ML20079B113
| ML20079B113 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/16/1994 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| References | |
| 1903.010, NUDOCS 9501050183 | |
| Download: ML20079B113 (131) | |
Text
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o ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE Arkansas Nuclear One Russellville, Arkansas Date: 941222 MEMORANDUM TO: 103 *Please return transmittal CC - NRC - WASHINGTON to Document Control, 3RD floor Admin Bldg
- FROM: DOCUMENT CONTROL Ref Key: 17670 1 1
SUBJECT:
PLANT MANUAL UPDATE: REVISION TO PROCEDURE j i
L PROCEDURE / FORM NUMBER: OP-1903.010 REV. # 32 TC # 0 PC # 0 i PROCEDURE / FORM TITLE: EAL CLASSIFICATION The following pages of the indicated procedure (s) contains items which involve personal privacy or proprietary material. PLEASE REMOVE THE INDICATED MATERIAL PRZOR TO DISTRIBUTION TO PUBLIC DOCUMENT ROOMS, ETC.
. PROCEDURE (S) PAGE(S)
SIGNATURE: DATE:
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ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE 60 of 75 PROC / WORK PLAN NO. REV.
TITLE: EMERGENCY ACTION LEVEL CLASSIFK:ATION
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FORM NO. REV.
FORM TITLE-1000.006A 42 PC-1 LIST OF AFFECTED PAGES
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE 61 of 75
'V TITLE: EMERGENCY ACTION LEVEL CLASSIFICATION PR NORK PLAN NO. REV.
1903.010 32 SAFETY-RELATED SYES ONO PAGE _2_,OF _,2, CONTINUATION PAGE PAGE CHG PAGE CHG PAGE CHG PAGE CHG 125 126 127 128 V
O FORM TITLE: FORM NO. REV.
LIST OF AFFECTED PAGES 1000.006A 42
l Pnocswonx Puw No. Psam-wonx Puw Tmz: PaoE: 1 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANoE.-
( ,) 1.0' PURPOSE !
This procedure establishes criteria for detection and classification of plant events into the four standard Emergency Classes.
2.0 SCOPE
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This procedure is applicable to Units 1 and 2 in all modes; it does not include specific plant casualty procedures or systems operations requirements, I but rather provides administrative processes only.
3.0 REFERENCES
3.1 REFERENCES
USED IN PROCEDURE PREPARATION:
3.1.1 ANO Emergency Plan ;
3.1.2 AP&L EAL Bases Document 3.1.3 NUREG-0654/ FEMA-REP-1, Rev. I t 3.1.4 10 CFR 50 -
3.2 REFERENCES
USED IN CONJUNCTION WITH THIS PROCEDURE:
3.2.1 1000.104, " Condition Reporting and Corrective Actions" 3.2.2 1903.011, " Emergency Response / Notifications" '
3.2.3 1903.064, " Emergency Response Facility - Control Room" 3.2.4 1903.065, " Emergency Response Facility - Technical j Support Center (TSC)"
3.2.5 1903.066, " Emergency Response Facility - Operational l Support Center (OSC)"
3.2.6 1903.067, " Emergency Response Facility - Emergency Operations Facility (EOF)" !
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3.2.7 1203.025, " Natural Emergencies" ]
3.2.8 2203.008, " Natural Emergencies" i 3.2.9 1202.XXX, " Emergency Operating Procedures" 3.2.10 2202.XXX, " Emergency Operating Procedures" 3.2.11 1404.016, " Post Earthquake Data acquisition and ,
l Measurement" 3.2.12 2304.058, " Peak Shock Recorder Surveillance" 3.2.13 1904.002, "Offsite Dose Projections-RDACS Method" l 3.2.14 1904.004, " Estimating Airborne Release Rates" l
3.3 RELATED ANO PROCEDURES:
3.3.1 1043.006, " Bomb Threat" 3.3.2 1502.004, Attachment H
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN Tm.E: PAGE: 2 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSlFICATION REV: 32 CHANGE:
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3.3.3 1903.023, " Personnel Emergency" 3.3.4 .ANO Security Plan / Security Procedures 3.3.5 1015.007, " Fire Brigade Organization and Responsibilities" 3.3.6 1903.042, " Duties of'the Emergency Medical Team" 3.3.7 1903.043, " Duties of the Emergency Radiation Team" 3.4 REGULATORY CORRESPONDENCE CONTAINING NRC COMMITMENTS WHICH ARE IMPLEMENTED IN THIS PROCEDURE INCLUDE:
3.4.1 OCAN068708 3.4.20 OCNA068807 A. Section 4.17 B. Attachment 3 C. Attachment 4 3.4.30 OCAN068320 A. Section 4.15 3.4.40 OCAN108213 A. 3.2.2 D B. 4.11 C. 6.1.4 3.4.51 0CAN088308 A. 5.0 B. 6.1 l
4.0 DEFINITIONS 4.1 Courtesy Call - A notification to the Arkansas Department of Health and follow-up notification to the NRC for conditions / events other than those constituting an Emergency Class as listed in procedure 1903.11,
" Emergency Response / Notifications", Section 6.3.
4.2 Emergency Action Level - Alarms, instrument readings or visual sightings at have exceeded pre-determined limits which would categorize the situation into an initiating condition of one of the following four Emergency Classes:
Notification of Unusual Event Alert Site Area Emergency General Emergency 4.3 Notification of Unusual Event - Unusual events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite
,O. response or monitoring are expected unless further degradation of V safety systems occurs.
4.4 Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of l
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Pnoc>wonK PLAN NO. PacCEDURFJWORK PLAN Tm.E: PAGE: 3 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE:
O the plant. Any mileases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
4.5 Site Area Emergency - Events are in progress or have occurred which involve actual or likely 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 near the site boundary.
4.6 General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off site for more than the immediate site area.
4.7 Emergency Planning Zone (EPZ) - The EPZ considered by this procedure is the inhalation zone and is that area within approximately a 10 mile radius of ANO.
4.8 Onsite - The area within the Exclusion Area Boundary.
4.9 Offsite - Those areas-not covered by Section 4.8.
4.10 Initial Response Staff (IRS) - The emergency organization composed of plant personnel which must be able to respond to the site in accordance with Table B-1 of the Emergency Plan.
4.11 Emergency Response Organization (ERO) - The organization which is O composed of the Initial Response Staff (IRS), the EOF staff, the TSC staff, the OSC staff, and the Emergency Team members. It has the capability to provide manpower and other resources necessary for immediate and long-term response to an emergency situation.
4.12 Technical Support Center (TSC) - The location within the ANO Administration Building equipped with instrumentation and communication systems and facilities useful in monitoring the course of an accident; this center is located in the 3rd Floor of the ANO Administration Building.
4.13 Operational Support Center (OSC) - Emergency response center within the ANO Maintenance Facility where support is coordinated for the following functions:
Onsite Radiological Monitoring Maintenance Nuclear Chemistry Emergency Medical Support Fire Fighting Support The OSC also serves as the briefing area for repair and damage control teams and is located in the Maintenance Facility.
4.14 Emergency Operations Facility (EOF) - A nearsite emergency response facility located approximately 0.65 miles northeast of the reactor buildings (the ANO Training Center).
4.15 Emergency Direction and Control - Overall direction of facility h
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response which must include the non-delegable responsibilities for the decision to notify and to recommend protective actions to Arkansas Department of Health personnel and other authorities responsible for offsite emergency measures. With activation of the EOF, the EOF
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PROCMORK PUW NO. WWWORK PUW TmJD PAGE: 4Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE.- ;
Director typically assumes the responsibility for Emergency Direction and Control. The management of on-site facility activities to mitigate accident consequences remains with the TSC Director in the Technical Support Center. The Shift Superintendent retains responsibility for the Control Room and plant systems operation.
4.16 FISSION PRODUCT BARRIER FAILURE 4.16.1 Fuel Cladding Failure A. Unit 1 - Greater than 1% failed fuel as indicated by ANY of the following:
- 1. Nuclear Chemistry analysis of RCS sample yields >
400 uci/gm specific I-131.
- 2. Failed Fuel Iodine process monitor (RE 1237) ;
indicates > 8.2 x 10' CPM.
- 3. Containment Radiation Levels correspond to a Site Area Emergency from Containment' Radiation EAL Plot (Attachment 5) .
l 4. Engineering assessment of core damage indicates
> 1% failed fuel. '
B. Unit 2 - Greater than 1% failed fuel as indicated by ,
fs ANY of the following:
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- 1. Nuclear Chemistry analysis of RCS sample yields > '
378 uCi/gm specific I-131.
- 2. Containment Radiation Levels correspond to a Site Area Emergency from Containment Radiation EAL Plot (Attachment 6).
- 3. Engineering assessment of core damage indicates I > 1% failed fuel.
4.16.2 RCS Boundary Failure i
A. Unit 1 - RCS leakage greater than normal makeup l capacity (50 gpm).
B. Unit 2 - RCS leakage greater than 44 gpm (capacity of a single Charging Pump). I 4.16.3 Containment Integrity Failure '
t A. Abnormally high Containment High Range Radiation '
Monitor readings (RE-8060 or 8061 for Unit 1; 2RY- ,
8925-1 or 2RY-8925-2 for Unit 2) and indications of '
radiological effluents outside of the Reactor Building that are not attributable to any other source.
B. In the judgement of the SS/TSC Director / EOF Director,
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a breach of the Reactor Building exists. The variety of possible Reactor Building integrity failure scenarios precludes the development of an all inclusive list. In the absence of the conditions
PnocAsoRK Puud NO. AmMr4 WORK M.AN TmE: PAGE: 5 of128 I 1903.010 EMERGENC1r ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
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( ,) described in 4.16.3.A above, the SS/TSC Director / EOF Director must judge the potential for an offsite release to occur based on a current status of Reactor Building isolation systems and structural integrity.
4.16.4 Inability to monitor a Fission Product Barrier.
A. Following the failure of two fission product barriers, I the inability to monitor the third barrier is to be regarded as equivalent to a failure of that barrier.
4.17 FISSION PRODUCT BARRIER CHALLENGE 4.17.1 Challenge to Fuel Cladding: any event or condition which in the judgement of the SS/TSC Director / EOF Director presents the potential for greater than 1% fuel cladding failure; for examples i A. RCS temperature and pressure indicates superheated conditions. i B. Indications of the core being uncovered.
C. Exceeding safety limits (e.g. DNBR or Local Power Distribution) 4.17.2 Challenge to RCS Boundary: any event or condition which, in the judgement of the SS/TSC Director / EOF Director could result in RCS leakage in excess of normal makeup capacity
(>50 gpm) for Unit 1 or greater than 44 gpm for Unit 2; for example:
A. RCS pressure > 2450 psig and not decreasing.
B. Two out of three seals failed on any RCP (U-1).
C. Three out of four seals failed on any RCP (U-2).
D. Failure of any component resulting in RCS leakage greater than Tech. Spec. lindts but less than normal make up capacity (50 gpm) for Unit 1 or less than 44 gpm for Unit 2.
4.17.3 Challenge to Reactor Building Integrity: any event or condition which in the judgement of the SS/TSC Director /
3 EOF Director significantly increases the potential for '
failure of containment integrity; for examples A. Containment pressure > Reactor Building spray actuation setpoint and increasing with no available RB l
spray or cooling. i B. Hydrogen concentrations in containment > 3.5%.
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PROC.MORK PLAN No. PROCEDUREMORK PLAN TITLE: PAGE: $ Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
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C. occurrence of system or component failure which degrades the capability to maintain containment integrity as defined by Tech Specs.
4.18 PLANT TRANSIENT 4.18.1 Any unplanned reactor trip from criticality.
4.18.2 A planned reactor trip in which the expected post-trip response did not occur.
4.18.3 Any event resulting in an automatic ESAS (Unit 1) or ESF (Unit 2) actuation or any event requiring manual initiation of these systems where automatic initiation would likely have occurred.
4.18.4 Any turbine-generator power change in excess of 100 MWe in less than one (1) minute other than a momentary spike due to a grid disturbance or a manually initiated runback.
4.18.5 Any unplanned main turbine or main feedwater pump turbine trip which results in a significant plant transient (change in excess of 100 MWe).
5.0 RESPONSIBILITY AND AUTHORITY O 5.1 The responsibility for event classification is assigned to the individual with responsibility for Emergency Direction and Control (i.e., The Shift Superintendent, TSC Director, or EOF Director) .
5.2 The Control Room Supervisor (CRS) will assume Emergency Direction and Control responsibilities whenever the SS is not available to assume this responsibility (e.g. the SS becomes incapacitated and a replacement has not yet arrived).
5.3 Any individual who observes an initiating condition which warrants an emergency class declaration, as described in Attachments 3 and 4, shall immediately notify the person with current responsibility for i Emergency Direction and Control (i.e. SS/TSC Director / EOF Director) . '
6.0 IIISTRUCTIONS NOTE l On emergencies that effect both units such as earthquakes, tornado's, etc., the unit with the highest Emergency Action Level Classification should be the one that is declaring the emergency.
6.1 CLASSIFYING EMERGENCIES:
6.1.1 When indications of abnormal occurrences are received by the Control Room staff, the SS/TSC Director / EOF Director shall:
A. Verify the indications of the off-normal event or reported sighting.
p=ae amamar PLAN NO. ' PROCEDUREMOAK PLAN Tm2 PAGE: 7Of128 '
1903.019 EMERGENCY ACTION LEVEL CLASSIFICATION nEv: . ' 32 i
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,, B. Ensure that the immediate' actions (e.g., use of
, Emergency and Abnormal _ Operating Procedures) are taken ;
for the safe and proper operation of the plant. ;
-i C. Compare the abnormal conditions with those listed in i the "Index of Emergency Action Levels" (Blue Tabs - ,
Unit la Green Tabs - Unit 2).
D. Turn to the appropriate tab which corresponds to the ;
condition picked from the Index of EALs. -
NOTE' Unit 1 EALs - Blue Tabs Unit 2 EALs - Green Tabs: ;
E. Assess the information available fram valid indica-tions or reports, then
- 1. Compare information to criteria given for EAL, '
- 2. Review any Related EALs to determine if the abnormal conditions meet those criteria, and
- 3. Declare the emergency classification that is :
indicated. (IF it appears that different !
classifications could be made for the current )
plant conditions, the highest. classification
( indicated should be the one that is declared.
