY HEAT REMOVAL CAPABILITY ........................................ 16 11 LOSS OF REACTIVITY CONTROL ................................ 17 12 LOSS OF REACTOR VESSEL INVENTORY ................................19 13 NATURAL PHENOMENA .................... ;.;.21 14- ONSITE FIRE/EXPLOSION .................................... ..::.;... 23 15 RADIOLOGICAL EFFLUENT ................................... , 25 16 SECURITY EVENT .29 17 SPENT FUEL RELATED INCIDENT .31 18 STEAM LINE BREAK .33 19 TOXIC/FLAMMABLE GASES .36 20 TECHNICAL SPECIFICATION SAFETY LIMIT .37 21 DRY FUEL STORAGE .................................. 38 EP-AD-000-200, Revision 21, Page 4 of 38
-: Tab4 EP-PS-127-4 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 2000 F as indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 1.4 None.
EP-AD-000-200, Revision 21, Page 5 of 38
Tab4 EP-PS-127-4 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 21, Page 6 of 38
Tab4 EP-PS-127-4 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 gCVcc of 1-131 equivalent.
ALERT EAL# 3.2 Severe fuel cladding degradation as indicated by:
(A orB orC orD)
A. Valid Off-gas Pre-treatment monitor High-High radiation annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).
or B. Valid Reactor coolant activity greater than' 300 pCVcc of equivalent 1-131, as determined by sample analysis.
or C. Valid Main Steam Line High-High radiation 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 21, Page 7 of 38
-: Tab4 EP-PS-1 27-4 3 - FUEL CLADDING DEGRADATION (continued)
SITE AREA EMERGENCY EAL# 3.3 Severely degraded core as indicated by:
(A orB)
A. Reactor coolant activity greater than 1,000 i/CVcc of equivalent 1-131 as determined by sample analysis.
or B. Valid containment post accident monitor indication on Panel 1 C601 (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 21, Page 8 of 38
Tab4 EP-PS-127-4 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 and2)
- 1. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 400 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)
and
- 2. (a orb orc)
- 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 and2)
- 1. Reactor coolant activity, greater than 1,000 jiCi/cc of equivalent 1-131 as determined by samp!e 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 21, Page 9 of 38
Tab4 EP-PS-1 27-4 4-GENERAL UNUSUAL EVENT EAL# 4.1 Plant conditions exist that warrant increased awareness on the part of plant operating staff or state and/or local offsite authorities as indicated by:
Events that are occurring or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
ALERT EAL# 4.2 Other plant conditions exist that warrant precautionary activation of PPL, State, County, and local emergency centers as indicated by:
Events that are occurring or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. .Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
SITE AREA EMERGENCY EAL# 4.3 Other plant conditions exist that warrant activation, of emergency centers and monitoring teams or a precautionary notification to the public near the site as indicated by:
Events that are occurring or have occurred which involve actual or. imminent major failures of plant functions needed for .protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except inside the emergency planning boundary.
GENERAL EMERGENCY EAL# 4.4 Other plant conditions exist, from whatever, source, that make release of large amounts of radioactivity in a short time period available as indicated by:
Events that are occurring or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Expectation is that releases will exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary.
EP-AD-000-200, Revision 21, Page 10 of 38
Tab 4 EP-PS-1 27-4 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 21, Page 11 of 38
Tab 4 EP-PS-127-4 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 Cs CC CN DACA DAC. DACC DACN ALERT EAL# 6.2 Unexpected in-plant high radiation levels or airborne contamination which indicates a severe degradation in the control of radioactive material as indicated by:
Area Radiation Monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2G600).
SITE AREA EMERGENCY EAL# 6.3 None.
GENERAL EMERGENCY EAL# 6.4 None.
EP-AD-000-200, Revision 21, Page 12 of 38
Tab 4 EP-PS-1 27-4 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 orB)
A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.
or B. Failure.of all diesel generators to start or. synchronize to the emergency buses by
'indication or annunciation on Panel OC653.
