ML20097B222
| ML20097B222 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/06/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| References | |
| NUDOCS 9602060343 | |
| Download: ML20097B222 (126) | |
Text
. . _ . _. . . .__
Arkansas Nuclear One - Administrative Senices Document Control Wednesday, January 31,1996 Document Update Notification COPYHOLDER NO: 103 TO: NRC - WASHINGTON ADDRESS: NRC DOCUMENTNO: OP-1903.010 TITLE: EAL CLASSIFICATION REVISIONNO: 33 CHANGENO: AP-33
SUBJECT:
NEW REVISION ANO-1 Docket 50-313 ANO-2 Docket 50-368 Please sign, date, andreturn transmittal in envelopeprovided.
Signature Date OGC086 fSA"A88$R!!888s13PDR bo46 y y
L
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUOLEAR ONE 61 of 77 A
U TITLE: EMERGENCY ACTION LEVEL CLASSIFICATION PROC / WORK PLAN NO. REV.
1903.010 33 EXP.DATE SAFETY-RELATED N/A SYEs ONO
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27 63 99 j 28 64 100 29 65 101 30 66 102 31 67 103 32 68 104 33 69 105 34 70 106 35 71 107 36 72 108 FORM TITLE: FORM NO. REV.
LIST OF AFFECTED PAGES 1000.006A 43 PC-1 s
PRoCJwoRK PLAN NO. PpntwruutPJWORK PLAN mu: PAGE: 1 Of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
C 1.0 PURPOSE This procedure establishes criteria for detection and classification of plant events into the four standard Emergency classes.
2.0 SCOPE This procedure is applicable to Units 1 and 2 in all modes; it does not include specific plant casualty procedures or systems operations requirements, but rather provides administrative processes only.
3.0 REFERENCES
3.1 REFERENCES
USED IN PROCEDURE PREPARATION:
3.1.1 PWO Emergency Plan 3.1.2 - 4L EAL Bases Document 3.1.3 'UREG-0654/ FEMA-REP-1, Rev. 1 3.1.4 , CFR 50 g 3.1.5 %.
nch Position on Acceptable Deviations to Appendix 1
- t. NJ :.. . i'54/ FEMA-REP-1, July 11, 1994
3.2 REFERENCES
L % IN CONAS CTION WITH THIS PROCEDURE:
3.2.1 100 iCf, " Cart tion Reporting and Corrective Actions" 3.2.2 1903.0.. "Emergu'ay Response / Notifications" 3.2.3 1903.054, "Etacten,y Response Facilfty - Control Room" 3.2.4 1903 = 665, "uc agency Response Facility - Technical Support Center (TSC) "
3.2.5 1903.066, " Emergency Response Facility - Operational Support Center (OSC)"
3.2.6 1903.067, " Emergency Response Facility - Emergency Operations Facility (EOF)"
3.2.7 1203.025. " Natural Emergencies" 3.2.8 2203.008, "itatural Dmergencies" 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 Measurement" 3.2.12 2304.058, " Peak Shock Recorder Surveillance" 3.2.13 1904.002, "Offsite Dose Projections-RDACS Method" 3.2.14 1904.004, " Estimating Airborne Release Rates" 3.2.15
/) NRC Position Paper on " Timeliness of Classification of Emergency Conditions" dated August 17, 1995 t
I PnocEculWWomK PLANTrfLE: PAGE: 2 Of 124 PnocJwomKPuw No.
REY: 33 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANoE:
O 3.3 RELATED ANO PROCEDURES:
1043.042, " Response to Security Contingencies" 3.3.1 3.3.2 1502.004, Attachment H 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" i
3.3.7 1903.043, " Duties of the Dnergency Radiation Team" l 3.4 REGUIATORY CORRESPONDENCE CONTAINING NRC COMMITMENTS WHICH ARE IMPLEMENTED IN THIS PROCEDURE INCLUDE:
3.4.1 OCAN068708 3.4.2 OCNA068807 A. Section 4.17 B. Attachment 3 C. Attachment 4 ,
I 3.4.30 OCAN068320 A. Section 4.15 ,
t 3.4.40 0CAN108213 A. 3.2.2 B. 4.11 C. 6.1.4 3.4.51 OCAN088308 A. 5.0 B. 6.1 4.0 DEFINITIONS 4.1 Courtesy call - A notification to the Arkansas Department of Health 1 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.
I 4.2 Emergency Action Level - Alarms, instrument readings or visual j sightings that 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 4 Alert l Site Area Emergency )
% General Emergency l l
1
l PROCJWORK PLAN NO. PROCEDURE / WORK PLAN Tm.E: PAGE: 3 Of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 l
CHANGE: i l '4.2.1 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 response or monitoring are expected unless further degradation of safety systems occurs.
l 4.2.2 Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA l I
Protective Action Guideline exposure levels.
~
I 4.2.3 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.
l 4.2.4 General Emergency - Events are in progress or have occurred I which involve actual or imminent substantial core j 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.
l 4.3 Emergency Direction and Control - Overall direction of facility
[~s' response which must include the non-delegable responsibilities for the A 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 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 Shif t Superintendent retains responsibility for the Control Room and plant systems operation.
! 4.4 Emergency Operations Facility (EOF) - A nearsite emergency response facility located approximately 0.65 miles northeast of the reactor buildings (the ANO Training Center). 1 I
4.5 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.
4.6 Emergency Response Organization (ERO) - The organization which is composed of the Initial Response Staff (IRS ) , the EOF staf f, 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.
4.7 EPA Protective Action Guideline (PAG) Exposure Levels - The projected dose to reference man, or other defined individual, from an unplanned release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended (i.e., 1 Rem TEDE or 5 Rem
')
,/
Child Thyroid (CDE)).
4.8 Exclusion Area Boundary - That area surrounding ANO within a minimum radius of 0.65 miles of the reactor buildings and controlled to the extent necessary by Entergy Operations during an emergency.
ppemMWORK PLAN TTTLE: PAGE: 4 Of 124 MtOCJWORK PLAN NO.
REV: 33 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION CHANGE:
Q Vl 4.9 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.