HOTE The emergency action levels described in this procedure !
are not intended to be used during maintenance and/or testing situations where abnormal temperature, !
pressure, equipment status, etc., is expected. - In j addition, each EAL contains information on the mode (s) ;
of operation during which it is applicable.
F. If the indications or reports do not match the given i EALs, then refer to the Miscellaneous Tab and using ,
appropriate judgement, determine if the plant status ,
warrants an emergency declaration. l t
6.1.2 _Due to the speed'in which events sometimes progress and the j duty of the plant operators to take immediate corrective !
actions, an event may occur which was classifiable as an emergency, however, prior to offsite notifications the' corrective actions taken may have removed the conditions ;
that would have resulted in an emergency declaration. In this situation, offsite authorities (i.e. ADH and NRC) must be notified of the most severe emergency class that ,
occurred (prior to the time when notifications- could be ' i made) with a brief description of events and the current I plant status provided via form 1903.0112. Subsequent j activation of response organizations should be based upon ;
the current plant conditions. l N
6.1.3 If no emergency declaration is apparently necessary, then refer to procedure 1903.011, " Emergency i Response / Notifications", Section 6.3 to determine if a w --, .--w,----,-,,--m. g ppvrm--
PROCMORK PLAN NO. P"'m **JHK PLAN TITLE: PAGE: 8Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 i CHANGE
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,,) ' Courtesy Call to the Arkansas Department of Health is required.
6.1.4 Upon declaration of an emergency classification implement f procedure,- 1903.011, " Emergency Response Notifications", to i ensure that immediate notification requirements are met and :
the proper Emergency Plan response is taken. !
I 6.1.5 Upgrade the emergency classification if plant conditions ;
degrade per steps 6.1.1.A through F. l 6.1.6 Downgrade the emergency classification when plant !
conditions have improved and step 6.2 is applicable.
l 6.2 DOWNGRADING THE EMERGENCY CLASSIFICATION:
6.2.1 Assess the current plant conditions, then perform the ;
following: !
I A. Compare the abnormal conditions with those listed in l the "Index of Emergency Action Levels" (Blue Tabs - }
Unit 1; Green Tabs - Unit 2)
B. Turn to the appropriate tab which corresponds to the !
condition picked from the Index Of EALs.
i (D Unit 1 EALs - Blue Tabs Unit 2 EALs - Green Tabs I
- c. Assess the information available from valid {
indications or reports, compare it to the given EALs. i Obtain concurrence from NRC and State officials that I downgrading is appropriate (if their emergency ;
response organizations have been activated as a result !
of this event). Downgrade to.the emergency classification that is indicated.
D. If the indications or reports do not match the given '
EALs, then refer to the Miscellaneous Tab and using appropriate judgement, determine if the plant status l warrants downgrading the emergency classification. l t
6.2.2 Perform notifications to downgrade the emergency i classification if appropriate per procedure 1903.011, ,
" Emergency, Response / Notifications".
6.2.3 If no emergency classification appears necessary, then :
terminate the emergency per step 6.3. ;
6.2.4 If the emergency classification is still required, repeat steps 6.2.1 through 6.2.3 whenever plant conditions again '
appear to have improved.
A 6.3 TERMINATING THE EMERGENCY:
l 6.3.1 Compare the existing plant conditions with the following:
i Pftoc) WORK PUW NO. Pft0CEDuftIUWOftK PUW TITLE: PAGE: 9Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION ItEV: 32 ,
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A. Plant conditions no longer meet the emergency action
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level criteria. AND It appears unlikely that current conditions will degrade further requiring reinstitution of an emergency classification. *
- 8. Non-routine releases of radioactive material to the environment are under control or terminated. '
- c. Any fire, flood, earthquake, or similar emergency condition is controlled or has ceased.
D. All specified corrective actions have occurred. OR h The plant has been placed in the appropriate ;
operational mode. '
E. All required notifications have been completed.
t F. NRC and State officials are in agreement that termination or transition to the recovery phase is appropriate (if their emergency response organizations ,
have been activated as a result of this event). '
6.3.2 If the conditions of 6.3.1 A-F are met, terminate the emergency or proceed to the recovery phase.
7.O ATTACHMENTS AND FORMS 7.1 Attachment 1 - Unit 1 Index of EALs 7.2 Attachment 2 - Unit 2 Index of EALs ;
7.3 Attachment 3 - Unit 1 Emetgency Action Levels !
7.4 Attachment 4 - Unit 2 Emergency Action Levels "
7.5 Attachment 5 - Unit 1 Containment Radiation EAL Plot !
7.6 Attachment 6 - Unit 2 Containment Radiation EAL Plot '
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-A PROCJWORK PUW NO. MtOCEDURE/ WORK PUW TrTLE: PAGE: 10 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REY: 32 CHANDE:
y) ATTACHMENT 1 UNIT 1 INDEX OF EALS 1.0 PRIMARY SYSTEM EVENTS 1.1 Actuation of ECCS Components Resulting in Flow to the Core...........NUE 1.2 RCS Activity Indicates >0.1% Failed Fuel.............................NUE 1.3 RCS Activity Indicates > 1% Failed Fuel.............................. ALERT 1.4 Core Damage Indicated with an Inadequate Core Cooling Condition......SAE 1.5 Containment Radiation Reading which Indicates LOCA and >l% Cladding Fa i l u r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SAE 1.6 Containment Radiation Reading which Indicates LOCA and >50% Fuel Overheat.............................................................GE 1.7 Core Melt............................................................GE 1.8 Loss of or challenge to all 3 Fission Product Barrier................GE 2.0 RCS LEAXAGE l
2.1 RCS Leakage > T.S. Limits requiring a plant S/D or C/D...............NUE 2.2 RCS Leakage > Normal Makeup Capacity (50 gpm) . . . . . . . . . . . . . . . . . . . . . . . . ALERT 2.3 RCS Leakage > Normal Makeup Capacity (50 gpm) with >l.0% Failed Fuel Conditions......................................................SAE 2.4 RCS Leakage > HPI Capacity...........................................SAE 3.0 SECONDARY SYSTEM EVENTS
% 3.1 Uncontrolled OTSG Depressurization Resulting in MSLI Actuation.......NUE 3.2 OTSG Tube Leak >.347 gpm.............................................NUE 3.3 OTSG Tube Leak >10 gpm concurrent with on-going Steam Release........ ALERT 3.4 OTSG Tube Rupture with Primary to Secondary Leakage > Normal Makeup Capacity (50 gpm) with ongoing steam release..................SAE 3.5 OTSG Tube Leak >l gpm with >1% Failed Fuel and on-going Steam R e l e a s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S AE 4.0 ELECTRICAL POWER FAILURES 4.1 Degraded Power.......................................................NUE 4.2 Station Blackout..................................................... ALERT 4.3 Blackout for more than 15 minutes....................................SAE 4.4 Loss of All Vital DC Power........................................... ALERT 4.5 Loss of All Vital DC Power for more than 15 minutes..................SAE 5.0 RADIOLOGICAL EFFLUENTS 5.1 Radiological Ef fluents >.05 mRe n/hr TEDE or .15 mrem /hr Child Thyroid at Site Boundary or Liquid Radiological Effluents exceed Tech Spec Limits.................................................,,..NUE
.2 Radiological Effluents >.5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid Site Boundary or Liquid Radiological Effluents exceed 10 times Tech Spec limits .................................... ALERT -
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( ATTACHMENT 1 UNIT 1 INDEX OF EALS
'5.3 Radiological Effluents 150 mrem /hr TEDE or 150 mrem /hr Child Thyroid at the Site Boundary ..................................SAE 5.4 Radiological Effluents 1250 mrem /hr TEDE or 500 mrem /hr Child Thyroid at the Site Boundary ..................................GE 5.5 High Radiation / Airborne Levels ...................................... ALERT ,
5.6 Spent Fuel Accident .................................................SAE 6.0 SAFETY SYSTEM FUNCTION- '
6.1 Initiation of Plant S/D or C/D for Tech Spec LCO Compliance OR Deviation from T.S. L.C.O.'s (10CFR50.54X) .......................NUE 6.2 i@S Failure to Complete an Automatic Trip . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 6.3 RPS Failure to Complete a Manual Trip . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SAE 6.4 Los s of Dose Ass es sment Capabilitics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NUE 6.5 Loss of Communications ..............................................NUE 6.6 Loss of Control Room Annunciators ................................... ALERT 6.7 Loss of Control Room Annunciators with Transient in Progress ........SAE 6.8 Control Room Evacuation ............................................. ALERT 6.9 Control Room Evacuation and control of shutdown systems not established in 15 minutes ..................................... .....SAE 6.10 Los s of Decay Heat Removal Sys tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 6.11 Degraded Hot Shutdown Cr9 ability ....................................SAE 7.0" HAZARDS TO STATION OPERATION 7.1 Security Threat or Attempted Entry or Attempted Sabotage ............NUE 7.2 Ongoing security Threat within Protected Area Security Fence ........ ALERT 7.3 Ongoing Security Threat Within Plant Building .......................SAE 7.4 Ongoing Security Threat Within CR or Vital Arte . . . . . . . . . . . . . . . . . . . . . GE 7.5 Fire or Explosion Onsite ....................g.......................NUE 7.6 Fire or Explosion Onsite Affecting One Train of ANY ES Systems ...... ALERT 7.7 Fire or Explosion Onsite Affecting Both Trains of ANY ES Systems ....SAE 7.8 Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine Failure, Toxic or Flammable Gas Release . . . . . . . . . . . . . . . . . . . . . NUE 7.9 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ANY ES Systems ......................................... ALERT 7.10 Aircraf t Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains of ANY ES Systems........................................ SAE 8.0 NATURAL EVENTS 8.1 Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake . . . . . . . . . . . . INE 1 8.2 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, '
Earthquake .......................................................... ALERT 8.3 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake ..........................................................SAE j 1
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l PROCJWCNtK PLAN NO. PROCEDURE / WORK PLAN TmE: PAGE: 12Of128 1903.010 E MERGENCY ACTION LEVEL CLASSIFICATION REV: 32 l
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l rsI v ATTACHMENT 1 .
UNIT 1 INDEX OF EALS 9.0 MISCELLANEOUS EVENTS- i 9.1 Transport of a Contaminated Injured Individual to an offsite Medical Facility ....................................................NUE 9.2 Plant Conditions Exist Which Require an Increased Awareness by Operations Staff and State and/or Local Authorities .................NUE 9.3 Plant Conditions Exist that Warrant Activation of the TSC ........... ALERT '
9.4 Plant Conditions Exist that Warrant Activation of the Emergency j
' Response Facilities .................................................SAE 9.5 Plant Conditions Exist That Make Release of Large Amount of Radioactivity Possible ..............................................GE r
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PROCJWORK PUUd NO. PROCEDURE / WORK Pt.AN TmE: PAGE: 13 of128
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1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: .
t y '
( ATTACHMENT 2 UNIT 2 INDEX OF EALS 1.0 PRIMARY SYSTEM EVENTS 1.1 Actuation of ECCS Components Resulting in Flow to the Core...........NUE 1.2 RC.; Activity Indicates >0.1% Failed Fuel. . . . . . . . . . . . . . . . . . . . . . . . . . . . .NUE 1.3 RCS Activity Indicates >1.0% Failed Fuel............................. ALERT 1.4 Core Damage Indicated with an Inadequate Core Cooling Condition......SAE l.5 Containment Radiation Indicates LOCA and >1% Cladding Failure........SAE 1.6 Containment Radiation Indicates LOCA and >50% Fuel Overheat..........GE 1.7 Core Melt with Containment Integrity Lost or Challenged..............GE 1.8 Loss of or challenge to all 3 Fission Product Barriers...............GE 2.0 RCS LEAKAGE 2.1 RCS Leakage > T.S. Limits requiring a plant S/D or C/D...............NUE 2.2 RCS Le a k a g e > 4 4 gpm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 2.3 RCS Leakage > 44 gpm with ICC Conditions.............................SAE 3.0 SECONDARY SYSTEM EVENTS 3.1 Uncontrolled S/G Depressurization Resulting in MSIS Actuation........NUE 3.2 S/G Tube Leak > Tech Spec Limits.....................................NUE A 3.3 S/G Tube Leak >10 gpm With an ongoing Steam Release.................. ALERT f S/G Tube Rupture >44 gpm With an Ongoing Steam Release and RCS W 3.4 4
Ac tivi t y > 1. 0 p Ci / gm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SAE 4.0 ELECTRICAL POWER FAILURES 4.1 Degraded Power.......................................................NUE 4.2 Station Blackout..................................................... ALERT 4.3 Loss of All Vital DC................................................. ALERT 4.4 Blackout > 15 minutes................................................SAE 4.5 Loss of All Vital DC for > 15 minutes................................SAE 5.0 RADIOLOGICAL EFFLUENTS 5.1 Radiological Effluents 2 05 mrem /hr TEDE or .15 Child Thyroid at Site Boundary or Liquid Radiological Effluents exceed Tech Spec.