ALERT EAL# 7.2 Loss of all offsite power and all onsite AC power supplies as indicated by:
(A and B)
A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.
and B. Failure of all diesel generators to start or synchronize to the emergency buses by annunciation or indication on Panel 00653.
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 a2l diesel generators to startup or synchronize to the emergency buses by indication or annunciation on OC653.
and C. The above conditions exist for greater than 15 minutes.
GENERAL EMERGENCY EAL# 7.4 None.
EP-AD-000-200, Revision 21, Page 13 of 38
Tab4 EP-PS-1 27-4 8 - LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS UNUSUAL EVENT EAL# 8.1 None.
ALERT EAL# 8.2 Loss of all control room annunciators as indicated by:
In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer are lost, or insufficient annunciators are available to safely operate the unit(s) without supplemental observation of plant systems.
SITE AREA EMERGENCY EAL# 8.3 All annunciators lost and plant transient initiated while annunciators are lost as indicated by:
(A and B)
A. In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer. are lost; or insufficient annunciators are available to safely operate the unit(s) without supplemental observation of plant systems.
and B. (1 or2or3or4)
- 1. Low-Low reactor water level indication on Panel 1C651 _2CQ651) followed by ECCS initiation on Panel 1C601 (2C601).
or
- 2. Reactor coolant temperature change greater than 1000 F per hour indication on recorder TR-1 R006 on Panel 1C007 (2C007) (Reactor Building elevation 683').
or
- 3. High reactor pressure indication on Panel 1C651 (2C651) and followed by scram indication on Panel 1C651 (2C651).
or
- 4. Any indication that transient has occurred or is in progress.
GENERAL EMERGENCY EAL# 8.4 None.
EP-AD-000-200, Revision 21, Page 14 of 38
- - Tab 4 EP-PS-127-4 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), 1D632 (2D632), and 1D642 (2D642) as indicated by trouble alarms on Panel 1C651 (2C651).
NOTE: Buses are not tripped on undervoltage condition.
SITE AREA EMERGENCY EAL# 9.3 Loss of all vital onsite DC 'power sustained .for greater than 15 minutes as indicated by:
(A and B and C)
A. Less than 210 volts on the 250 VDC main distribution Panel buses, 1 D652 (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 21, Page 15 of 38
Tab4 EP-PS-127-4
.~~~~~~~~ . .
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 2000 F and rising..
and C. Suppression Pool temperature greater than 1201F 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 2001F and rising.
and C. Suppression pool temperature greater than 2900 F indicated on the computer output (MAT 12,13,14,15 or 16).
EP-AD-000-200, Revision 21, Page 16 of 38
-: Tab 4 EP-PS-1 27-4 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 andD 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 Tndications.
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 21, Page 17 of 38
Tab 4 EP-PS-127-4 11 - LOSS OF REACTIVITY CONTROL (continued)
SITE AREA EMERGENCY EAL# 11.3 Loss of functions needed to bring the reactor subcritical and loss of ability to bring the reactor to cold shutdown as indicated by:
(A and B and C and D)
A. Inability to insert sufficient control rods to bring the reactor subcritical as indicated by count rate on the neutron monitoring instrumentation on Panel 1C651 (2C651).
and B. (1 or2)
Failure of both loops of standby liquid control to inject into the vessel indicated by:
- 1. Low pump discharge pressure indication on Panel 1C601 (2C601).
or
- 2. Low flow indication on Panel 1C601 (2C601).
and C. Reactor coolant temperature greater than 2000F, indicated on Panel 1C651 (2C651).
and D. Reactor power >5% indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 11.4 Loss of functions needed to bring the reactor subcritical and transient in progress that makes release of large amounts of radioactivity in a short period possible as indicated by:
(A or B) and (0 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 10 651 (20651).