4.10 Normal Makeup (NU) Capacity - Normal MU capacity is defined as the maximum expected water addition to the RCS through the MU line with the letdown line isolated. This amount will vary with RC pressure.
! 4.11 Offsite - Those areas not covered by Section 4.12.
I 4.12 onsite - The area within the Exclusion Area Boundary.
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 l Nuclear Chendstry Emergency Medical Support 1 Fire Fighting Support l The OSC also serves as the briefing area for repair and damage control teams and is located in the Maintenance Facility.
l 4.14 Technical Support Center (TSC) - The location within the ANO
(* g 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.
l 4.15 FISSION PRODUCT BARRIER FAILURE ,
l 4.15.1 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.
- 3. Containment Radiation Levels correspond to a Site Area Emergency from Containment Radiation EAL Plot (Attachment 5).
- 4. Engineering assessment of core damage indicates
> 1% failed fuel.
B. Unit 2 - Greater than 1% failed fuel as indicated by ANY of the following:
- 1. Nuclear Chemistry analysis of RCS sample yields > ,
O 378 uCi/gm specific I-131. l
PROCEDURE / WORK PLAN Tm.E: PAGE: 5 of 124 PROCJWORK PLAN NO.
M: 33 1903.010 EMER'lENCY ACTION LEVEL Ct.ASSlFICATION CHANGE:
rs Containment Radiation Levels correspond to a Site (s,) 2.
Area Emergency from Containment Radiation EAL Plot (Attachment 6).
- 3. Engineering assessment of core damage indicates
> 1% failed fuel.
4.15.2 RCS Boundary Failure 1
A. Unit 1 - RCS leakage greater than normal makeup capacity (50 gpm) .
B. Unit 2 - RCS leakage greater than 44 gpm (capacity of a single Charging Pump).
! 4.15.3 Containment Integrity Failure l
A. Abnormally high Containment High Range Radiation l Monitor readings (RE-8060 or 8061 for Unit is 2RY- ;
8925-1 or 2RY-8925-2 for Unit 2) 3nd indications of I radiological effluents outside of the Reactor Building l that are not attributable to any other source. l l
B. In the judgement of the SS/TSC Director / EOF Director, 1 a breach of the Reactor Building exists. The variety !
of possible Reactor Building integrity f ailure scenarios precludes the development of an all inclusive list. In the absence of the conditions
/"')
(f described in 4.15.3.A above, the SS/TSC Director / EOF j Director must judge the potential for an offsite release to occur based on a current status of Reactor Building isolation systems and structural integrity.
I 4.15.4 Inability to Idonitor a Fiesion Product Barrier A. Following the failure of two fission product barriers, the inability to monitor the third barrier is to be regarded as equivalent to a failure of that barrier.
l 4.16 FISSION PRODUCT BARRIER CHALLENGE )
I 4.16.1 Challenge to Fuel Cladding: any event or condition which in j the judgement of the SS/TSC Director / EOF Director presents the potential for greater than 1% fuel cladding failure; for example:
A. RCS temperature and pressure indicates superheated conditions.
B. Indications of the core being uncovered.
C. Exceeding safety limits (e.g. DNBR or Local Power Distribution)
I PROCJWORK PLAN NO. PROCEDUREMORK PUW Tm.E: PAGE: 6 of 134 REY: 33 1903 010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE:
4.16.2 Challence to Rcs Boundary: any event or condition which, in l the judgement of the SS/TSC Director / EOF Director could result in RCS leakage in excess of normal makeup capacity (i.e., 50 gpm for Unit 1 or 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. limits but less than normal ,
make.up capacity; (50 gpm) for Unit 1 or (44 gpm) for Unit 2.
I 4.16.3 challenge to containment Building Integrity: any event or condition which in the judgement of the SS/TSC Director /
EOF Director significantly increases the potential for failure of containment integrity; for example: i l
A. Containment pressure > Reactor Building spray 1 actuation setpoint and increasing with no available RB )
spray or cooling. J
/"'N B. Hydrogen concentrations in containment > 3.5%.
b C. Occurrence of system or component failure which degrades the capability to maintain containment integrity as defined by Tech Specs. l l 4.17 PLANT TRANSIENT I 4.17.1 Any unplanned reactor trip from criticality.
l 4.17.2 A planned reactor trip in which the expected post-trip response did not occur.
I 4.17.3 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.
4.17.4 Any turbine-generator power change in excess of 100 MWe in l l
less than one (1) minute other than a momentary spike due to a grid disturbance or a manually initiated runback. 4 4.17.5 Any unplanned main turbine or main feedwater pump turbine l trip which results in a significant plant transient (change in excess of 100 MWe).
5.0 RESPONSIBILITY AND AUTHORITY 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) .
Mt0CAWOfDC PLAN NO. Pane semWORK PLAN TME: PAGE: 7 Of 124 1903.010 EMER ENCY ACTION LEVEL CLASSIFICATION
- 33 CHANGE:
p, k,
m 5.2 The Control Room Supervisor (CRS) will assume Deergency 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 amergency class declaration, as described in Attachments 3 and 4, shall immediately notify the person with current responsibility for Dnergency Direction and Control (i.e. SS/TSC Director / EOF Director) .
6.0 INSTRUCTIONS ,
l NOTE On emergencies that effect both units such as earthquakes, l tornado's, etc., the unit with the highest Emergency Action l Level Classification should be the one that is declaring the emergency.
6.1 CLASSIFYING EMERGENCIES: i i
NOST l NRC guidelines recommend that once indications are available to l ANO staff that an EAL has been exceeded, a 15 minute goal is a reasonable period of time for assessing and classifying an emergency 6.1.1 When indications of abnormal occurrences are received by f-~s the Control Room staff, the SS/TSC Director / EOF Director
(- ') shall:
A. Verify the indications of the off-normal event or reported sighting.
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.
C. Compare the abnormal conditions with those listed in the "Index Of Dmergency Action Levels" (Blue Tabs -
Unit 1; Green Tabs - Unit 2).
D. Turn to the appropriate tab which corresponds to the condition picked from the Index of EALs.
NOTE l Unit 1 EALs - Blue Tabs !