Limits ..............................................................NUE 5.2 Radiological Effluents 3 5 mrem /hr TEDE or 1.5 mrem /nr Child Thyroid at Site Boundary or Liquid Radiological Effluents exceed 10 times Tech. Spec. Limits......................... ALERT 5.3 Radiological Effluents 250 mrem /hr TEDE or 150 mrem /hr Child Thyroid at the Site Boundary...................................SAE 5.4 Radiological Effluents 1250 mrem /hr TEDE or 500 mrem /hr Child Thyroid at the Site Boundary ..................................GE 5.5 High Radiation / Airborne Levels ...................................... ALERT 5.6 Spent Fuel Accident .................................................SAE N
PROCMORK PLAN NO. PROCEDURE / WORK PLAN Tm2: PAGE: 14Of128 1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE.-
.m ATTACHMENT 2 UNIT 2 INDEX OF EALS 6.0 SAFETY SYSTEM FUNCTION 6.1 Initiation of Plant S/D or C/D for Tech Spec LCO Compliance OR Deviation from T.S. L.C.O.'s (10CFR50.54X)...........................NUE 6.2 RPS Failure to Complete an Automatic Trip............................ ALERT 6.3 RPS Failure to Complete a Manual Trip................................SAE 6.4 Loss of Dose Assessment Capabilities.................................NUE 6.5 Lo s s o f Conununi ca ti ons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NUE 6.6 Control Room Evacuation.............................................. ALERT 6.7 Control Room Evacuation and control of shutdown systems not established in 15 minutes............................................SAE 6.8 Loss of Decay Heat Removal Systems................................... ALERT 6.9 Loss of Both S/Gs as a Heat Removal Method...........................SAE 6.10 Loss of Control Room Annunciators.................................... ALERT 1 6.11 Loss of Control Room Annunciators with a Transient in Progress.......SAE 7.0 HAZARDS TO STATION OPERATION 7.1 Security Threat or Attempted Entry or Attempted Sabotage.............NUE 7.2 Ongoing Security Threat Within Protected Area Security Fence......... ALERT 7.3 Ongoing Security Threat Within Plant Buildings.......................SAE 7.4 Ongoing Security Threat Within CR or Vital Area......................GE A 7.5 Fire or Explosion Onsite.............................................NUE
( 7.6 Fire or Explosion Onsite Affecting One Train of ESF Systems.......... ALERT 7.7 Fire or Explosion Onsite Affecting Both Trains of ESF Systems........SAE :
7.8 Aircraft Crash, Unusual Aircraft Activity, Train Derailment, ,
Turbine Failure, Toxic or Flammable Gas.............................NUE l 7.9 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One T r a i n o f ES F S ys t ems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 7.10 Aircraf t Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains of ESF Systems ..........................................SAE 8.0 NATURAL EVENTS 8.1 Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake.............NUE 8.2 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake........................................................... ALERT 8.3 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake...........................................................SAE 9.0 MISCELLANEOUS EVENTS 9.1 Transport of a Contaminated Injured Individual to an offsite Medical Facility ....................................................'NUE 9.2 Plant Conditions Exist Which Require an Increased Awareness by Operations Staff and State and/or Local Authorities..................NUE 9.3 Plant Conditions Exist that Warrant Activation of the TSC . . . . . . . . . . . ALERT 9.4 Plant Conditions Exist that Warrant Activation of the Emergency Response Facility ...................................................SAE
) 9.5 Plant Conditions Exist That Make Release of Large Amount of d Ra di o a c tivi t y Po s s ibl e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . GE
PROCAWORK PLAN NO. PROCEDUREAWORK PUW Tm.E: PAGE: 15 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 ;
CHANGE:
O ATTACHMENT 3 UNIT 1 ,
PRIMARY SYSTEM EVENTS 1.1 1 CONDITION:
Actuation of ECCS Components resulting in flow to the core EMERGENCY CLASSIFICATION: -
Notification of Unusual Event .
MODES Above CSD CRITERIA:
NOTE This EAL does not include manual actuation of HPI as a conservative action to maintain pressurizer level above 30" or RCS pressure above ,
1700 PSIG during a reactor trip transient.
- 1. Either of the following events occur:
A. HPI pump (s) running AND injecting BWST water into the RCS as indicated on the HPI Flow indicators on C16 or C18.
OR i
B. LPI pump (s) running AND injecting BWST water into the core as I indicated on the LPI flow indicators on C16 or C18. !
AND
- 2. Actuation is the result of ANY of the following: .
I A. A valid ES signal B. Inadvertent actuation ;
C. Manual actuation which preempts imminent automatic actuation of ECCS ,
l RELATED EALS: TAB j None l i
\ '
PROCJWORK PUW No. PROCEDUIWWORK PLAN TmE: PAGE: 16Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
s ,
ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.2 CONDITION
RCS Activity indicates >0.1% failed fuel EMERGENCY CIASSITICATION:
Notification c;f Unusual Event MODES All CRITERIA:
- 1. Greater than 0.1% failed fuel as indicated by EITHER of the following:
A. Nuclear Chemistry analysis of RCS sample yields >40.0 pCi/gm specific 1 131 OR B. Failed Fuel Iodine monitor (RE 237) indicates >3.3 x 10' CPM s
i RELATED EALS: TAB RCS Activity indicates >1% failed fuel 1 High Radiation / Airborne Levels 5 Initiation of Plant S/D or C/D due to T.S. L.C.O. 6 O ,
PROCANOfuC PLAN NO. PROCEDURE / WORK M.AN TmK: PAGE: 17Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
A ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.3 CONDITION
RCS Activity indicates >1% failed fuel EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Greater than 1% failed fuel is indicated by Either of the following:
A. Nuclear Chemistry analysis of RCS sample yields >400 pCi/gm specific I'
5 RELATED EALS: TAB RCS Activity indicates >0.1% failed fuel 1 Containment Radiation indicates LOCA and >1% clad failure 1 ;
Loss of or Challenge to 3 Fission Product Barriers 1 Core Damage indicated with an ICC condition i High Radiation / Airborne Levels 5 Initiation of Plant S/D or C/D due to T.S. L.C.O. 6
{
l l
l
PROCAWORK PLAN NO. PROCEDURIUWORK Pt.AN TmE: PAGE: 18 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
' C'T ,
j ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.4 CONDITION
Core Damage Indicated with an Inadequate Core Cooling Condition EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Inadequate core cooling capacity exists as evidenced by CETS indicating superheated conditions of Region 3 of Figure 4 of EOP 1202.013.
AND
- 2. Greater than 1% failed fuel is indicated by EITHER of the following:
A. Nuclear Chemistry analysis of RCS sample yields >400 pCi/gm specific I***
QR B. Failed Fuel Iodine process monitor (RE 1237) indicates >B.2 x 10' CPM.
RELATED EALS: TAB Containment Radiation High/Very High 1 Core Melt 1 Loss of or challenge to 3 Fission Product Barriers 1 RCS Leakage 2 O)
\_
i i
PROCAYORK PLAN NO. PROCEDUREMKNtK PUud TTTLE: PAGE: 19 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION stEv: 32 CHANGE:
(~h V ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.5 CONDITION
Containment Radiation reading which indicates LOCA and >1% cladding failure EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Containment Radiation Levels correspond to a Site Area Emergency as Determined from the Containment Radiation EAL Plot (Att 5)
RELATED EALS: TAB
, Containment Radiation indicates LOCA and > 50% fuel overheat 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1 Radiological Effluents 5
/
l
f I PROC.MORK PUW NO. PROCEDUREMORK PLAN TULE: PAGE: 20 of 128 1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: :
ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.6 CONDITION
Containment Radiation readings which indicate LOCA and >50% fuel overheat EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
- 1. Containment Radir'. ion Levels correspond to a General Emergency as determined ;
from the Containment Radiation EAL Plot (Att 5) j i
%./
RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1 i
?
O :
1
PROCJWORK PLAN NO. PROCEDURE /WOftK PUWd TITLE: PAGE: 21 Of 128 l 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
/\
/ ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS ,
t
- 1. */
CONDITION: ;
Core Melt j EMERGENCY CLASSITICATION:
General Emergency MODES All ,
CRITERIA:
O RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation High/Very High 1 Radiological Effluents 5
'N
4 PROCAWORK PUW NO. PROCEDURE / WORK PLAN TITLE: PAGE: 22 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CuaNoE: ;
y/ ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS 1.8 l CONDITION:
Loss of or challenge to all 3 Fission Product Barriers EMERGENCY CLASSIFICATION:
General Emergency MODES All l
CRITERIA:
- 1. Either of the following conditions exist:
A. Fuel Cladding Failure (refer to section 4.16.1)
% B. Challenge to Fuel Cladding (refer to section 4.17.1)
J AND
- 2. Either of the following conditions exist:
A. RCS boundary failure (refer to section 4.16.2)
B. Challenge to RCS boundary (refer to section 4.17.2)
AND
- 3. Either of the following conditions exists A. Containment Integrity failure (refer to section 4.16.3) i B. Challenge to Containment Integrity (refer to section 4.17.3) 1 RELATED EALS: TAB _
Containment Radiation High/Very High 1 Core Melt 1 Radiological Effluents 5 Natural Events B i
I
Pnoc>wasuc PLAN No. Mt0CEDUsupWORK PLAN TirLE: PAGE: 23 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION nev: 32 CHANGE: i m 4 I
ATTACHMENT 3 UNIT 1 RCS LEAKAGE i
2.1 ,
CONDITION:
RCS Leakage > T.S. limits requiring a Plant S/D or C/D l EMERGENCY CLASSIFICATION:
i
' Notification of Unusual Event MODES Above CSD CRITERIA:
- 1. RCS Leakage exceed T.S. 3.1.6 requirements necessitating a Plant S/D.
O l
RELATED EALS: TAB RCS Leakage > Normal Makeup Capacity (. 7pm) 2 t Initiation of Plant S/D or C/D due to LCO 6 OTSG Tube Leak 3 r
i
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 24 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
/~~N ATTACHMENT 3 UNIT 1 RCS LEAKAGE
2.2 CONDITION
RCS Leakage > Normal Makeup Capacity (50 gpm)
EMERGENCY CLASSIFICATION:
Alert MODES Above CSD CRITERIA:
- 1. An RCS leak necessitates EITHER of the following:
A. Need to open the BWST suction for the operating makeup pump due to a decreasing makeup tank level.
0B B. Full or partial HPI is needed to maintain the RCS Pressure or Pressurizer Level RELATED EALS: TAB RCS Leakage > Normal Makeup Capacity with Failed Fuel Conditions 2 RCS Leakage > HPI Capacity 2 Containment Radiation High/Very High 1 Core Damage Indicated with an ICC Condition 1 ,
Loss of or Challenge to 3 Fission Product Barriers 1 Radiological Ef fluents 5 Core Melt 1 Actuation of ECCS Components resulting in flow to the core 1 ;
I PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 25 of128 ;
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
10
( ATTACHMENT 3 UNIT 1 RCS LEAKAGE i
2.3 CONDITION
RCS Leakage > Normal Makeup Capacity (50 gpm) with >1.0% Failed Fuel Conditions l EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
Failed Fuel in the RCS (EAL 1.3)
O FAL 2.2 EAL 1.3 NOTE RCS Leakage > Normal Makeup Capacity (50 gpm)
RCS Activity Indicates >1% failed fuel RELATED EALS: TAB i Containment Radiation indicates LOCA and fuel failure 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1 i
i O l l
PROCANDRK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 26 Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
()- ATTACHMENT 3 UNIT 1 RCS LEAKAGE
2.4 CONDITION
RCS Leakage > HPI Capacity EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
A. Full available HPI being injected into the core AND B. RCS Pressure / Pressurizer Level continues to decrease or RCS Subcooling margin remains inadequate with no indication of recovery.
l l
RELATED EALS:
TAB Containment Radiation High/Very High 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product Barriers 1 Radiological Effluents 5
Core Melt 1
l
i i
PROCJWORK PUUd NO. PROCEDUfUUWORK PLAN Tm.E: PAGE: 27 Of128 ,
1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
ry.
ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.1 CONDITION
Uncontrolled OTSG Depressurization Resulting in MSLI Actuation FMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES Above CSD E
CRITERIA: #
- 1. Any snanual or automatic actuation of MSLI due to uncontrolled OTSG ;
depressurization below 600 psig. l
\
RELATED EALS: TAB OTSG Tube Leak 3 Radiological Effluents 5 i
v .
PRoCJWORK Pt.AN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 28 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
D ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.2 CONDITION
OTSG Tube Leakage 3 347 gpm EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES Above CSD CRITERIA:
i
- 1. RCS Leak rate of 1 347 gpm, with coincident Main Steam line N-16 alarm (s),
Steam Line High Range RAD Monitors Increase (RI-2681 or 2682) or condenser off O gas process monitor count rate increase or Nuclear Chemistry sample indicating Primary-Secondary tube leak.
[
RELATED EALS: TAB OTSG Tube Leak 3 !
RCS Leakage 2 t
l O !
PROCJwoRK PUW NO. PROCEDUREMORK PLAN TITLE: PAGE: 29 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION ' Rev: 32 CHANGE:
(..) ATTACHMENT 3 !
UNIT 1 SECONDARY SYSTEM EVENTS
3.3 CONDITION
OTSG Tube Leakage >10 gpm concurrent with ongoing steam release EMERGENCY CLASSIFICATION:
Alert MODES Above CSD CRITERIA:
- 1. RCS Leakrate increase of >10 gpm, with coincident Main Steam Line N-16 ala rm(s) or condenser off gas process monitor count rate increase, or Steam
/] Line High Range Rad Monitors Increase (RI-2681 or 2682) or Nuclear Chemistry
() sample indicating Primary-Secondary tube leak.
AND
- 2. ANY of the following occur:
A. Loss of offsite power B. Steam release to the environment indicated by:
- 1. Main Steam Safety Valve (s) lift
- 2. Use of ADV(s) to control affected OTSG pressure
- 3. P7A running with steam from affected OTSG
- 4. Steam line break outside containment RELATED EALS: TAB OTSG Tube Rupture >50 gpm with ongoing steam release 3 OTSG Tube Leak with failed fuel 3 RCS Leakage 2 Radiological Effluents 5 High Radiation / Airborne Levels 5 Electrical Power Failures 4 Loss of or Challenge to 3 Fission Product Barriers 1 (s
PROCJWORK PUW NO. PROCEDURE /WDRK PLAN TTTLE: PAGE: 30 of 128 !
1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION miiv: 32 CHANGE:
-0 ,
ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS 3.4 CONDITION:
OTSG Tube Rupture with primary to secondary leakage > normal makeup capacity (50 gpm) with ongoing steam release EMERGENCY CIASSIFICATION: l Site Area Emergency MODES Above CSD CRITERIA:
- 1. OTSG Tube Rupture as indicated by BOTH of the following:
A. RCS Leakage > Normal Makeup Capacity (50 gpm)
I
( B. Coincident Main Steam line N-16 alarm (s) or condenser off gas process monitor count rate increase or Steam Line High Range Rad Monitors Increase ,
(RI2681 or RI2682) or Nuclear Chemistry Sample indicating Primary-Secondary tube leak.