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 21, Page 18 of 38
-: Tab4 EP-PS-1 27-4 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 or B)
A. Drywell floor drain sump A or B Hi-Hi alarm on Panel 1C601 (2C601) and 2 or more drywell floor drain pumps continuously running as indicated on Panel 1C601 (2C601).
or B. Other estimates of Reactor coolant system leakage indicating greater than 50 gpm.
SITE AREA EMERGENCY EAL# 12.3 Known loss of coolant accident greater than make-up capacity as indicated by:
Water level below (and failure to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 21, Page 19 of 38
Tab 4 EP-PS-1 27-4 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 and2 and3)
- 1. High drywell pressure annunciation or indication on Panel 1C601 (2C601).
and
- 2. (a orb or c)
- a. Containment pressure exceeds 40.4 PSIG as indicated on Panel 1C601 (2C601).
or
- b. A visual inspection of the conrtainment 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 and2)
- 1. Failure of reactor pressure vessel isolation valves to isolate coolant break outside containment as indicated by valve positiod 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 21, Page 20 of 38
Tab4 EP-PS-1 27-4 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:
(AorBorC)
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 21, Page 21 of 38
Tab 4 EP-PS-1 27-4 13 - NATURAL PHENOMENA (continued)
SITE AREA EMERGENCY EAL# 13.3 Severe natural phenomenon occurrence, with plant not in cold shutdown, as indicated by:
(A and B)
A. Reactor Coolant Temperature greater than 200OF as indicated on Panel 1C651 (2C651).
and B. (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 OC696.
or
- 3. Tornado with reported wind velocities greater than 220 mph impacting on site.*
GENERAL EMERGENCY EAL# 13.4 None.
- Telephone numbers for the National Weather Bureau are located in the Emergency.
Telephone Directory.
EP-AD-000-200, Revision 21, Page 22 of 38
-: Tab4 EP-PS-1 27-4 14- ONSITE FIRE/EXPLOSION UNUSUAL EVENT EAL# 14.1 Significant fire within the plant as indicated by:
(A and B)
A. Activation of fire brigade by Shift Supervisor.
and B. Duration of fire longer than 15 minutes after time of notification.
OR Explosion inside security protected area, with no significant damage to station facilities, as indicated by:
Visual observation or notification received by control room operator and Shift Supervisor evaluation.
ALERT EAL# 14.2 On-site Fire/Explosion as indicated by:
(A or B)
A. Fire lasting more than. 15 minutes and fire is in the vicinity of equipment required for safe shutdown of the plant and the fire is damaging or is threatening to damage the equipment due to heat, smoke, flame, or other hazard.
or B. (1 and2)
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 21, Page 23 of 38
Tab4 EP-PS-1 27-4
~~~.
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 2001F as indicated on Panel 1C651 (2C651). -
GENERAL EMERGENCY EAL# 14.4 None.
EP-AD-000-200, Revision 21, Page 24 of 38
-: Tab 4 EP-PS-1 27-4 15- RADIOLOGICAL EFFLUENT UNUSUAL EVENT EAL# 15.1 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 2 times the Technical Requirements Manual limits for 60 minutes or longer.
EAL# 15.1 (1 br 2 or 3)
- 1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2.OE+6 liCVmin and that is sustained for 60 minutes or longer.
- 2. Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary with a release duration of 60 minutes or longer resulting in dose rates of:
a) Noble gases >1000 mrem/year whole body, or b) Noble gases >6000 mrem/year skin, or c) 1-131, 1-133, H-3, and particulates with half lives >8 days >3000 mrem/year to any organ (inhalation pathways only).
- 3. Confirmed sample analyses for liquid releases indicates concentrations with a release duration of 60 minutes or longer in excess of two time the-Technical Requirements Manual liquid effluent limits.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 21, Page 25 of 38
Tab4 EP-PS-1 27-4 15 - RADIOLOGICAL EFFLUENT (continued)
ALERT EAL# 15.2 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 200 times Technical Requirement Manual limits for 15 minutes or longer.