Unit 2 EALs - Green Tabs (
I l
E. Assess the information available from valid )
indications or reports, then: (
l
- 1. Compare information to criteria given for EAL, I
/N 2. Review any Related EALs to determine if the
( ,) abnormal conditions meet those criteria, and
pen *Mm84 WORK PLAN TmE: PAGE: 8 Of 124 PROCAWOM PulN NO.
RN 33' 1903.019 EMERGENCY ACTION LEVEL CLASSIFICATION
' CHANGE:
- 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.
NOTE 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 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 EALs, then refer to the Miscellaneous Tab and using appropriate judgement, determine if the plant status j varrants an emergency declaration.
6.1.2 Due to the speed in which events sometimes progress and the duty of the plant operators to take inanediate 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 made) with a brief description of events and the current plant status provided via form 1903.011Z. Subsequent activation of response organizations should be based upon the current plant conditions.
6.1.3 If no emergency declaration is apparently necessary, then refer to procedure 1903.011, " Emergency Response / Notifications", Section 6.3 to determine if a Courtesy Call to the Arkansas Department of Health is required.
6.1.4 Upon declaration of an emergency classification implement procedure, 1903.011, " Emergency Response Notifications", to ensure that isunediate notification requirements are met and .
the proper Emergency Plan response is taken.
6.1.5 Upgrade the emergency classification if plant conditions degrade per steps 6.1.1.A through F.
6.1.6 Downgrade the emergency classification when plant conditions have improved and step 6.2 is applicable.
6.2 DOWNGRADING THE EMERGENCY CLASSIFICATION: !
6.2.1 Assess the current plant conditions, then perform the following:
A. Compare the abnormal conditions with those listed in O- the "Index of Emergency Action Levels" (Blue Tabs -
Unit 1; Green Tabs - Unit 2) 1
d MtOCJWORK PUW NO. PROCEDUREMORK PLAN TITLE: PAGE: 9 of 124 1903 010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
s
( / B. Turn to the appropriate tab which corresponds to the condition picked from the Index Of EALs. ,
l NOTE ,
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.
Obtain concurrence from NRC and State officials that 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 Kiscellaneous Tab and using appropriate judgement, determine if the plant status warrants downgrading the emergency classification.
6.2.2 Perform notifications to downgrade the emergency 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.
\s_ 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.
6.3 TERMINATING THE EMERGENCY:
6.3.1 Compare the existing plant conditions with the following:
A. Plant conditions no longer meet the emergency action level criteria AND it appears unlikely that current conditions will degrade further requiring reinstitution of an emergency classification.
B. 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 the plant has been placed in the appropriate operational mode.
E. All required notifications have been completed.
F. NRC and State officials are in agreement that tennination or transition to the recovery phase is O
appropriate (if their emergency response organizations have been activated as a result of this event).
PROCEDUREMORK PUW mu: PAGE: 10 of124
- PRoCMORK PLAN NO.
REY: 33
! 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION CHANGE-i l \
- 6.3.2 If the conditions of 6.3.1 A-F are met, terminate the emergency or proceed to the recovery phase.
7.0 ATTACIDENTS 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 Emergency 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 i
O O
PROCJWORK PLAN NO. MtOCEDUREMORK PLAN TmK: PAGE: 11 Of 124 REV: 38 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION CHANGE:
(
ATTACHMENT 1 C/
UNIT 1 INDEX OF EALS 1.0 PRIMARY SYSTEM EVENTS 1.1 RCS Activity Indicates >0.1% Failed Fue1...........................NUE 1.2 RCS Activity Indicates > 1% Failed Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 1.3 Core Damage Indicated with an Inadequate Core Cooling Condition....SAE 1.4 Containment Radiation Reading which Indicates LOCA and >1% Cladding Fa i l u r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SAE 1.5 Containment Radiation Reading which Indicates LOCA and >50% Fuel Overheat...........................................................GE 1.6 Core Melt..........................................................GE 1.7 Loss of or challenge to all 3 Fission Product Barrier. . . . . . . . . . . . . .GE 2.0 RCS LEAKAGE 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 >1.0% 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 (OV) 3.2 OTSG Tube Leak 3 347 gpm .........................................NUE 3.3 OTSG Tube Leak >10gpm Concurrent with an 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 Release............................................................SAE 4.0 ELECTRICAL POWER FAILURES 4.1 Degraded Power.....................................................NUE 4.2 S t a t i o n Bl a c k o u t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 4.3 Blackout for more than 15 minutes..................................SAE 4.4 Lo s s o f All Vital DC Powe r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 4.5 Loss of All Vital DC Power for more than 15 minutes................SAE 5.0 RADIOLOGICAL EFFLUENTS 5.1 Radiological Effluents 3 05 mrem /hr TEDE or .15 mrem /hr Child l
Thyroid CDE 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 /hr Child l Thyroid CDE at Site Boundary or Liquid Radiological Effluents exceed 10 time s Te ch Sp e c limi t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 5.3 Radiological Effluents 150 mrem /hr TEDE or 150 mrem /hr Child l Thyroid CDE at the Site Boundary...................................SAE 5.4 Radiological Ef fluents 3250 mrem /hr TEDE or 500 mrem /hr Child Thyroid CDE at the Site Boundary...................................GE 5.5 High Radiation / Airborne Levels..................................... ALERT (sd) 5.6 Spent Fuel Accident................................................SAE
PAGE: 12 Of 124 PROCMORK PLAN NO. PROCEDuREMORK PUUd TTTLE:
REV: 33 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE:
. d ATTACHMENT 1 .