AND
- 2. ANY of the following occur: ,
A. Loss of offsite power t B. Steam release to the environment indicated by:
- 1. Main Steam Safety Valve (s) lift
- 2. Use of ADV(s) to control affected OTSG pressure
- 3. P7A running with steam from affected OTSG
- 4. Steam line break outside containment REIATED EALS: TAB RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 Electrical Power Failures 4 i
O
PROC.4 WORK PLAN NO. PROCEDURE 4 WORK PLAN TTTLE: PAGE: 31 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS 3.5 i
CONDITION:
OTSG Tube Leak >l gpm with >1% failed fuel with ongoing steam release EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
- 1. OTSG Leakrate increase of >1.0 gpm, with coincident Main Steam Line I N-16 alarm (s), or condenser off gas process monitor countrate increase or Nuclear Chemistry sample: indicating Primary-Secondary tube leak.
AND
AND
- 3. ANY of the following occur:
A. Loss of offsite power B. Steam release to the environment indicated by:
- 1. Main Steam Safety Valve (s) lift
- 2. Use of ADV(s) to control affected OTSG pressure
- 3. P7A running with steam from affected OTSG
- 4. Steam line break outside containment RELATED EALS: TAB RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 Electrical Power Failures 4 0
PROC / WORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 32 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 i CHANGE:
th ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILUAES
4.1 CONDITION
Degraded Power EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Only Diesel Generator power is available to 4160V Buses (A3 and/or A4).
AND 2a No voltage indicated on 6.9 KV AND 4.16 KV nonvital buses (H1, H2, A1, and A2)
RELATED EALS: TAB Blackout 4 OTSG Tube Leak 3 O
PROCJWORK PLAN NO. MtOCEDUMUWORK PLAN TITLE: PAGE: 33 of 128 l 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 j CHANGE:
ATTACHMENT 3 UNIT 1- )
ELECTRICAL POWER FAILURES l
4.2 CONDITION
l Station Blaekout-EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. All 4160V buses de-energized.
O RELATED EALS: TAB Blackout more than 15 minutes 4 Loss of Control Room Annunciators 6
i PROCJWORK PLAN NO. - PROCEDURFJWORK PLAN TTTLE: PAGE: 34 of 128 I
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 !
CHANGE:
-/'~'N ii i
\d ATTACHMENT 3 i UNIT 1 '
ELECTRICAL POWER FAILURES
4.3 CONDITION
l Blackout for more than 15 minutes.
EMERGENCY CLASSIFICATION:
Site Area Emergency
+
MODES All CRITERIA:
- 1. All 4160V buses de-energized for greater than 15 minutes.
RELATED EALS: TAB Electrical Power Failures 4 Loss of Control Room Annunciators 6 Core Melt 1 0
M10CJWORK PLAN NO. PROCEDUREMORK PLAN TmE: PAGE: 35 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
.i m
-(
i
. \_,/ ATTACHMENT 3-UNIT 1 !
ELECTRICAL POWER FAILURES 4.4 l
i' CONDITION:
Loss of All Vital DC Power i
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Loss of voltage on ALL of the following busses A. D01 and D02 i g B. RA1 and RA2 C. D11 and D21 RELATED EALS: TAB Loss of All Vital DC Power for more than 15 minutes 4 Loss of Control Room Annunciators 6 e
O l
PROCMORK Pt.AN NO. MtOCEDURIDWORK PLAN TITLE: PAGEb 36of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE' l
^
ATTACHMENT 3 j UNIT 1 l ELECTRICAL POWER FAILURES '
4.5 l
CONDITION: l Loss of All Vital DC Power for more than 15 minutes d
EMERGENCY CIASSIFICATION:
Site Area Emergency MODES All !
i CRITERIA: ,
f
- 1. Loss of voltage on ALL of the following busses A, p01 and D02
/ B. P/d and RA2 C. D11 and D21 AND 2, DC power is not restored within 15 minutes ,
RELATED EALS: TAB Electrical Power Failures 4 Loss of Control Room Annunciators 6 t
i i
i
PROCAWORK PLJud NO. MtOCEDURE/ WORK PLAN TITLE: PAGE: 37 Of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 :
CHANGE:
\
C ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.1 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is greater than or equal to .05 mrem /hr TEDE or .15 mrem /hr Child Thyroid or Liquid radiological effluents exceed Tech. Spec. Limits.
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
I
- 1. Radiologi. cal Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to .05 mrem /hr TEDE or .15 mrem /hr child thyroid.
E B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds .05 mrem /hr TEDE or .15 mrem /hr Child Thyroid.
E C. Liquid radiological effluents exceed Tech. Spec. Limits.
RELATED EALS: TAB Radiological Effluents 5 High Radiation / Airborne Levels 5 OTSG Tube Leak 3 O .
PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 38of128 1903.010 EMERGENCY ACTION LEVEL CLASSlFICATION REV: 32 CHANGE: .
(
(_/ ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS 5.2 CONDITION:
Projected or measured activity at the Site Boundary, averaged over one hour, is greater than or equal to .5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid or Liquid radiological effluents exceed 10 times Tech. Spec. Limits.
EMERGENCY CLASSIFICATICN Alert MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS :
method, indicates greater than or equal to .5 mrem /hr TEDE or 1.5 mrem /hr Child thyroid. 1 0B B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds .5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid. >
EB C. Liquid radiologica' effluents exceed 10 times Tech. Spec. Limits.
RELATED EALS: TAB Radiological Effluents 5 OTSG Tube Leak 3 Containment Radiation High 1 N
l l
PROCJWORK PLAN NO. PROCEDURFJWORK PLAN TRU: PAGE: 39 of 128 ;
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
r
'\ _,\/ ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.3 CONDITION
Radiological Effluents are greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr child Thyroid at the Site Boundary.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits A. Projected dose rates at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr Child thyroid.
9.R B. Offsite monitoring teams report dose rates at the Site Boundary are greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr Child Thyroid.
RELATED EALS: TAB Radiological Effluents 5 Containment Radiation High / Very High 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1 i
PROCJWORK PLAN NO. PROCEDURE / WORK PUW Tm2: PAGE: 40 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: (
ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS ;
5.4 CONDITION
Radiological Effluents are greater than or equal to 250 mram/hr TEDE or 500 mrem /hr Child Thyroid at the Site Boundary.
EMERGENCY CLASSIFICATION:
General Emergency ;
MODES All ,
CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits
(%
( ') A. Projected dose rates at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr Child Thyroid.
pR B. Offsite monitoring teams report dose rates at the Site Boundary are greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr Child Thyroid.
RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation High / Very High 1
i PROCJWORK PLAN NO. PROCEDURE / WORK M.AN MLE: PAGE: 41 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: ,
R ATTACHMENT 3 UNIT 1. l RADIOLOGICAL EFFLUENTS f
5.5 CONDITION
High Radiation / Airborne Levels EMERGENCY CLASSIFICATION:
Alert MODES All i
CRITERIA:
- 1. The loss of control of radioactive material results in ANY of the following:
I A. Containment radiation indicates >2R/hr
, B. Area Radiation levels in controlled access (excluding containment) increase by 1 Rem /hr at 2 or more locations.
C. General area radiation levels outside of radiologically controlled areas increase by 10 mrem /hr.
D. Airborne levels as follows:
- Auxiliary Building 1100 DAC (General Area)
- Turbine Building 310 DAC ,
1 NOTE: " Loss of Control *' shall be defined as: ANY radioactive material outside its normal system boundries. (For Example: spent resin spill, RCS liquid spill, spent fuel accident resulting in gaseous release, etc.)
l I
RELATED EALS: TAB Radiological Effluents 5 i Containment Radiation High 1 i Spent Fuel Accident 5 !
RCS Leakage 2 l k
I i
PROCAUORK PLAN NO. PROCEDUIEWORK PLAN MU: PAGE: 42 of 128
.1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 l
\ [
s ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS I 5.6 CONDITION: f Spent Fuel Accident EMERGENCY CIASSIFICATION: !
Site Area Emergency
- MODES All CRITERIA:
- 1. The loss of water OR damage to a spent fuel assembly occurs in the spent fuel j pool, refueling canal, or Rx core (head removed).
AND
)
RELATED EALS: TAB ,
Radiological Effluents 5 ,
High Radiation / Airborne Levels 5 i
l P
i
c; PROCJWORK PLAN NO. - Mt0CEDURE/ WORK PUW Tm.E: PAGE: 43 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: ,
i V ATTACHMENT 3 UNIT 1 SAFETY SYSTEM IUNCTION
6.1 CONDITION
Initiation of a Plant Shutdown or Cooldown for Tech Spec Limiting Condition for !
Operation Compliance OR Deviation from T.S. L.C.O.'s (10CFR 50.54x) ,
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES Above CSD CRITERIA:
- 1. ANY of the following conditions exist:
A. Plant shutdown or cooldown has been initiated as required to comply with the action statements associated with any L.C.O.
B. Deviation from Tech specs authorized pursuant to 10CFR50.54(x)
RELATED EALS: TAB RCS Leakage 2 OTSG Tube Leak 3 RCS Activity High 1 s
)
PROCJWORK PLAN No. PROCEDURFJWORK PLAN TITLE: PAGE: 44 of 128 1903.010 EMERGENCY ACTION LEVEL CLAS3IFICATION 'REV: 32 i CHANGE:
( / ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.2 CONDITION:
Reactor Protection System Failure to Complete an Automatic Trip EMERGENCY CIASSIFICATION: ,
Alert MODES Hot Stdy-Pwr Ops -
CRITERIA:
- 1. A valid RPS trip setpoint is exceeded on ANY TWO RPS channels and the RPS fails to initiate and complete an automatic trip that brings the reactor suberitical.
AND !
- 2. Subsequent efforts to manually trip the Reactor from the Control Room and bring it suberitical are successful. ,
REIATED EALS: TAB RPS Failure to Complete a Man ? Trip 6 Core Melt 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product Barriers 1
)
O l
PROCAWORK PLAN NO. PROCEDURIUWORK PLAN TME: PAGE: 45 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
(\j ATTACHMENT 3 t
UNIT 1 SAFETY SYSTEM FUNCTION
6.3 CONDITION
Reactor Protection System Failure to Complete an Manual Trip EMERGENCY CIASSIFICATION:
Site Area Emergency MODES Hot Stdy-Pwr Ops CRITERIA:
- 1. A valid RPS trip setpoint is exceeded on ANY TWO RPS channels and the RPS fails to initiate and complete an automatic trip that brings the reactor suberitical.
AND -
- 2. Failure of manual trip function occurs. (Failure to trip the Reactor in the Control Room; i.e., must leave Control Room to trip the Reactor.)
REIATED EALS: TAB .
Loss of or Challenge to 3 Fission Product Boundaries 1 Core Melt 1 Core Damage Indicated with an ICC Condition 1 I O
PROCJWORK Pt.AN NO. PROCEDURE / WORK PLAN TmE: PAGE: 44 Of 128 1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
f')
C/ ATTACHMENT 3 UNIT 1 '
SAFETY SYSTEM FUNCTION
6.4 CONDITION
Loss of Dose Assessment Capabilities !
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. The following conditions exist in the PASS Building:
A. SPING is inoperable AND B. PASS sampling is in progress AND C. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 2. The following conditions exist in t.h Low Level Radwaste Building:
A. SPING is inoperable AND B. Compacting is in progress AND C. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
E
- 3. Reactor Building Purge System or Penetration Ventilation System is not isolable, and the applicable SPING is inoperable.
- 4. All of the following conditions exist for any source of gaseous effluents in the Auxiliary Building or Spent Fuel Storage Building ventilation systems.
A. Applicable SPING is inoperable AND B. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> RELATED EALS: TAB None O
PROCAWORK PLAN NO. Pwm MAWORK PLAN Tm.E: PAGE: 47Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
(j\
\ ATTACHML1.-J UNIT 1 SAFETY SYSTEM FUNCTION
6.5 CONDITION
Loss of Conununications ,
EMERGENCY CLASSIFICATION: ,
Notification of Unusual Event MODES All t
CRITERIA:
- 1. Complete loss of ANY TWO of the following:
A. Plant telephone systems (Commercial Telephones and microwave)
B. Station Radio ,
C. Energency Notification System REIATED EALS: TAB None O
M:cWORK PUW No. PROCEDUREtWORK PLAN Tm.E: PAGE: 48 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
q ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.6 CONDITION
Loss of Control Room Annunciators EMERGENCY CLASSIFICATION:
1 Alert MODES All l
CRITERIA:
- 1. Loss of both AC and DC power to >50% of control room annunciators.
RELATED EALS: TAB Loss of Control Room Annunicators with Transient in Progress 6 0
i l
PROCJWORK PuhN NO. Pwm m) WORK PUW Tmf: PAGE: 49 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 j CP*.:03E: I
\ ATTACHMENT 3 UNIT 1 i SAFETY SYSTEM FUNCTION ,
1
6.7 CONDITION
Loss of Control Room Annunciators with Transient in Progress EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA: i
- 1. Loss of both AC and DC power to >50% of control room annunciators. '
\ AND -
Y 2. A plant transient is initiated or in progress.
(See sectin 4.18 of this procedure for the definition of a Plant Transient.)
s l
RELATED EALS: TAB -
None t
O
l c
PROCJWORK PLAN NO. PROCEDUREAVORK PLAN TTTLE: PAGE: 50 of128 1 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
b i V
ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.8 CONDITION
Control Room Evacuation EMERGENCY CIASSIFICATION:
Alert MODES All CRITERIA:
- 1. Control Room evacuation is expected to occur OR has already occurred.
O RELATED EALS: TAB l
Control Room Evacuation and control of shutdown systems not 6 established in 15 minutes Fire or explosion onsite affecting both trains of any ES Systems 7 I
h
+
O .
t i
PROCJWORK PUUd NO. PROCEDUfMMORK PLAN TmE: PAGE: 51 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 l CHANGE-p ATTACHMENT 3 :
UNIT 1 SAFETY SYSTEM FUNCTI0N I'
6.9 1
CONDITION:
Control Room Evacuation and control of shutdown systems not established in 15 '
minutes. I i
EMERGENCY CIASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Control Room evacuation has occurred AND control of shutdown systems is not established from local stations within 15 minutes.