EAL# 15.2 (1 'or 2 or 3)
- 1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2E+8 giCimin and that is sustained for 15 minutes or longer.
OR 2 Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary for 15 minutes or longer resulting in dose rates of:
a) Noble gases >1.OE+S mremlyear whole body, or b) Noble gases >6.OE+5 mrem/year skin, or c) 1-131,1-133, H-3, and particulates with half-lives >8 days >3.OE+5 mrem/year to any organ (inhalation pathways only).
- 3. Confirmed sample analyses for liquid releases indicates concentrations in excess of 200 times the Technical Requirements Manual liquid effluent limits-o :15 minutes or longer.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 21, Page 26 of 38
-. Tab 4 EP-PS-1 27-4 15 - RADIOLOGICAL EFFLUENT (continued)
SITE AREA EMERGENCY EAL# 15.3 Dose at the Emergency Plan boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mrem whole body TEDE or 500 mrem child thyroid CDE for the actual or projected duration of release.
EAL# 15.3 (1 or 2 or 3 or 4 or.5)
- 1. Valid Noble Gas vent stack monitor readings(s) that exceeds a total release rate 6.2E8 ,VCVmin for greater than 15 minutes and Dose Projections are not available.
Note: If the required dose projection cannot be completed within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).
- 2. Valid dose assessment using actual meteorology indicates projected doses greater than 100 mrem whole body TEDE or 500 mrem child thyroid CDE at or beyond the EPB.
- 3. A valid reading sustained for 15 minutes or longer on the RMS-perimeter radiation monitoring system greater than 100 mR/hr.
- 4. Field survey results indicate Emergency Planning boundary dose rates exceeding 100 mR/hr expected to continue for more than one hour.
- 5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 500 mrem for one hour of inhalation.
(CONTiNUED ON NEXT PAGE)
EP-AD-000-200, Revision 21, Page 27 of 38
Tab 4 EP-PS-127-4
. .- I . ......
15 - RADIOLOGICAL EFFLUENT (continued)
GENERAL EMERGENCY EAL# 15.4 Dose at the Emergency Planning Boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE for the actual or projected duration of the release using actual meteorology.
EAL# 15.4 (1 or 2 or 3 or 4 or 5)
- 1. Valid Noble Gas vent stack monitor readings(s) that exceed a total release rate of 6.2E9 piCimin for greater that 15 minutes and Dose Projections are not available.
Note: If the required dose projection cannot be completed within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).
- 2. Valid dose assessment using actual meteorology indicates projected doses greater than 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE at or beyond the EPB.
- 3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 1000 mR/hr.
- 4. Field survey results indicate Emergency Planning Boundary dose rates exceeding 1000 mR/hr expected to continue for more than one hour.
- 5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 5000 mrem for one hour of inhalation.
EP-AD-000-200, Revision 21, Page 28 of 38
- Tab4 EP-PS-1 27-4 16 - SECURITY EVENT UNUSUAL EVENT EAL# 16.1 Security threat or attempted entry or attempted sabotage as indicated by:
(A orB orC)
A. A report from Security of a security threat, attempted entry, or attempted sabotage of the owner controlled area adjacent to the site.
or B. Any attempted act of sabotage which is deemed legitimate-in the judgment of the SHIFT SUPERVISOR/EMERGENCY DIRECTOR, and affects plant operation.
or C. A site specific credible security threat notification.
ALERT EAL# 16.2 Ongoing Security Compromise as indicated by:
(A or B)
A. A report from Security that a security compromise is at the site but no penetration of protected areas has occurred.
or B. Any act of sabotage which results in an actual or potential substantial degradation of the level of safety of the plant as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.
SITE AREA EMERGENCY EAL# 16.3 An ongoing adversary event threatens imminent loss of physical control of plant as indicated by:
(A orB)
A. Report frorri 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 21, Page 29 of 38
-: Tab 4 EP-PS-1 27-4 16 - SECURITY EVENT (continued)
GENERAL EMERGENCY EAL# 16.4 Loss of physical control of facilities as indicated by:
(A or B)
A. Report from Security that a loss of physical control of plant vital areas has occurred.
or B. Any act of sabotage which results in imminent significant cladding failure or fuel melting.with a potential for loss of containment integrity or the'potential for release of significant amounts of radioactivity in a short time as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.