UNIT 1 INDEX OF EALS 6.0 SAFETY SYSTEM FUNCTION 6.1 Deviation from T.S. action statements when required to shutdown or l cooldown or deviations pursuant to 10CFR50.54(x)...................NUE 6.2 RPS Failure to Complete an Automatic Tr1p. . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 6.3 RPS Failure to Complete a Manual Trip..............................SAE 6.4 Loss of Dose Assessment Capabilities...............................NUE 6.5 Loss of Communications.............................................NUE 6.6 Los s o f Cont rol Room Annunciato rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 6.7 Loss of Control Room Annunciators with Transient in Progress. . . . . . .SAE 6.8 Cont r ol Room Eva cua tio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 6.9 Control Room Evacuation and control of shutdown systems not established in 15 minutes..........................................SAE 6.10 Lo s s o f De ca y He at Removal S ys tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT ;
6.11 Degraded Hot Shutdown capability...................................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 Ongoing Security Threat Within Plant Building......................SAE p 7.3 Ongoing Security Threat Within CR or Vital Area. . . . . . . . . . . . . . . . . . . .GE 4
(" 7.4 7.5 Fi r e o r Expl o s i on Ons i t e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NUE 7.6 Fire or Explosion Onsite Af fecting 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 Flanunable Gas Release. . . . . . . . . . . . . . . . . . . .NUE 7.9 Aircraft crash, Missiles, Toxic or Flammable Gas Affecting one T r ain o f ANY ES S ys t ems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 7.10 Aircraft 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...........NUE 8.2 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Ea rth qu a k e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 8.3 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, 4 E a r t h qu a k e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S AE 9.0 MISCELLANEOUS EVENTS 9.1 Plant Conditions Exist Which Require an Increased Awareness by Operations Staff and State and/or Local Authorities................NUE 9.2 Plant Conditions Exist that Warrant Activation of the TSC. . . . . . . . . . ALERT 9.3 Plant Conditions Exist that Warrant Activation of the Emergency Re s p o n s e Fa cili t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S AE 9.4 Plant Conditions Exist That Make Release of Large Amount of Ra di o a c t ivi ty Po s s ibl e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . GE
PRoCJWORK PLAN NO. PROCEDURE / WORK PLAN TTTLE: PAGE: 13 of134 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 1903.010 CHANGE:
O Q ATTACHMENT 2 UNIT 2 INDEX OF EALS 1.0 PRIMARY SYSTEM EVENTS 1.1 RCS Activity Indicates >0.1% Failed Fuel...........................NUE 1.2 RCS Activity Indicates >l.0% Failed Fuel........................... ALERT 1.3 Core Damage Indicated with an Inadequate Core Cooling Condition....SAE 1.4 Containment Radiation Indicates LOCA and >l% Cladding Failure......SAE 1.5 Containment Radiation Indicates LOCA and >50% Fuel Overheat. . . . . . . .GE i 1.6 Core Melt with Containment Integrity Lost or Challenged. . . . . . . . . . . .GE l 1.7 Loss of or challenge to all 3 Fission Product Barriers.............GE I l
2.0 RCS LEAKAGE 2.1 RCS Leakage > Tech Spec Limits requiring a Plant S/D or C/D. . . . . . . .NUE 22 RC S Le a k a g e > 4 4 gpm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . AL ERT 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 3.3 S/G Tube Leak >10gpm with an ongoing Steam Release. . . . . . . . . . . . . . . . . ALERT 3.4 S/G Tube Rupture >44 gpm With an Ongoing Steam Release and RCS Activity > 1.0 pCi/gm..............................................SAE G
4.0 ELECTRICAL POWER FAILURES 4.1 Degraded Power.....................................................NUE 4.2 S t a ti o n Bl a c k o u t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 l 5.1 Radiological Effluents 3 05 mrem /hr TEDE or .15 Child Thyroid CDE at Site Boundary or Liquid Radiological Effluents exceed Tech Spec. Limits..................................................NUE l 5.2 Radiological Effluents 3 5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid CDE at Site Boundary or Liquid Radiological Effluents exceed 10 time s Te ch . Spec . Limit s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 5.3 Radiological Effluents 250 mrem /hr TEDE or 150 mrem /hr child
[
Thyroid CDE at the Site Boundary...................................SAE l 5.4 Radiological Effluents 3250 mrem /hr TEDE or 500 mrem /hr Child Thyroid CDE at the Site Boundary...................................GE 5.5 High Radiation / Airborne Levels..................................... ALERT 5.6 Spent Fuel Accident................................................SAE l l
\
l 10 G ,
1 l
i PROCJWOfut PLAN NO. PROCEDUREWWOfut PLAN TTTLE: PAGE: 14 Of 124 REV: 33 1903.010 EMEIMENCY ACTION LEVEL CLASSIFICATION CHANGE:
ATTACIOGDIT 2 UNIT 2 INDEX OF EALS l
6.0 SAFETY SYSTEM FUNCTION l l
Deviation from T.S. action statements when required to shutdown or !
6.1 cooldown or deviations pursuant to 10CFR50. 54 (X) . . . . . . . . . . . . . . . . . . .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 Los s o f Comununi ca tions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NUE 6.6 Cont r ol Room Eva cua tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 6.7 Control Room Evacuation and control of shutdown systems not ;
established in 15 minutes..........................................SAE ,
6.8 Los s o f De cay Hea t Removal Sys tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT -
6.9- Loss of Both S/Gs as a Heat Removal Method.........................SAE 6.10 Los s o f Control Room Annunciato rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 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 J 7.4 Ongoing Security Threat Within CR or Vital Area. . . . . . . . . . . . . . . . . . . .GE :
7.5 Fi re o r Expl o s ion Ons i t e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NUE J 7.6 Fire or Explosion Onsite Affecting One Train of ESF Systems. . . . . . . . ALERT 7.7 Fire or Explosion Onsite Af fecting Both Trains of ESF Systems. . . . . .SAE 7.8 Aircraft crash, Unusual Aircraft Activity, Train Derailment, Turbine Failure, Toxic or Flamable Gas . . . . . . . . . . . . . . . . . . . . . . . . . . . .NUE 7.9 - Aircraft Crash, . Missiles, Toxic or Flasunable Gas Affecting One .