1 I
RELATED EALS: TAB Core Damage Indicated with an ICC Condition 1 Loss of Decay Heat Removal Systems 6 ;
Core Melt 1 L
1
MeoCUWORK PUW NO. PowwmmanaORK PLAN Tm2: PAGE: $2Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
A ATTACHMENT 3 ,
UNIT 1 i SAFETY SYSTEM FUNCTION '
6.10 i
CONDITION:
Loss of Decay Heat Removal Capabilities EMERGENCY CLASSIFICATION:
Alert ,
MODES CSD-Refueling S/D i
CRITERIA:
i
- 1. Loss of Decay Heat Removal capabilities shall be identified as ANY of the following:
A. RCS indicates saturated conditions B. Loss of both Decay Heat trains for >l hr and OTSGs are not available for decay heat removal (NA if Fuel Transfer Canal is flooded) l
} C. HPI is required for cooling the reactor core.
l 1
i RELATED EALS: TAB Core Damage Indicated with an ICC Condition 1 i Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 High Radiation / Airborne Levels 5 ,
Core Melt 1
PnoCJunonKPt.E NO. PROCEDUIWWORK PUW Tm2: PAoE: 53 of138 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
[ ATTACHMENT 3
'O UNIT 1 SAFETY SYSTEM FUNCTION i 6.11 CONDITION: v Degraded Hot Shutdown capability EMERGENCY CLASSIFICATION:
Site Area Emergency ,
i MODES Above CSD i
CRITERIA:
- 1. Degraded HSD capability shall be identified as ANY of the following:
A. Loss of ALL steam removal capability on BOTH OTSGs. (eg. Loss of i ALL Turbine Bypass Valves, Atmospheric Dump Valves, and Main Steam Safety Valves)
B. Loss of ALL feedwater supply capability on BOTH OTSGs. (eg. Loss of BOTH Main Feedwater Trains and BOTH EEW trains) ;
C. BOTH HPI Trains are inoperable.
RELATED EALS: TAB Core Damage Indicated with an ICC Condition 1 Containment Radiation Very High 1 Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 ;
i l
i i
l l
PnOCJWORK PUW NO. PROCED'MUWORK PUW Tm.E: PAGE: 54 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANOE:
s ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.1 CONDITION
?
Security threat onsite but outside the Protected Area Security Fence (e.g.,
attempted entry or sabotage which has been stopped outside the security fence).
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA: ,
f Same as the Condition stated above.
r 1
i RELATED EALS: TAB ongoing security Threat Inside Protected Area Fence but outside 7 plant buildings 1
PaoCJwasut PUW NO. MtOCEDuftEUWORK PLAN TITLE: PAGE: 55 of 128 1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE:
O
'N ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.2 CONDITION
Ongoing security threat within the Protected Area Security Fence but outside of plant buildings EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
Same as the Condition stated above. l O l i
i I
l RELATED EALS: TAB Ongoing security threat within plant buildings but not in Control 7 Room or vital areas.
O
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN Tm2: PAGE: $$Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE:
N
) ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.3 CONDITION
Ongoing security threat within plant buildings but not within the Control Room or vital areas EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
Same as the Condition stated above.
O RELATED EALS: TAB ongoing security Threat within Control Room or Vital Areas 7 P
t
'I J
O !
PROCJWORK PLAN NO. PROCEDUREAWORK PLAN Tm2: PAGE: 57 of 128 ,
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
m s a V ATTACHMENT 3 UNIT 1 !
HAZARDS TO STATIGli DrERATION
7.4 CONDITION
Ongoing security threat within the Control Room or vital areas EMERGENCY CLASSIFICATION:
General Emergency MODES All i
CRITERIA:
Same as the Condition stated above.
O RELATED EALS: TAB None O
l MeccAWORK PLAN NO. PF*ruutEMORK PLAN Tm.E: PAGE: 88 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
\s ATTAC1 DENT 3 I UNIT 1 HAZARDS TO STATION OPERATION l
7.5 CONDITION
I Fire or Explosion Onsite i EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Fire within the Protected Area Security Fence which is not extinguished within 10 minutes.
\
EE
- 2. Explosion causing facility damage.
RELATED EALS: TAB Fire or Explosion Onsite Affecting One Train of an ES System 7 l
PROCJWWOIUC PLAN NO. PftOCEDUltEJWOftK PLAN TITU: PAGE: 59 of128 j 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
I y/ ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION y 7.6 f CONDITION:
Fire or Explosion Onsite Affecting One Train of ANY ES Systems EMERGENCY CLASSIFICATION:
Alert MODES All i
CRITERIA:
- 1. Fire or explosion onsite O 2.
^""
A potential or actual loss of a single train of ANY ES system as a result of the fire or explosion RELATED EALS: TAB Fire or Explosion Onsite Affecting Both Trains of ANY ES System 7 Control Room Evacuation 6 O
l l
PROCMORK PUW NO. PROCEDUMUWORK PUW TmE: PAGE: 60 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
( ATTACHMENT 3 UNIT 1 ,
HAZARDS TO STATION OPERATION I
7.7 CONDITION
Fire or Explosion Onsite Affecting Both Trains of ANY ES Systems i
EMERGENCY CIASSITICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Fire or explosion onsite b
i
- D v 2. A potential or actual loss of Both trains of ANY ES system as a result of the fire or explosion RELATED EALS: TAB Control Room Evacuation and control of shutdown systems not 6 established in 15 minutes
PROCMORK PLAN NO. MtOCEDUREMORK PLAN TITUE: PAGE: 61Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
^ ~
f\
V ATTACHMENT 3 UNIT 1 l HAZARDS TO STATION OPERATION l I
7.8 CONDITION
Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine Failure, Toxic or Flammable Gas Release EMERGENCY CIASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. ANY of the following:
) A. Aircraft crash onsite.
B. Unusual Aircraft activity over the facility.
C. Train derailment onsite.
D. Turbine rotating component failure causing rapid plant shutdown.
E. Tos:ic or flammable gas release which limits or restricts access to areas requitad for security or safe operation of the plant. ;
REIATED EALS: TAB -
Fire or Explosion Onsite 7 Security Threat 7 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One 7 Train of ANY ES System t
{ s V
PROC /AKWtK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 62 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSlFICATION REV: 32 CHANGE:
.,n l
(, ATTACHMENT 3 UNIT 1
. HAZARDS TO STATION OPERATION
7.9 CONDITION
Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ANY ES Systems EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following:
A. Aircraft crash onsite.
B. Missiles / Projectiles from any source C. Toxic or flammable gas release AND
- 2. A potential OR actual loss of a single train of ANY ES system RELATED EALS: TAB Fire or Explosion Onsite Affecting One Train of an ES System 7 !
Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both 7 Trains of ANY ES System l l
1 O
PROCJWORK PLAN No. Mt0CEDUfupWORK PLAN Tm2: PAGE: 63of128 1903.010 EMERGENCY ACTION LEVEL CLASSlFICATION REV: 32 CHANGE:
/
.' ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.10 CONDITION:
Aircraft Crash, Missiles, Toxic or Flansnable Gas Affecting Both Trains of ANY ES System EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. ANY of the following:
/3 A. Aircraft crash onsite.
B. Missiles / Projectiles from any source C. Toxic or flammable gas release AND ;
- 2. A potential OR actual loss of BOTH trains of ANY ES system REIATED EALS: TAB Fire or Explosion Onsite Affecting Both Trains of an ES System 7 l
0
PROCJWORK PLAN NO. PROCEDUREWRNtK PLAN Tm2: PAGE: 64Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
ATTACHMENT 3 UNIT 1 NATURAL EVENTS
8.1 CONDITION
Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION: ,
Notification of Unusual Event MODES All CRITERIA:
- 1. ANY of the following:
A. Tornado observed on the ground within the Exclusion Area Og B. Flood - Lake level 2340' elev. and rising, with forecasted lake level 1350' elev.
C. Low Level - Lake level <337' elev. AND forecasted by U.S. Army Corp I of Engineers to reach 335' elev. ;
D. Earthquake - VERIFIED earthquake of magnitude of .Olg RELATED EALS: TAB Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, 8 Earthquakes i i
t O
i Mt0CAMORK PLAN NO. PROCEDUfUUWORK PLAN Tm.E: PAGE: 65 of 128 t 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE.-
rs ATTACHMENT 3 UNIT 1 NATURAL EVENTS
8.2 CONDITION
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION:
Alert MODES All ,
CRITERIA:
- 1. ANY of the following:
O A. Tornado striking vital facility structures (e.g. housing ES related equipment)
B. High Winds - Sustained winds of 160 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments).
C. Flood - Flood waters 3350' elev, and are forecasted by U.S. Army Corp of Engineers to reach or exceed 354' elev.
D. Low Level - Lake level 5335' elev E. Earthquake - VERIFIED earthquake of magnitude of 1.lg F. Any of the above resulting in the potential or actual loss of ONE train of ANY ES system.
RELATED EALS: TAB Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake 8 Loss of or challenge to all 3 Fission Product Barriers 1 O
PROCJWORK PLAN No. MtoCEDURE/ WORK PLAN TITLE: PAGE: $$ Of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
O ATTACHMENT 3 UNIT 1 NATURAL EVENTS 8.3 CONDITION:
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
- 1. ANY of the following
[ A. High Winds - Sustained winds of 167 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments).
B. Flood - Flood Water Level is >361' elev.
C. Low Level Lake level 5335' elev. and Emergency Cooling Pond not available D. VERIFIED Earthquake 30.2g E. Tornado, high wind, flood, low lake level or earthquake resulting in the potential or actual loss of BOTH trains of ANY ES system.
RELATED EALS: TA3 Loss of or challenge to all 3 Fission Product Barriers 1 O
PROCJWORK PLAN NO. PROCEDURIDWORK PLAN Tm.E: PAGE: 67Of128.
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
(~
( ATTACHMENT 3 UNIT 1 MISCELIANEOUS EVENTS
9.1 CONDITION
Transport of a Contaminated Injured Individual to an Offsite Medical Facility i
EMERGENCY CIASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. A personnel emergency has occurred and the following conditions exist:
A. The injured individual is radiologically contaminated.
AND B. The injured individual is transported to an offsite Medical Facility.
l RELATED EALS: TAB None
.= . ._
PROCJWORK PLAN NO. PROCEDUMUWORK PUW TITLE: CAGE: SS of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
( i V ATTACHMENT 3 UNIT 1 ;
MISCELLANEOUS 9.2 {
l l
CONDITION:
other plant conditions exist that warrant increased awareness on the part of the operating staff and state and/or local offsite authorities or require plant shutdown under technical specification requirements or involve other than normal controlled shutdown.
1 EMERGENCY CLASSIFICATION:
Notification of Unusual Event >
MODES All i
CRITERIA: 4
( '
An event has occurred and the following conditions exist:
- 1. This event is not covered by any other EAL [
AND l
- 2. This event does not challenge or cause the loss of a fission product barrier AND
- 3. In the judgement of the SS/TSC Director / EOF Director this event requires an ,
increased awareness by the ANO staff and offsite authorities. 6 I
RELATED EALS: TAB Plant Conditions Exist that Warrant Precautionary Activation of the 9 TSC I
l r
i PROCJWORK PUW NO. PROCEDURElWORK PLAN Tm.E: PAGE: 69 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
)
) ATTACHMENT 3 UNIT 1 MISCELIANEOUS 9.3 i CONDITION:
Other plant conditions exist that warrant precautionary activation of the Technical Support Center and placing the near-site Emergency Operations Facility and other ;
key emergency personnel on standby. !
EMERGENCY CLASSIFICATION: ,
Alert MODES All CRITERIA:
f The following conditions must exist f
- 1. This event is not covered by any other EAL. ,
AND
- 2. This event must either challenge or cause the loss of a fission product f barrier.
l Plant conditions exist that warrant activation of the Emergency Response
Organization.
j l
i RELATED EALS: TAB !
Plant Conditions Exist that Warrant Activation of the Emergency 9 Response Centers. !
O
PROCJWORK PLAN NO. PROCEDUREfWORK PuhN TITLE PAGE: 70 of 128 1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
.,c-V ATTACHMENT 3 UNIT 1 MISCELLANEOUS
9.4 CONDITION
i i
Other plant conditions exist that warrant activation of the emergency response facilities and monitoring teams or a precautionary notification to the public near the site.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
The following conditions must exist
- 1. This event is not covered by any other EAL.
AND
- 2. The event must cause ANY of the following:
A. Challenge two fission product barriers B. Failure of one fission product barrier and a challenge to another C. Failure of Two fission product barriers REIATED EALS: TAB Plant Conditions Exist that Make Release of Large Amounts of 9 Radioactivity Possible ,
I o
b
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TTTLE. PAGE: 71 Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
O ATTACHMENT 3 UNIT 1 MISCELIANEOUS 9.5 CONDITION:
Plant Conditions Exist That Make Release of Large Amounts of Radioactivity Possible EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
t The following conditions must exist: ;
- i. This event is not covered by any other EAL AND
- 2. Events have occurred that make a release of large amounts of radioactivity in a short period of time possible. ,
RELATED EALS: TAB None i t
f 9
h r - - __ _ _ _ _ _ _ _ _ . _ . _ _
t PROCJwoRK PUW NO. PROCEDUREMORK PLAN TITLE: PAGE: 72of128 '
1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION _ m: 32 CHANGE:
(
( ,
ATTACHMENT 4 UNIT 2 i
ECC INJECTION [
1.1 CONDITION
Actuation of ECCS Components resulting in flow to the core l i
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 CRITERIA:
- 1. Either of the following events occur: ,
T A. HPSI pump (s) running AND injecting flow into the core as indicated by ALL of the following: ;
- 1) RCS pressure <1450 psia
- 3) HPSI Flow indicated B. LPSI pump (s) running AND injecting flow into the core as indicated by ALL ,
of the following: ,
- 1) RCS pressure <200 psia
- 3) Pzr Level increasing ,
i I
RELATED EALS: TAB None f
l t
b i
PROCAWORK M.AN NO. PROCEDURE / WORK PLAN Tm2: PAGE: 73 Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
75 ATTACHMENT 4 UNIT-2
- RCS ACTIVITY
1.2 CONDITION
RCS Activity indicates >0.1% failed fuel EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-5 CRITERIA:
- 1. Greater than 0.1% failed fuel as indicated by EITHER of the following:
A. Selected isotope activity (I*'*) 5.5E' CPM (2RR4806 on 2C14 or 2Rits 4806B on 2C22)
B. Specific I*** sample results >37.8 pCi/gm RELATED EALS: TAB RCS Activity 1 T.S. L.C.O.'s 6 General Area Radiation / Airborne 5 l
O
- Mt0CJWORK PLAN NO. PROCEDUREJWORK PLAN Tm.E: PAGE: 74 Of 128
( 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
! ATTACHMENT 4 UNIT 2 RCS ACTIVITY
1.3 CONDITION
RCS Activity indicates >l.0% failed fuel EMERGENCY CIASSIFICATION:
Alert MODES 1-5 CRITERIA:
- 1. Greater than ts:
1% failed fuel as indicated by RCS Sample Analysis >378 pCi/gm specific I O
U REIATED EALS: TAB General Area Radiation / Airborne 5 Containment Radiation 1 .