EP-AD-000-200, Revision 21, Page 30 of 38
Tab 4
- . EP-PS-127-4 17 - SPENT FUEL RELATED INCIDENT UNUSUAL EVENT EAL# 17.1 Unanticipated or unplanned concentrations of airborne activity exist in normally accessible areas, which is not due to planned maintenance activities, as indicated by:
Concentrations exceed 500 times the DAC values of 10CFR20 Appendix B, Table I values for a single isotope, or full multiple isotopes where CA + C 8 + CC ... CN> >A 0 DA CA DA C. DA Cc DA CN 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 21, Page 31 of 38
Tab4 EP-PS-127-4 17 - SPENT FUEL RELATED INCIDENT (continued)
SITE AREA EMERGENCY EAL# 17.3.a Major damage to irradiated fuel with actual or clear potential for significant release of radioactive material to the environment as indicated by:
(A and B)
A. Dropping, bumping, or otherwise rough handling of a new OR irradiated fuel bundle with irradiated fuel in the pool.
and B. (1 or2)
- 1. Refueling floor area radiation monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).
or
- 2. Reactor Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.
OR EAL# 17.3.b Damage to irradiated fuel due to uncontrolled decrease in the fuel pool level to below the level of the fuel as indicated by:
(A and B)
A. (1 or2)
- 1. Uncovering of irradiated fuel confirmation by verification of significant leakage from spent fuel pool.
or
- 2. Visual observation of water level below irradiated fuel in the pool.
and B. (1 or2)
- 1. Refueling floor area radiation monitor annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).
or
- 2. Reactor .Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.
GENERAL EMERGENCY EAL# 17.4 None.
EP-AD-000-200, Revision 21, Page 32 of 38
Tab4 EP-PS-127-4 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 21, Page 33 of 38
Tab4 EP-PS-127-4 18 - STEAM LINE BREAK (continued)
SITE AREA EMERGENCY EAL# 18.3 Steam line break occurs outside of containment without isolation as indicated by:
(A orB orC orD)
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 and2)
- 1. Failure of RCIC steam isolation valves HV-F008 and HV-F007 to close as indicated on Panel 1C601 (2C601).
and
- 2. (a orb orc ord ore orf).
- a. RCIC steamline pipe routing-area high temperature annunciation on Panel 1C601 (2C601), or indication on Panel 10614 (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 21, Page 34 of 38
Tab4 EP-PS-1 27-4 18 - STEAM LINE BREAK (continued)
SITE AREA EMERGENCY (continued) or
- 0. (1 and2)
- 1. Failure of HPCI steam isolation valves HV-F002 and HV-F003 to close as indicated by position indicator on Panel 1C601 (2C601).
and
- 2. (a orb orc ord ore orf)
- a. HPCI steamline pipe routing area high temperature-annunciation on Panel 1C601 (2C601), or indication on Panel 1C614 (2C614).
or
- b. HPCI equipment area high temperature annunciation on Panel 110601 (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 21, Page 35 of 38
Tab 4 EP-PS-127-4 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 rec'eivediby. control room operator.
GENERAL EMERGENCY EAL# 19.4 None.
EP-AD-000-200, Revision 21, Page 36 of 38
Tab 4 EP-PS-127-4 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 orB orC orD)
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.
I ALERT EAL# 20.2 None.
SITE AREA EMERGENCY EAL# 20.3 None.
GENERAL EMERGENCY EAL# 20.4 None.
EP-AD-000-200, Revision 21, Page 37 of 38
Tab 4 EP-PS-127-4 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 BI A. Radiological readings exceed 2 Rlhour 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 Rfhour 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 21, Page 38 of 38