^
T r a i n o f ES F S ys t ems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT
-7.10 Aircraft Crash, Missiles, Toxic or Fl= =mble Gas Affecting Both i T r a i n s o f ES F S ys t ems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SAE j 8.O NATURAL EVENTS 8.1 Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake...........NUE l 8.2 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Ea r t h qua k e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ALERT 8.3 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Ea r t h qu a k e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S AE l
9.0 MISCELLANEOUS EVENTS 9.1 Plant Conditions Exist Which Require an Increased Awareness by Operations Staff and State and/or Local Authorities................NUE 9.2 Plant Conditions Exist that Warrant Activation of the TSC. . . . . . . . . . ALERT 9.3 Plant Conditions Exist that Warrant Activation of the Emergency Response Facility..................................................SAE 9.4 Plant Conditions Exist That Make Release of Large Amount of Ra di o a ctivi t y P o s s ible . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . GE O
PaoCJWORK PLAN NO. PROCEDUMUWORK Pt.AN TITLE: PAGE: 15 of 124 REV: 33 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANGE.
,n.
/ ATTACHMENT 3 l UNIT 1 <
I PRIMARY SYSTEM EVENTS l 1.1 CONDITION:
RCS Activity indicates >0.1% failed fuel EMERGENCY CLASSIFICATION:
Notification of 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 I 13' O,,3
[] B. Failed Fuel Iodine monitor (RE 1237) indicates >3.3 x 10' CPM 5
%/
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 l
I v
l l
l l
Pnoc.MORK PUW NO. PROCEDUfEWORK PLAN MLE: PAoE: 16 of 124 EMEREENCY ACTION LEVEL CLAS21FICATION
" 33 1903.010 CHANGE.
u ATTACHMENT 3~
(/ UNIT 1 PRIMARY SYSTEM EVENTS 1.2 l
CONDITION:
RCS Activity indicates >1% failed fuel EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Greater than it failed fuel is indicated by Either of the following:
A. Nuclear Chemistry analysis of RCS sample yields >400 pCi/gm specific I525 0E 5
B. Failed Fuel Iodine monitor (RE 1237) indicates >B.2 x 10 CPM.
J 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 1 High Radiation / Airborne Levels 5 Initiation of Plant S/D or C/D due to T.S. L.C.O. 6 i V
PRocJwoRK PLAN NO. PROCEDUMUWORK PLAN MLE: PAGE: 17 of 124 !
REV: 33 1903.010- EMER2ENCY ACTION LEVEL CLASilFICATION CHANGE f-kj ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS 1.3 l
CONDITION:
Core Damage Indicated with an Inadequate Core Cooling Condition EMERGENCY CIASSIFICATION:
Site Area Emergency MODES All CRITERIA:
1
- 1. Inadequate core cooling capacity exists as evidenced by CETS indicating superheated conditions of Region 3 of Figure 4 of EOP 1202.013.
i AND l (g) e
- 2. Greater than 1% failed fuel is indicated by EITHER of the following:
%./
A. Nuclear Chemistry analysis of RCS sample yields >400 pCi/gm 1
specific I'1 EB B. Failed Fuel Iodine process monitor (RE 1237) indicates >8.2 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
[i i
Pfl0CAWOftK PLAN NO. Pft0CEDUREMf0ftK PLAN TITLE: PAGE: 18 Of 134 i903.010 EMERSENCY ACTION LEVEL CLAS8lFICATION ftEV: 33 CHANGE:
Ch (m) ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.4 CONDITION
d containment Radiation reading which indicates LOCA and >l% 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)
AND
- 2. LOCA occurring within the containment building O RELATED EALS: TAB Containment Radiation indicates LOCA &nd > 50% fuel overheat 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1 Radiological Effluents 5 O
l
__ _. _.~_m . _ . . . . . _.. _____ _ . _ _ _ . _ _ _ . _ _ _ _ .
PftOCJWOftK PLAN NO. PitOCEDUftEMOftK PLAN TITLE: PAGE: 19 of 124 ftEV: 33 4
1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANGE-
' (% ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS l 1.5 i
CONDITION: I Containment Radiation readings which indicate LOCA and >50% fuel overheat EMERGENCY CLASSIFICATION:
General Emergency MODES All l
i CRITERIA:
- 1. Containment Radiation Levels correspond to a General Emergency as determined from the Containment F.adiation EAL Plot (Att 5)
- D
- 2. LOCA occurring within the Containment Building I
RELATED EALS: TAB i
I Loss of or Challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1 l
1 i
O
PROcJwonK PLAN NO. PROCEDURE / WORK Pt.AN Tm.E: PAGE: D of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION
- 33 CHANGE:
ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS 1.6 l
CONDITION: !
l Core Melt EMERGENCY CLASSIFICATION:
General Emergency j i
MODES All l
l CRITERIA:
v i
RELATED EALS: TAB l Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation High/Very High 1 Radiological Effluents 5 O
V
l PROCAWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAoE: 21 of 124 j REv: 33 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANGE:
I
, ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS 1
g 1.7 CONDITION:
Loss of or challenge to all 3 Fission Product Barriers 1
i EMERGENCY CLASSIFICATION: .l General Emergency .
MODES All CRITERIA:
- 1. Either of the following conditions exist:
A. Fuel Cladding Failure (refer to section 4.15.1)
B. Challenge to Fuel Cladding (refer to section 4.16.1)
AND
- 2. Either of the following conditions exist: l A. RCS boundary failure (refer to section 4.15.2)
B. Challenge to RCS boundary (refer to section 4.16.2)
AND l
- 3. Either of the following conditions exist: j 1
A. Containment Integrity failure (refer to section 4.15.3) 1 B. Challenge to Containment Integrity (refer to section 4.16.3)
RELATED EALS: TAB Containment Radiation High/Very High 1 Core Melt 1 Radiological Effluents 5 Natural Events 8 I
l i
l 1
- PnocJwoRK PLAN No. PPnP8'mm PUW TRLE: PAGE: 22 of 124 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION
- 33 CHANGE:
ATTACHMENT 3 4 UNIT 1
, RCS LEAKAGE 2.1 4 CONDITION:
RCS Leakage > Tech. Spec. limits requiring a Plant S/D or C/D i
j 1 EMERGENCY CLASSIFICATION:
i Notification of Unusual Event MODES Above CSD i
CRITERIA:
- 1. RCS Leakage exceeds T.S. 3.1.6 requirements necessitating a Plant S/D or C/D RELATED EALS: TAB RCS Leakage > Normal Makeup Capacity (50 gpm) 2 Initiation of Plant S/D or C/D due to TS LCO 6 OTSG Tube Leak 3
PRoCJWOfDC PUW NO. PROCEDURElWORK PLAN TITLE: PAGE: 23 Of 124 REv: 33 1903 010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANGE:
f~s k 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.