Loss of or Challenge to 3 Fission Product Barriers 1 Core Damage /ICC 1
\
I
PROCJWORK PLAN NO. PROCEDURIUWORK PLAN TULE: PAGE: 75 of128 ,
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
ATTACHMENT 4 UNIT 2 Core Damage /ICC
1.4 CONDITION
Core Damage Indicated with a Inadequate Core Cooling Condition EMERGENCY CLASSIFICATION:
Site Area Emergency MO' DES 1-5 '
CRITERIA:
- 1. Greater than 1% failed fuel as indicated by RCS sample analysis >378 pCi/gm Specific I 131 AND
- 2. Inadequate core cooling capacity exist as indicated by ANY of the following:
A. Th RTD and average CET temperature indicates >10*F superheat AND RVLMS LVL 7 or Lower indicates Dry.
B. Th RTD and average CET temperature indicates >10*F superheat with both RVLMS Channels inoperable AND RCS temperatures increasing.
C. CET Temperatures indicate greater than 700*F.
RELATED EALS: TAB Decay Heat Removal 6 Containment Radiation 1 Core Melt 1 RCS Leakage 2
PROCAWORK PUW NO. PNSWORK PLAN TITLE: PAGE: 76 Of128 l
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANC :
/G. !
() ATTACHMENT 4 UNIT 2 CONTAINMENT PARAMETERS i
1.5 I l
CONDITION:
Containment Radiation readings which indicate LOCA and >l% cladding failure EMERGENCY CLASSIFICATION:
Sito Area Emergency MODES All d* O %N-CRITERIA:
- 1. Containment Radiation Levels correspond to a Site Area Emergency as determined from the containment radiation EAL plot (Att 6)
(
l RELATED EALS: TAB Containment Radiation 1 Loss of or challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1 V ,
PROCJWORK Pt.AN NO. PROCEDUREMORK PLAN TITLE: PAGE: 77 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
)
%) ATTACHMENT 4 UNIT 2 f
CONTAINMENT RADIATION
1.6 CONDITION
i Containment Radiation readings which indicate LOCA and >50% fuel overheat I 1
EMERGENCY CLASSIFICATION:
General Emergency i MODES All ;
CRITERIA:
ll
- 1. Containment Radiation Levels correspond to a General Emergency as determined from the containment radiation EAL plot (Att 6) !
O i
i RELATED EALS: TAB +
Loss of or challenge to 3 Fission Product' Barriers 1 Radiological Effluents 5 !
Core Melt 1 1
sammene i-
, PROCJWORK PLAN NO. PROCEDUREMORK PLAN Tm.E: PAGE: 78 Of 128
- 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: L w/ ATTACHMENT 4 UNIT 2 ,
CORE MELT'
1.7 CONDITION
Core Melt with Containment Integrity Lost or Challenged l l
EMERGENCY CLASSIFICATION:
General Emergency MODES All ,
e CRITERIA:
- 1. ANY of the following events occur O
U A. Small or Large LOCA and a complete failure of ALL ECCS systems occurs. ,
t B. Loss of ALL feedwater AND S/G Level in both S/G's is $70" (Wide Range) I AND a complete failure of ALL ECCS Systems occurs.
- c. Anticipated transient without a Rx trip i
AND
- 2. Containment Integrity is lost OR challenged as defined by 4.16.3 or 4.17.3 (Definitions)
RELATED EALS: TAB Loss of or challenge to 3 Fission Product Barriers 1 Containment Radiation 1 Radiological Effluents 5 V
i 1
I 4
I
1 PROCAWORK Pt.AN NO. PROCEDUUUUWORK PLAN TmE: PAGE: 79 of 128 1 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32
- CHANGE
- ,
i p~,
ATTACHMENT 4 l UNIT 2 l LOSS OF OR CHALLENGE TO 3 FISSION PRODUCT BARRIERS j i
1.8 I CONDITION:
Loss of or challenge to all 3 Fission Product Barriers b
EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA: ,
- 1. Either of the following conditions exist:
A. Fuel Cladding Failure (refer to section 4.16.1)
T B. Challenge to Fuel Cladding (refer to section 4.17.1)
[O AND
- 2. Either of the following conditions exist:
A. RCS boundary failure (refer to section 4.16.2)
B. Challenge to RCS boundary (refer to section 4.17.2)
AND
- 3. Either of the following condition exist A. Containment Integrity failure (refer to section 4.16.3)
B. Challenge to containment Integrity (refer to section 4.17.3)
RELATED EALS: TAB Containment Radiation 1 Core Melt 1 Radiological Effluents 5 Natural Events 8
+
l i
PROCJWORK PUWd NO. PROCEDUIWWORK PLAN Tm.E: PAGE: 80 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: ;
ATTACHMENT 4 UNIT 2 RCS LEAKAGE ,
i
2.1 CONDITION
i RCS Leakage >T.S. limits requiring a plant S/D or C/D EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 CRITERIA:
1
- 1. RCS Leakage exceeds ANY of the tollowing limits: (T. S. 3.4.6.2) l A. RCS pressure boundary leakage >0 i Q'Q B.
C.
Unidentified RCS Leakage >l gpm Identified RCS Leakage >10 gpm D. RCS Pressure Isolation Valves Leakage > T.S. Table 3.4.6-1 Limits AND
- 2. A Plant S/D or C/D is required REIATED EALS: TAB RCS Leakage 2 T.S. L.C.O.'s 6 Primary to Secondary Leakago 3 General Area Radiation / Airborne 5 O
S
PROCJWORK A.AN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 81 Of 128 1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE:
('~)1
( ATTACHMENT 4 UNIT 2 RCS LEAKAGE
2.2 CONDITION
RCS Leakage > 44 gpm EMERGENCY CLASSIFICATION:
- 1. RCS Leakage is >44 gpm (Capacity of a single Charging Pump).
l RELATED EALS: TAB RCS Leakage 2 General Area Radiation / Airborne 5 Containment Radiation 1 Decay Heat Removal 6 Primary to Secondary Leakage 3 l)
U
PROCJWOfuC PLAN NO. PROCEDUREMORK PLANTHLE: PAGE: 82of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 ;
CHANGE:
'm
(
Le)- ATTACHMENT 4 UNIT 2 RCS LEAKAGE :
i 2.3 <
CONDITION:
RCS Leakage > 44 gpm with ICC Conditions i i
EMERGENCY CLAS3IFICATION:
Site Area Emergency NODES 1-4 CRITERIA:
- 1. RCS Leakage is >44 gpm (Capacity of a single Charging Pump). ;
AND
(
( 2. Inadequate Core Cooling conditions exist as indicated by ANY of the following:
A. Th RTD and average CET temperature indicates >10*F superheat AND RVIRS LVL 7 or Lower indicates Dry.
B. Th RTD and average CET temperature indicates >lC'F superheat with both RVLMS Channels inoperable AND RCS temperature increasing. j C. CET Temperatures indicate greater than 700'F. !
RELATED EALS: TAB Core Damage /ICC 1 Radiological Effluents 5 Containment Radiation 1 Core Melt 1 Loss of or challenge to 3 Fission Product Barriers 1 Primary to Secondary Leakage 3 ,
l i
(
m)
Ppt 0CAWOftK PLAN NO. PwmmM MAN TITLE: PAGE: 83 of 128 1903.010 ptev: 32 EMERGENCY ACTION LEVEL CL.ASSIFICATIOfJ CHANGE:
3 ATTACHMENT 4 UNIT 2 MSIS
3.1 CONDITION
Uncontrolled S/G Depressurization Resulting in MSIS Actuation l
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 CRITERIA:
- 1. Any actuation of MSIS due to uncontrolled Steam Generator depressurization.
i RELATED EALS: TAB Primary to Secondary Leakage 3 Radiological Effluents 5 l
l l
l O l
)
l l
PROCJWORK PLAN NO. PROCEDUREAMORK PLAN TTTUD PAGE: 84of128 1003.010 - EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE:
r\
h ATTACHMENT 4 UNIT 2 PRIMARY TO SECONDARY LEAYAGE 3.2 :
CONDITION:
S/G Tube Leak > Tech Spec Limits EMERGENCY CLASSIFICATION:
i Notification of Unusual Event MODES 1-4 CRITERIA:
- 1. Primary to Secondary Leakage exceeds EITHER of the following limits A. Total leakage through both S/G's is > 1 gpm EB B. Leakage to 1 S/G is >.5 gpm l
RELATED EALS: TAB RCS Leakage 2 Primary to Secondary Leakage 3 Radiological Effluents 5 s
PnoCJWosuc PLAN NO. PROCEDURE / WORK PLAN TTTLE: PAGE: 85 of 128 l 1903.010 Rev: 32 ;
EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE:
j O) ATTACHMENT 4 UNIT 2 PRIMARY TO SECONDARY LEAKAGE 3.3 CONDITION: ,
i S/G Tube Leak >10 gpm With an Ongoing Steam Release t
EMERGENCY CLASSIFICATION:
Alert MODES 1-4 l
CRITERIA:
- 1. 1. S/G tube leak >10 gpm with a Steam Release in Progress as indicated by ANY of the following:
A. Main Steam Safety Valves maintaining S/G Pressure B. SDBCS Atmospheric Dump Valves in Use C. Steam Line Break Outside of Containment D. 2P7A is in use and continued operation is required to maintain S/G levels.
RELATED EALS: TAB !
Primary to Secondary Leakage 3 RCS Leakage 2 General Area Radiation / Airborne 5 Radiological Effluents 5 Electrical Power 4 l
1 I
E' PROCAMORK PLAN NO. PROCEDURFJWORK PLAN TITLE- PAGE: 86of128 1903,010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE.*
O'
-ul ATTACHMENT 4 l UNIT 2 PRIMARY TO SECONDARY LEAKAGE 3.3,,4, CONDITION: 'l Steam Generator Tube Rupture >44 gpm With an Ongoing Steam Release and RCS Activity > 1.0 pCi/gm.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES 1-4 CRITERIA:
- l. S/G tube leak >44 gpm with a Steam Release in Progress as indicated by ANY of the followings
(_/ A. Main Steam Safety Valves maintaining S/G Pressure B. SDBCS Atmospheric Dump Valves in Use C. Steam Line Break Outside of Containment D. 2P7A is in use and continued operation is required to maintain S/G levels.
AND ;
- 2. RCS Activity > 1.0 pCi/gm (T.S. 3.4.8)
RELATED EALS: TAB RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt I r Electrical Power 4 i
O
MIOCAWOftK PLAN NO. MtOCEDUREhWORK PLAN TITLE: PAGE: 87 Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION stEv: 32 CHANGE: ;
("))
( ATTACHMENT 4 UNIT 2 ELECTRICAL POWER
?
4.1 i
i CONDITION:
Degraded Power EMERGENCY CLASSITICATION:
Notification of Unusual Event
- 10 DES All Modes CRITERIA:
- 1. Temporary Loss of Normal Control Room Lighting O AND U
- 2. No voltage indicated on Both 4.16 KV nonvital busses. (2A1 and 2A2)
AND
- 3. At Least One Emergency Diesel Started and supplying its respective bus (2A3 or 2A4)
RELATED EALS: TAB Electrical Power 4 MSIS 3 Primary to Secondary Leak 3 0
T Pn0CJWORK PLAN NO. MtOCEDUREtWORK PLAN Tm.E: PAGE: 88Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE:
' /%
ATTACHMENT 4 UNIT 2 ELECTRICAL POWER
4.2 CONDITION
Station Blackout EMERGENCY CLASSIFICATION:
Alert MODES All Modes CRITERIA:
1
- 1. Loss of all Control Room Lighting except emergency DC Lights O
^""
- 2. No voltage indicated on Both 4.16 KV nonvital busses. (2A1 and 2A2)
AND
- 3. Neither Emergency Diesel Generator Supplying power to its 4.16 KV busses RELATED EALS: ,
TAB Electrical Power 4 Communications, Dose Assessment 6 Primary to Secondary Leak 3 Decay Heat Removal 6 Core Melt 1
Pnoc) WORK PLAN NO. PROCEOlgtEMORK PUW TITUE: PAGE: 89Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
()
)( J ATTACHMENT 4 UNIT 2 ELECTRICAL POWER
4.3 CONDITION
Loss of All Vital DC EMERGENCY CLASSIFICATION:
Alert MODES 1-4 CRITERIA:
- 1. Loss of All of the following busses has occurred 2D01 and 2D02
~
A.
m/ B. 2RA1 and 2RA2 C. 2D21 and 2D23 D. 2D22 and 2D24 i
RELATED EALS: TAB Electrical Power 4 Communications, Dose Assessment 6 O
PROCJWORK PUW NO. PROCEDURE / WORK PLAN Tm.E: PAGE: 90 of128 1903.010 EMERGENCY ACTION LEVEL CLA881FICATION REV: 32 CHANGE:
Q -
. ATTACHMENT 4 UNIT 2 ELECTRICAL POWER
4.4 CONDITION
Blackout >15 minutes.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All i
CRITERIA:
i
- 1. Blackout has occurred as indicated by ALL of the following:
.O A. Loss of all Control Room lighting except emergency DC lights
- h B.