f% i V 2R B. Full or part'ial HPI is needed to maintain the RCS Pressure or l
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 Effluents 5 Core Melt 1 I
O
PnocAsoset M.AN NO. PROCEDUIWWORK PLAN TRLE: PAGE: 24 of 124 "EV: 83 1003.010 EMER!ENCY ACTION LEVEL CLASSIFICATKM CHANGE:
I ATTACHMENT 3 UNIT 1 RCS LEAKAGE j 1
2.3 l
i CONDITION:
RCS Leakage > Normal Makeup Capacity (50 gpm) with >1.0% Failed Fuel Conditions J
l 1
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
( Failed Fuel in the RCS (EAL 1.2)
O NOTE EAL 2.2 RCS Leakage > Normal Makeup Capacity (50 gpm)
EAL 1.2 RCS Activity Indicates >l% failed fuel RELATED EALS: TAB 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 O
~ . . - - . -
PROCJWORK PLAN NO. Pft0CEDURE/WOftK PLAN TITLE: PAGE: 25 of 124 1903.010 EMERIENCY ACTION LEVEL CLAS lFICATION REY: 33 CHANGE f
r ATTACHMENT 3 UNIT 1 RCS LEAKAGE
2.4 CONDITION
RCS Leakage > HPI Capacity EMERGENCY CLASSIFICATION:
Site A.rea 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.
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 f*
PftoCJWORK PLAN NO. PftoCEDURE/ WORK PUW TITLE: PAGE: 26 of 124 REV: 33 1903.010 EMER2ENCY ACTION LEVEL CLASZlFICATION CHANGE:
ATTACHMENT 3 v UNIT 1 SECONDARY SYSTEM EVENTS
3.1 CONDITION
Uncontrolled OTSG Depressurization Resulting in MSLI Actuation EMERG'.NCY CLASSIFICATION:
Notification of Unusual Event l i
MODES Above CSD l
l CRITERIA:
- 1. Any manual or automatic actuation of MSLI due to uncontrolled OTSG depressurization below 600 psig.
l i
RELATED EALS: TAB OTSG Tube Leak 3 Radiological Effluents 5
PetoCAMORK PUUd NO. PROCEDUREMOtK PLAN TITLE: PAGE: 27 of 124 REV: 33 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANGE.
\ .
y) ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.2 CONDITION
OTSG Tube Leakage > .347 gpm EMERGENCY CLASSIFICATION:
l Notification of Unusual Event i
MODES Above CSD '
CRITERIA:
- 1. RCS Leak rate of > .347 gpm, with conincident Main Steam line N-16 alarm (s),
Steam Line High Range RAD Monitors Increase (RI-2681 or 2682) or condenser l off gas process monitor count rate increase or Nuclear Chemistry sample
/, indicating Primary-Secondary tube leak.
k ,
I I
RELATED EALS: TAB OTSG Tube Leak 3 l RCS Leakage 2 O
PROCJWORK PLAN NO. PROCEDUREMORK Pt.AN TITLE: PAGE: 28 of 124 REY: 33 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE:
(
() ATTACEMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.3 CONDITION
OTSG Tube Leakage > 10 gpm concurrent with ongoing steam release 1
EMERGE!;CY CLASSIFICATION:
Alert MODES Above CSD J CRITERIA:
- 1. RCS Leakrate increase of >10 gpm, with coincident Main Steam Line N-16 alarm (s) or condenser off gas process monitor count rate increase, or Steam
(T Line High Range Rad Monitors Increase (RI-2681 or 2682) or Nuclear Chemistry
(_,/ sample indicating Primary-Secondary tube leak.
1 AND l l
- 2. ANY of the following occur: l 1
i A. Loss of offsite power B. Steam release to the environment indico v! by:
- 1. Main Steam Safety Valve (s) lift
- 2. Use the ADV(s) to control affected .236 pressure
- 3. P7A running with steam from affected OTSG
- 4. Steam line break outside containment j l
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 V
PROCJWORK PLAN NO. PROCEDUREMORK PUW Tm.E: PAGE: 29 of 124 REV: 33 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANGE:
/* %
Q ATTACHMENT.3 UNIT 1 SECONDARY SYSTEM EVENTS CONDITION:
OTSG Tube Rupture with primary to secondary leakage > normal makeup capacity (50 gpm) with ongoing steam release ,
EMERGENCY CLASSIFICATION:
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)
D\
V B. Coincident Main Steam line N-16 alarm (s) or condenser off gas process monitor count rate increase or Steam Line High Range Rad Moniters Increase (RI2681 or RI2682) or Nuclear Chemistry Sample indicating Primary-Secondary tube leak.
A,,,N,,,D_
- 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 RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 Electrical Power Failures 4
/D V
PROCJWORK PUUd NO. PROCEDURE / WORK PLAN TITLE: PAGE: 30 of 124 REV: 33 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION CHANGE:
,rm ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.5 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 >l gpm, with coincident Main Steam Line N-16
^% alarm (s), or condenser off gas process monitor countrate increase or Nuclear j Chemistry sample indicating Primary-Secondary tube leak.
AND l 2. Greater than 1% failed fuel indicated in the RCS (EAL 1.2)
A__N_p
- 3. ANY of the following occur.
I A. Loss of offsite power I B. Steam release to the environment indicated by: j
- 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 j
- 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 O
v
Pn0C.M000C PLAN NO. PROCEDUREM000C PUW TTTLE: PAGE: 31 Of 124 -
REV: 33 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE:
ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES 4.1 i
CONDITION: !
Degraded Power EMERGENCY CLASSIFICATION: I Notification of Unusual Event MODES All CRITERIA:
- 1. Only Diesel Generator (Station Blackout Diesel or Emergency Diesel) power is l available to 4160V Buses (A3 and/or A4).
I AND v
- 2. No voltage indicated on 6.9 KV AND 4.16 KV nonvital buses (H1, H2, A1, and A2) i RELATED EALS: TAB Blackout 4 l OTSG Tube Leak 3 j i
r i
l I
l I
O l
. _ _ _ _ _ _ _ _ _. _ _ . _ _ . . . . . . _ _ _ _ ~ . _ _ . __
PROCJWOftK PLAN NO. Pft0CE PtJud TITLE: PAGE: 32 Of 124 N: 33 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION CHANGE.
ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES
4.2 CONDITION
Station Blackout EMERGENCY CLASSIFICATION:
Alert MODES All 5
CRITERIA:
- 1. All 4160V buses de-energized.
[
RELATED EALS: TAB Blackout more than 15 minutes 4 Loss of Control Room Annunciators 6
. - . . - _ . .. _ . . -. .- . _.- ~_. . _ ~ - . . . . . . . .. -
PROCJWORK PLAN NO. Mt0CEDURE/ WORK PLAN Tm.E: PAGE: 33 Of 124 REV: 33 l 1903.010 EMER5ENCY ACTION LEVEL CLASSIFICATION CHANGE:
Q ATTACHMENT 3 UNIT 1 1
ELECTRICAL POWER FAILURES
4.3 CONDITION
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.
O V !
1 RELATED EALS: TAB Electrical Power Failures 4 Loss of Control Room Annunciators 6 Core Melt 1 l
I l
Q
~. - . .. _ _ . . ..
i PRocJwoRK PLAN NO. PROCEDURf) WORK PLAN TITLE: PAGE: 34 of 124 M: 33 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION CHANGE:
h (Q ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES l
4.4 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 1
A. D01 and D02 '
f B. RA1 and RA2 *
\ C. D11 and D21 l
l RELATED EALS: TAB ;
Loss of All Vital DC Power for more than 15 minutes 4 Loss of Control Room Annunciators 6 i
i I
C,)
l l
-. - -.. . . . . - ~ _ . . - - . . - . -
PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 35 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION *: 33 CHANGE:
+
h Q ATTACHMENT 3
- UNIT 1
. ELECTRICAL POWER FAILURES 4.5 1 CONDITION: _,
s Loss of All Vital DC Power for more than 15 minutes EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Loss of voltage on ALL of the following busses A. D01 and D02 (N B. RAl and RA2 C. D11 and D21 AND
- 2. DC power is not restored within 15 minutes RELATED EALS: TAB j i
Electrical Power Failures 4 Loss of Control Room Annunciators 6 1
0
Proc; work PLAN NO. PROCEDUREf40RK PLAN TITLE: Pact: 34 of 124 REV: 33 1903.010 EMERS.ENCY ACTION LEVEL CLASSIFICATION CHANGE.
ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.1 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is l greater than or equal to .05 mrem /hr TEDE or .15 mrem /hr Child Thyroid CDE 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 mrem /hr Child Thyroid CDE.
(
3 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 CDE.
[
9 C. Liquid radiological effluents exceed Tech. Spec. Limits.
RELATED EALS: TAB Radiological Effluents 5 High Radiation / Airborne Levels 5 OTSG Tube Leak 3
(')N L
Pnoc; WORK PUW NO. PROCEDUREDWORK PLAN TITLE: PAGE: 37 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE.
\
g 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 CDE or Liquid
( radiological effluents exceed 10 times Tech. Spec. Limits.
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits m
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 l mrem /hr Child Thyroid CDE.
3 B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds .5 mrem /hr TEDE or
( l.5 mrem /hr Child Thyroid CDE. I C. Liquid radiological effluents exceed 10 times Tech. Spec. Limits.
RELATED EALS: TAB Radiological Effluents 5 OTSG Tube Leak 3 l Containment Radiation High 1
/ '
V
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 38 of 124 RN 33 1903 010
. EMERIENCY ACTION LEVEL CLASSIFICATION CHANGE:
/~h/ 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 l Child Thyroid CDE at the Site Boundary.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits
] r 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 g
mrem /hr Child Thyroid CDE.
ER.
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 l CDE.
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 l
F 1
PRoCJwoRK PLAN NO. PROCEDURE / WORK PUUd TITLE: PAGE: 39 of 124 1903.010 EMER0 ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
f"%
( I b/ ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.4 CONDITION
Radiological Effluents are greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr l Child Thyroid CDE at the Site Boundary.
I i
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 l mrem /hr Child Thyroid CDE.
9E 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 CDE.
-l; RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation High / Very High 1 N
1 l
1 PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 40 of 124 <
1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
Ol I
V ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.5 CONDITION
High Radiation / Airborne Levels i
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. The loss of control of radioactive material results in ANY of the following:
A. Containment radiation indicates >2R/hr B. Area Radiation levels in controlled access (excluding containment)
D increase by 1 Rem /hr at 2 or more locations.
l C. General area radiation levels outside of radiologically controlled areas increase by 10 mrem /hr.
D. Airborne levels as follows:
- Auxiliary Building 2100 DAC (General Area)
- Turbine Building 310 DAC 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.)
RELATED EALS: TAB Radiological Effluents 5 Containment Radiation High 1 Spent Fuel Accident 5 RCS Leakage 2
(%
\ l V
.. . . . . . . . . . - _. - . ~ ..__ . _- --- = -_. . . .
PRoCJWoRK PUud NO. PROCEDUREUWORK PLAN TITLE: PAGE: 41 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
/ ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.6 CONDITION
Spent Fuel Accident EMERGENCY CLASSIFICATION:
Site Area Emergency l MODES All l
CRITERIA:
- 1. The loss of water OR damage to a spent fuel assembly occurs in the spent fuel pool, refueling canal, or Rx core (head removed).