C.
No voltage indicated on Both 4.16 KV nonvital busses (2Al and 2A2)
Neither Emergency Diesel Generator supplying power to its 4.16 KV busses.
AND
- 2. The Blackout Condition exists for >l5 minutes RELATED EALS: TAB Decay Heat Removal 6 Electrical Power 4 Primary to Secondary Leakage 3 Core Melt 1 Radiological Effluents 5 O
i
PROCJWORK PUW NO. PROCEDufWWORK PUW Tm2: PAGE: 91 of 128 l 1903.010 EMERGENCY ACTION LEVEL Ct.ASSIF; CATION REV: 32 CHANGE:
/'^N
-t's ,/
1 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER I 4.5 i
CONDITION: I Loss of ALL Vital DC for >15 minutes EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Loss of both of the following trains of DC Busses has occurred i RED TRAIN GREEN TRAIN 2D01 2D02 ,
2RAI 2RA2 !
2D21 2D22 :
'~
2D23 2D24 AND
- 2. Power is not restored to at least one train within 15 minutes e
RELATED EALS: TAB Communications, Dose Assessment 6 Decay Heat Removal 6 Core Melt 1 Radiological Effluents 5 0
Proc) WORK PLAN NO. PROCEDUREMORK PLAN Tm2: PAGE: 92 Of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
- L
{
'v ATTACHMENT 4 UNIT 2 .
RADIOLOGICAL EFFLUENTS
5.1 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is greater than or equal to .05 mrem /hr TEDE or .15 mrem /hr Child Thyroid or Liquid radiological effluents exceed Tech. Spec. Limits.
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to .05 mrem /hr TEDE or .15 mrom/hr Child Thyroid. j e
B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds .05 mrem /hr TEDE or .15 mrem /hr Child Thyroid.
E C. Liquid radiological effluents exceed Tech. Spec. Limits.
RELATED EALS: TAB Radiological Effluents 5 General Area Radiation / Airborne 5 j Primary to Secondary Leak 3 i
l l !
l l l
PROCJWORK PLAN NO. PftOCEDURE/WOftK PLAN TITLE: PAoE: 93 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REY: 32 CHANGE:
7-
/ ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.2 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is greater than or equal to .5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid or Liquid i radiological effluents exceed 10 times Tech. Spec. Limits.
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to .5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid.
e B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds .5 mrem /hr TEDE or 1.5 i mrem /hr Child Thyroid. l M
C. Liquid radiological effluents exceed 10 times Tech. Spec. Limits. ;
RELATED EALS: TAB Radiological Effluents 5 Primary to Secondary Leak 3 Containment Radiation 1 O
l 1
l PROCJWORK PLAN NO. MtOCEDURE/ WORK PLAN TITLE: PAGE: 94Of128
-1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE.-
AMACNT 4 ,
UNIT 2 RADIOLOGICAL EFFLUENTS
5.3 CONDITION
Radiological Effluents are greater than or equal to 50 mrem /hr TEDE or 150 mram/hr Child Thyroid at the Site Boundary.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits
[h A. Projected dose rates at the Site Boundary, as calculated by the RDACS ,
h method, indicate greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr Child Thyroid.
EB B. Offsite monitoring teams report dose rates at the Site Boundary are greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr Child Thyroid.
RELATED EALS: TAB Radiological Effluents 5 Containment Radiation 1 Loss of or Challenge to 3 Fission Product Barriers _
1 Core Melt 1
i l
PROCJWOftK PLAN NO. PftOCEDUREMORK PLAN TITLE: PAGE: $$ of 128 l 1903.010 EMERGENCY ACTION LEVEL CLASS 6FICATION REV: 32 CHANGE:
sO ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS l
5.4 CONDITION
Radiological Effluents are greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr Child Thyroid at the Site Boundary.
EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits A. Projected dose rates at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr Child Thyroid.
OR B. Offsite monitoring teams report dose rates at the Site Boundary are greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr child '
Thyroid.
l RELATED EALS: TAB ;
Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 l Containment Radiation 1 l l
O l
l l
PROCJWORK PLAN NO. PROCEDUREMORK PLAN Tm.E: PAGE: 96 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE:
(D '
Cl ATTACHMENT 4 UNIT 2 GENERAL AREA RADIATION / AIRBORNE
5.5 CONDITION
High Radiation / Airborne Levels EMERGENCY CLASSIFICATION:
Alert MODES All !
CRITERIA:
- 1. The loss of control of radioactive material results in ANY of the tollowing:
A. Containment radiation indicates >2R/hr B. Area Radiation levels in controlled access (excluding containment) increase by 1 Rem /hr at 2 or more locations.
C. General area radiation levels outside of radiologically controlled areas increase by 10 mrem /hr.
D. Airborne levels as follows:
NOTE: " Loss of Control" Shall be defined as: Any Radioactive material.
outside its normal system boundaries.
(For Example: Spent resin spill, RCS liquid spill, Spent fuel accident resulting in gaseous release, etc.)
RELATED EALS: TAB Radiological Effluents 5 Containment Radiation 1 Spent Fuel Damage 5 RCS Leakage 2 l
(
MtoCJWORK PLAN NO. PROCEDUREMORK PLAN TrTLE: PAGE: 97 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
(d ATTACHMENT 4 UNIT 2 SPENT FUEL ACCIDENT
5.6 CONDITION
Spent Fuel Accident t
i EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. The loss of water g damage to a spent fuel assembly occurs in the spent fuel pool, refueling canal, or Rx core (head removed).
AND
RELATED EALS: TAB Radiological Effluents 5 General Area Radiation / Airborne 5 nv
I PROCJWORK PLAN NO. MtOCEDUREDWORK PLAN Tm.E. PAGE: 98 of 128 ,
REV; 32 :
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE:
- (~ ,
( ATTACHMENT 4 '
UNIT 2 T.S. L.C.O.'s
6.1 CONDITION
Initiation of a Plant Shutdown or Cooldown for Tech Spec. Limiting condition for (
Operation Compliance OR Deviation from T.S. L. C.O. 's (10CFR 50.54x) i EMERGENCY CLASSIFICATION:
Notification of Unusual Event !
MODES 1-4 CRITERIA:
- 1. ANY of the following conditions exist:
(s A. Plant shutdown or cooldown has been initiated as required to comply with the action statements associated with all L.C.O.'s B. Deviation from Tech Specs authorized pursuant to 10CFR50.54(x)
RELATED EALS: TAB RCS Leakage 2 Primary to Secondary Leakage 3 RCS Activity 1 O
f
PnOCAv0RK PUW NO. PROCEDURE / WORK PLAN Tm.E: PAGE: 99 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
O ATTACHMENT 4 ;
UNIT 2 RPS FAILURE
6.2 CONDITION
Reactor Protection System Failure to Complete an Automatic Trip EMERGENCY CLASSIFICATION:
Alert HO' DES 1-2 CRITERIA: i r
- 1. A valid RPS trip setpoint is exceeded ,
AND O, 2. Ten (10) or more CEAs fail to insert as result of the automatic trip AND 3 CEAs are inserted either by manual trip or DSS.
1 k
RELATED EALS: TAB RPS Failure 6 Core Melt 1 Core Damage /ICC 1 O
PnoCJwoRK PLAN NO. Mt0CEDUlupWORK PUW TmE: PAGE: 100 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: ,
\g ATTACHMENT 4 UNIT 2 RPS FAILURE
6.3 CONDITION
Reactor Protection System railure to Complete a Manual Trip EMERGENCY CLASSIFICATION:
Site Area Emergency MODES 1-2 CRITERIA:
- 1. A valid RPS trip setpoint is exceeded O 2.
AND Ten (10) or more CEAs fail to insert after the RPS, DSS and manual trip (Example: 2B7 & 2B8 feeder breakers opened to insert CEAs due to a failure of automatic and manual RPS trips.)
RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1 Core Damage /ICC 1 O
)
I PROCANCRK PLAN NO. PROCEDUREMORK PLAN Tm.E: PAGE: 101 of 128 '
1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
. s A, ATTACHMENT 4 UNIT 2 LOSS OF COMMUNICATIONS / DOSE ASSESSMENT ,
l
6.4 CONDITION
)
Loss of Dose Assessment capabilities i
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. The following conditions exist in the PASS Building:
A. SPING is inoperable l B. PASS sampling is in progress C. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
8
- 2. The following conditions exist in the Low Level Radwaste Building:
- A. SPING is inoperable B. Compacting is in progress C. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
E
- 3. Reactor Building Purge penetration is not isolable and both the applicable SPING and the Process Radiation Monitor are inoperable.
0R
- 4. All of the following conditions exist for any source of gaseous effluents in the Auxiliary Building, Auxiliary Extension Building, or Spent Fuel Storage Building ventilation systems.
A. Applicable SPING is inoperable B. Applicable Process" Radiation Monitor is inoperable C. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
RELATED EALS: TAB Communications, Dose Assessment 6 ;
PROCJWORK PLAN NO. PROCEDUREMORK PLAN Tm.E: PAGE: 102 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: -32 CHANGE:
) ATTACHMENT 4 N/
UNIT 2 LOSS OF COMMUNICATIONS / DOSE ASSESSMDIT
6.5 CONDITION
Loss of Communications DiERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Complete loss of ANY TWO of the following:
A. Plant telephone systems (Commercial telephones and microwave)
B. Station Radio C. Emergency Notification System RELATED EALS: TAB None r
l 1
PROCAWOHK PLAN NO. Mt0CEDU149WOHK PLAN TmK: PAoE: 103 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
("%
ATTACHMENT 4 UNIT 2 CONTROL ROOM EVACUATION
6.6 CONDITION
Control Room Evacuation EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
i
- 1. Control Room evacuation is expected to occur g has already occurred RELATED EALS: TAB Control Room Evacuation 6 l
I O
I
Pn0CJWORK PLAN NO. M40CEDUfWWORK PLAN TITUE: PAGE: 104 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
ATTACHMENT 4 UNIT 2 CONTROL ROOM EVACUATION
6.7 CONDITION
Control Room Evacuation and control of shutdown systems not established in 15 minutes.
1 i
EMERGENCY CLASSIFICATION: {
Site Area Emergency MODES 1-4 CRITERIA:
- 1. Control Room evacuation has occurred AND control of shutdown systems is not established from local stations within 15 minutes.
(
RELATED EALS: TAB i
Core Damage /ICC 1 Decay Heat Removal 6 Core Melt _
1 i
i 1
)
MOOCJWORK PUW NO. PROCEDUREtWORK PLAN TmL* PAGE: 105 of 128 1003.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 CHANGE: l l
w/ ATTACHMENT 4 UNIT 2 i DECAY HEAT REMOVAL 6.8 ;
CONDITION: )
I Loss of Decay Heat Removal Systems EMERGENCY CLASSIFICATION:
Alert I
MODES 5-6 CRITERIA:
r 1.
Loss of Decay Heat Removal capabilities shall be identified as ANY of the following: L O A. RCS indicates saturated conditions B. Loss of both shutdown cooling trains for >l hr and S/G's not available for decay heat removal (NA if Fuel Transfer Canal >23 ft)
C. HPSI injection required for cooling the core RELATED EALS: TAB Spent Fuel Accident 5 Core Damage /ICC 1 Radiological Effluent 6 5 ,
Loss of or Challenge to 3 Fission Product Barriers 1 l High Radiation / Airborne 5 Core Melt 1 i
O :
I
i MIOCJWORK PUW NO. N MWORK M.AN TmE: PAGE: 106 of128 1003.010 EMERGENCY ACTION LEVEL Cf ASSIFICATION REV: 32 ;
CHANGE:
p <
- I C) ATTACHMENT 4 UNIT 2 DECAY HEAT REMOVAL 6.9 i
CONDITION: ,
Loss of Both S/Gs as a Heat Removal Method i
EMERGENCY CLASSIFICATION:
?
Site Area Emergency
?
MODES 1-4 l CRITERIA: ,
t
- 1. ALL of the following conditione exist:
3
) A. S/G level in BOTH S/Gs's is <70" AND B. ECCS Vent System is utilized i ,
1 l
l RELATED EALS: TAB Containment Radiation 1 RCS Leakage 2 Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 t
P r
l PROCMORK PLAN NO. PROCEDURE 4 WORK PLAN TITLE: PAGE: 107 of128 ;
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
(
V ATTACHMENT 4 UNIT 2
. LOSS OF CONTROL ROOM ANNUNCIATORS 6.10 CONDITION:
Loss of Control Room Annunciators EMERGENCY CLASSIFICATION:
Alert MODES ALL CRITERIA: '
- 1. Loss of BOTE AC and DC power to 9 or more of the Control Room Annunciator Panels. 1 l I f
RELATED EALS: TAB .
Loss of Control Room Annunciators with a Transient in progress 6 Electrical Power 4 T
O l
1 l
1
PROCJWORK PUW NO. PwmmWORK PLAN Tm2: PAGE: 108 of f 28 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 !
CHANGE:
Os ATTACHMENT 4 UNIT 2 -
LOSS OF CONTROL ROOM ANNUNCIATORS 6.11 L
CONDITION:
Loss of Control Room Annunciators with a Transient in Progress ,
EMERGENCY CLASSIFICATION:
I Site Area Emergency MODES ALL CRITERIA:
- 1. Loss of BOTE AC and DC power to 9 or more of the Control Room Annunciator Panels:
AND l l ,
- 2. A plant transient is initiated OR in progress. (See Section 4.18 of this procedure for the definition of a Plant Transient.
RELATED EALS: TAB Electrical Power 4 L
O .
PROCJWORK PUW NO. PROCEDUREAMORK PLAN TITLE: PAGE: 109 of 128 1903.010 EMERGENCY ACTION LEVEL Ct.ASSlFICATION REV: 32 CHANGE:
rm ATTACHMENT 4 UNIT 2 SECURITY THREAT
7.1 CONDITION
Security threat onsite but outside the Protected Area Security Fence (e.g.
attempted entry or sabotage which has been stopped outside the security fence).
L i
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
Same as the condition stated above.
l'M U
l RELATED EALS: TAB Security Threat 7 t
l r
i f
l t
O
PROCAWORK PLAN NO. Pwmm/ WORK PLAN TITub PAGE: 110 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE: ;
c
~l
( ATTACHMENT 4 UNIT 2 SECURITY THREAT 7.2 ,
CONDITION:
Ongoing security threat within the Protected Area Security Fence but outside of plant buildings.
EMERGENCY CIASSIFICATION:
Alert MODES All .
i l
CRITERIA: !
Same as the Condition stated above. [
l REIATED EALS: TAB Security Threat 7 Fire or Explosion 7 i
I
PROCAICRK PLAN NO. PROCEDUREMmRK PLAM TITLE: PAGE: 111 Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
7,-
'd ATTACHMENT 4 UNIT 2 SECURITY THREAT )
7.3 CONDITION
Ongoing security threat within plant buildings but not within the Control Room or vital areas.
EMERGENCY CLASSIFICATION: ,
Site Area Emergency MODES All CRITERIA:
Same as the Condition stated above.
I RELATED EALS: TAB Security Threat 7 Fire / Explosion 7 4
9 V l .
Mt0CAWOftK PLAN NO. - Nm4 WORK PLAN TmE: PAGE: 112 Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REY: 32 l
~x !
ATTACHMENT 4 UNIT 2 SECURITY THREAT 1
7.4 CONDITION
Ongoing security threat within the Control Room or vital areas.
EMERGENCY CLASSIFICATION:
. r General Emergency MODES All CRITERIA:
Same as the condition stated above.
[
l RELATED EALS: TAB None D
b
PROCAWORK MAN NO, Mt0CEDURE/ WORK PLAN Tm.E: PAGE: 113 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
ATTACHMENT 4 UNIT 2 FIRE / EXPLOSION
7.5 CONDITION
Fire or Explosion Onsite EMERGENCY CIASSIFICATION:
Notification of Unusual Event ;
MODES All CRITERIA:
L
- 1. Fire within the Protected Area Security Fence which is not extinguished within 10 minutes.
OR f
- 2. Explosion causing facility damage. ,
RELATED EALS: TAB l
Fire or Explosion 7 Security Threat 7 i
l l
O l
PRocswCRK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 114 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
/s ATTACHMENT 4 UNIT 2 FIRE / EXPLOSION
7.6 CONDITION
Fire or Explosion Onsite affecting One Train of ESF Systems EMERGENCY CIASSIFICATION: .
Alert MODES All CRITERIA:
- 1. Fire or explosion onsite O 2.
^""
A potential or actual loss of a single train of ANY ESF system as a result of the fire or explosion.
REIATED EALS: TAB Fire or Explosion 7 ,
Communications, Dose Assessment 6 Control Room Evacuation 6 ee-s -, - - - - , , ,
PnOCMORK PLAN NO. PNutfMORK PLAN Tm.E: PAGE: 115 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
(m ,
ATTACHMENT 4 UNIT 2 FIRE / EXPLOSION
7.7 CONDITION
Fire or Explosion Onsite affecting Both Trains of ESF Systems EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Fire or explosion onsite AND
- 2. A potential or actual loss of Both trains of ANY ESF system as a result of the fire or explosion.
RELATED EALS: TAB Communications, Dose Assessment 6 Control Room Evacuation 6 !
I i
h
PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 116 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 J
CHANGE:
ATTACIOfENT 4 UNIT 2 OTHER HAZARDS 7.8 l CONDITION:
Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine failure, Toxic or Flammable Gas EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. ANY cf the following A. Aircraft crash onsite B. Unusual Aircraft activity over the facility C. Train derailment onsite D. Turbine rotating component failure causing rapid plant shutdown E. Toxic or flammable gas release which limits or restricte access to areas required for security or safe operation of the plant.
RELATED EALS: TAB Fire or Explosion 7 Security Threat 7 MSIS 3 Other Hazards 7 O
U
PROC > work PUW NO. PROCEDURE / WORK PLAN Tm.E: PAGE: 117 Of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 ,
CHANGE:
- rh ATTACHMENT 4 UNIT 2 OTHER HAZARDS
7.9 CONDITION
Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ESF Systems i
EMERGENCY CIASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following A. Aircraft crash onsite B. Missiles / Projectiles from any source C. Toxic or flammable gas release AND
- 2. A potential OR actual loss of a single train of ANY ESF system REIATED EALS: TAB Fire or Explosion 7 Other Hazards 7 O
T PROCAMORK PLAN NO. PHOCEDURE/ WORK PLAN TITLE: PAGE: 118of128 l 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
(V ATTACHMENT 4 UNIT 2 OTHER HAZARDS I 7.10 CONDITION:
Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Redundant EST Trains ,
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA: ,
- 1. ANY of the following A. Aircraft crash onsite ;
B. Missiles / Projectiles from any source C. Toxic or flammable gas release
- AND i
1 i
i
)
RELATED EALS: TAB l Fire or Explosion 7 i i
l O
PROCAUORK PUW NO. PROCEDulupWORK PUW Tm2. PAGE: 119 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
g w.
(j ATTACHMENT 4 UNIT 2 NATURAL PHENOMENON
8.1 CONDITION
Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake ,
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. ANY of the following A. Tornado observed on the ground within the Exclusion Area B. Flood - Lake level 3340' elev. and rising with forecasted lake level 1350' elev.
C. Low Level - Lake level $337' AND forecasted by U.S. Army Corp of Eng1neers to reach 335' i D. Earthquake - VERIFIED earthquake of magnitude of .Olg RELATED EALS: TAB Natural Phenomenon 8 O
l l
1
PROCJWORK Pl.AN No. PROCEDUMUWORK PLAN TTruE: PAGE: 120 of128 1903.010 EMERGENCY ACTION LEVEL Ct.ASSIFICATION REV: 32 CHANDE:
AMACN 4 UNIT 2 NATURAL PHENOMENON 8.2 ,
CONDITION: 1 i
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake ;
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following i A. Tornado striking vital facility structures (e.g. housing ES related equipment) ,
B. High Winds - Sustained winds of 272 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments).
C. Flood - Flood waters 2350' and are forecasted by U.S. Army Corp of Engineers to reach or exceed 354' D. Low Level - Lake level $335' elevation E. Earthquake - VERIFIED Earthquake of magnitude 1.lg RELATED EALS: TAB Natural Phenomenon 8 Loss of or challenge to all 3 Fission Product Barriers 1 O
PROCAUCIWC PUW NO. PROCEDURE 4 WORK PLAN TITLE: PAGE: 121 of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE.-
C ATTACHMENT 4 ,
UNIT 2 NATURAL PHENOMENON 8.3 CONDITION:
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGZNCY CLASSIFICATION:
l Site Area Emergency MODES ~1-4 CRITERIA:
- 1. ANY of the following A. High Winds - Sustained winds of >80 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments). >
B. Flood - Flood Water Level is >361' elev.
/ C. Low Level - Lake level $335' elev. and Emergency Cooling Pond not available.
D. VERIFIED Earthquake >0.2g E. Tornado, high wind, flood, low lake level or earthquake resulting in the potential or actual loss of BOTH trains of ANY ESF system.
RELATED EALS: TAB Loss of or challenge to all 3 Fission Product Barriers 1
PROCAWORK PLAN NO. MtOCEDURE4 WORK PLAN TITUh PAGE: 122 of 128 1003.010 EMERGENCY ACTION LEVEL CL.ASSIFICATION REV: 32 CHANGE:
O U ATTACHMENT 4 UNIT 2 MISCELLANEOUS-9.1 CONDITION:
Transport of a Contaminated Injured Individual to an Offsite Medical Facility EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. A Personnel injury has occurred and the following conditions exist:
A. The injured individual is radiologically contaminated.
AND B. The injured individual is transported to an offsite Medical Facility.
RELATED EALS: TAB None i
8,
PROCJWCWIK PLAN NO. PROCEDURFJWORK PLAN Tm.E: PAGE: 123 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REv: 32 CHANGE:
(
() - ATTACHMENT 4 UNIT 2 MISCELLANEOUS
9.2 CONDITION
Other plant conditions exist that warrant increased awareness on the part of the operating staff and state and/or local offsite authorities or require plant shutdown under technical specification requirements or involve other than normal controlled shutdown.
l EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
An event has occurred and the following conditions exist:
- 1. This event is not covered by any other EAL AND
- 2. This ever. Las not challenge or cause the loss of a fission product barrier AND
- 3. In the judgement of the SS/TSC Director / EOF Director this event reauires an increased awareness by the ANO Staff and offsite authorities.
RELATED EALS: TN3 RCS Activity 1 RCS Leakage 2 Primary to Secondary Leak 3 Radiological Effluents 5 T.S. L.C.O.'s 6 Loss of Indications / Communications / Dose Assessment 6 e
^
1
! l Pn0CAWORK PLAN NO. PROCEDURE / WORK PLAN Tm.E: PAGE: 124 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
d ATTACHMENT 4 UNIT 2 MISCELIXiEOUS
9.3 CONDITION
Other plant conditions exist that warrant precautionary activation of the Technical Support Center and placing the near-site Emergency Operations Facility and other key emergency personnel on standby.
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
The following conditions must exist i ,
- 1. This event is not covered by any other EAL AND
- 2. This event must either challenge or cause the loss of a fission product barrier.
RELATED EALS: TAB RCS Activity 1 RCS Leakage 2 Primary to Secondary Leak 3 Radiological Effluents 5 Decay Heat Removal 6
\
PROCJWORK M.AN NO. MtOCEDUREMORK PUW TITLE: PAGE: 125 of 128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REv: 32 CHANGE:
[
V ATTACHMENT 4 UNIT 2 MISCELLANEOUS
9.4 CONDITION
Other plant conditions exist that warrant activation of emergency response facilities and monitoring teams or a precautionary notification to the public.near the site.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
The following conditions must exist
- 1. This event is not covered by any other EAL AND
- 2. This event may cause ANY of the following:
A. Challenge to two fission product barriers B. Failure of one fission product barrier and a challenge to another C. Failure of 2 fission product barriers RELATED EALS: TAB Core Damage /ICC 1 Containment Radiation 1 Decay Heat Removal 6 Radiological Effluents 5 RCS Leakage 2 Primary to Secondary Leak 3
'v
PROCJWORK PLAN NO. PROCEDufEWORK PLAN Tm.E: PAGE: 126Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 32 CHANGE:
i
'\ ATTACHMENT 4 UNIT 2 MISCELLANEOUS
9.5 CONDITION
Plant Conditions Exist That Make Release of Large Amounts of Radioactivity Possible EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
The following conditions must exist
- 1. This event is not covered by any other EAL AND
- 2. Events have occurred that make a release of large amounts of radioactivity in a short period of time possible.
RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation 1 Radiological Effluents 5
PROCJWORK M.AN NO. MmM PLAN TITUE: PAGE: 127 Of128 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 32 5
CHANGE: f N
[ ATTACHMENT 5 UNIT 1 l l
CONTAINMENT RADIATION EAL PLOT l 1E4 4 !
2-1EG - i 4 A --
2.
OENERAL EN .
Rkm 4-2-
1E @ !
4-2 1E432 4 A _ _ .
g 2- -
AREA 0 2 4 6 8 10 12 14 16 18 20 22 34 ftE N HOLR
{
l INSTRUCTIONS I. If the plant has been operating at 100% power for the past 30 days:
A. Determine the Containment radiation level from RE-8060 or RE-8061.
B. Determine the plant's time af ter shutdown in hours. ;
C. Find the point on the graph above where these two values intersect.
D. The criteria for Site Area Emergency is met if the point is located between the two curves. ,
E. The criteria for General Emergency is met if the point is located above the upper curve.
OR II. If the plant has NOT been operating aT 100% power for the past 30 days:
A. Divide 100 by the representative power for the past 30 days.
(For example, if the plant has been operating at 50% power for the last 30 days, divide 100 by 50.)
- 1. The value used for " representative power" should be a best estimate.
Absolute precision is not required. ;
B. Determine the containment radiation level from RE-8060 or RE-8061. !
- c. Multiply the value found in B by the value in A.
D. Determine the plant's time after shutdown in hours.
E. Find the point on the graph above where these two values intersect.
F. The criteria for Site Area Emergency is met if the point is located between the two curves.
G. The criteria for General Emergency is met if the point is located above the upper curve, i
\ l
. -. ~ _ __ . . _ _ _ _ .
1 PROCAWofut PUW NO. PAMWEAWORK PLAN TEL PAGE: 128 Of 128 1903.010 EMERGENCY ACTIO1 LEVEL CLASSIFICATION REV: 32 CHANGE:
f
% ATTACHMENT 6 UNIT 2 CONTAINMENT RADIATION EALPLOT -
1E+0B !
4 ,
2-1E+05, ,
4l f 1E+04 l
RMR 4-2-
1E+03 l
4 2
1E@
4 l s 4 g
2- AREA ,
0 2 4 6 8 10 12 14 16 18 20 22 14 :
ThE N HO(R
(
l INSTRUCTIONS I. If the plant has been operating at 100% power for the past 30 days:
A. Determine the Containment radiation level from 2RY-8925-1 or 2RY-8925-2.
B. Determine the plant's time after shutdown in hours.
C. Find the point on the graph above where these two values intersect. i D. The criteria for Site Area Emergency is met if the point is located ;
between the two curves. '
E. The criteria for General Emergency is met if the point is located above the upper curve. ;
OR II. If the plant has NOT been operating aT 100% power for the past 30 days:
A. Divide 100 by the representative power for the past 30 days. l (For example, if the plant has been operating at 50% power for the last 30 days, divide 100 by 50.)
- 1. The value used for " representative power" should be a best estimate.
Absolute precision is not required.
B. Determine the Containment radiation level from 2RY-8925-1 or 2RY-8925-2. e
- c. Multiply the value found in B by the value in A.
D. Determine the plant's time after shutdown in hours. ;
E. Find the point on the graph above where these two values intersect.
F. The criteria for Site Area Emergency is met if the point is located between the two curves.
G. The criteria for General Emergency is met if the point is located above the upper curve.
t I
L . _. _ _ _ _ _. . _