. \h AND
l i
RELATED'EALS: TAB Radiological Effluents 5 High Radiation / Airborne Levels 5 l
I l
PROCJWORK PLAN NO. PROCEDUREMORK Pt.AN TITLE: PAGE: 42 of 124 I I
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REv: 33 CHANGE:
f%
ATTACHMENT 3 UNIT 1 j SAFETY SYSTEM FUNCTION ;
e
6.1 CONDITION
Deviation from T.S. action statements when required to shutdown or cooldown or deviations pursuant to 10CFR50.54(x) l EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES Above CSD CRITERIA:
- 1. EITHER of the following conditions exist:
A. Inability to reach required mode within Tech. Spec. limits.
- 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 l
l 4
V l
PROCJWORK PLAN NO. PROCEDURENYORK PLAN TITLE: PAGE: 43 Of 124 ,
1903.010 EMER0ENCY ACTION LEVEL CLASSIFICATION Rm 33 )
CHANGE:
.m 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.
- 2. Subsequent efforts to manually trip the Reactor from the Control Room and bring it suberitical are successful.
RELATED EALS: TAB RPS Failure to Complete a Manual Trip 6 Core Melt 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product Barriers 1 a
PROCJWORK PLAN NO. PROCEDURE / WORM PLAN TITLE: PAGE: 44 Cf 124 1903.010 EMERBENCY ACTICN LEVEL CLASSIFICATION REV: 33 CHANGE:
( \
V ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.3
~
CONDITION:
Reactor Protection Systen Failure to Complete an Manual Trip ,
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Hot Stdy-Pwr Ops l
CRITERIA:
w
- 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
, subcritical. ,
( l
\ AND a
- 2. Failure of manual trip function occurs. (Failure to trip the Reactor in the Control Rooms i.e., must leave Control Room to trip the Reactor. )
A 1
1 l
RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Boundaries 1 Core Melt 1 Core Damage Indicated with an ICC Condition 1 A
U l
Proc.twoRK PMO. PROCEDURE / WORK PLAN TITLE: PAGE: 45 of 124 1903.010 EMERHENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
' p)
(V ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION l l
6.4 CONDITION
Loss of Dose Assessment Capabilities i
l EMERGENCY CLASSIFICATION:
I Notification of Unusual Event l
MODES All l
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 />.
-m @
- 2. The following conditions exist in the 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 />.
,'r i 4
@ l
- 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 a
e v
. . . - . . . . _ _ . _ . - _ . - - -~ - . . .
4 PROCJWORK PLAN NO. PftOCEDURE/ WORK PLAN TITLE: PAGE: 44 of 124 1905.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33
- CHANGE.
l'
/ ATTACHMENT 3 I' UNIT 1 SAFETY SYSTEM FUNCTION i l
6.5 t
i l- CONDITION: i Loss of Communications 1
EMERGENCY 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)
O B.
'Q Station Radio C. Emergency Notification System RELATED EALS: TAB None l
l I
A
PRoCJWORK Pt.AN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 47 of 124 l 1903.010 EMER!ENCY ACTION LEVEL CL.ASSIFICATION " 33 l CHANGE:
(= N $
t ATTACHMENT 3
! UNIT 1 l SAFETY SYSTEM FUNCTION
+
6.6 CONDITION
l 1
Loss of Control Room Annunciators i
i i
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Loss of both AC and DC power to >50% of control room annunciators.
O RELATED EALS: TAB Loss of Control Room Annunicators with Transient in Progress 6
\
l PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: ,
44 of 124 -l 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 I CHANGE:
0
- kj ATTACHMENT 3
, UNIT 1 SAFETY SYSTEM FUNCTION ,
. I
6.7 CONDITION
Loss of Control Room Annunciators with Transient in Progress EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All l
CRITERIA:
- 1. Loss of both AC and DC power to >50% of control room annunciators.
O AND lv 2. A plant. transient is initiated or in progress.
procedure for the definition of a Plant Transient.)
(See section 4.17 of this 1
l RELATED EALS: TAB None 1
l l
l O
t PRoCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 49 of 124 i
1903.010 EMER"ENCY ACTION LEVEL CLASSIFICATION REV: 33 l
CHANGE: l t
\
ATTACHMENT 3 UNIT 1 ;
SAFETY SYSTEM FUNCTION 6.8 CONDITION:
Control Room Evacuation i l
4 r
EMERGENCY CLASSIFICATION:
Alert i
MODEF A_11
(
CRITERIA:
1
- 1. Control Room evacuation is expected to occur OR has already occurred.
f N I i.
I t
i 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 l
O l l
j
PROCJWORK PLAN No. I PROCEDURE / WORK PLAN TITLE: PAGE: 50 of 124 1903.010 EMER!IENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
(m ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.9 CONDITION
Control Room Evacuation and control of shutdown systems not established in 15 .
minutes.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Control Room evacuation has occurred AND control of shutdown
[ n systems is not established from local stations within 15 minutes.
V RELATED EALS: TAB Core Damage Indicated with an ICC Condition 1 Loss of Decay Heat Removal Systems 6 Core Melt 1
(
v
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 51 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REv: 33 CHANGE:
% ATTACHMENT 3 4 UNIT 1 SAFETY SYSTEM FUNCTION 6.10
-CONDITION:
Loss of Decay Heat Removal Capabilities EMERGENCY CLASSIFICATION:
Alert MODES CSD-Refueling S/D CRITERIA:
- 1. Loss of Decay Heat Removal capabilities shall be identified as ANY of the following:
.D \
C/ A. RCS indicates saturated conditions B. Loss of both Decay Heat trains for >l hr and OTSGs are not available fer decay heat removal (NA if Fuel Transfer Canal is flooded)
C. HPI is required for cooling the reactor core.
I l
RELATED EALS: TAL Core Damage Indicated with an ICC Condition 1 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 High Radiation / Airborne Levels S ,
Core Melt 1
- .- - _ -- . . - - . -. . = . . . . .
PROCJWORK PLAN NO. PROCEDUREMORK PLAN TTTLE: PAGE:' 52 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
s-
.'d ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.11 CONDITION:
Degraded Hot Shutdown Capability EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD 6
1 CRITERIA:
I
- 1. Degraded HSD capability shall be identified as ANY of the following: l i
A. Loss of ALL steam removal capability on BOTH OTSGs. (eg. Loss of ALL '
Turbine Bypass Valves, Atmospheric Dump Valves, and Main Steam Safety O(/ Valves) '
B. Loss of ALL feedwater supply capability on BOTH OTSGs. (eg, Loss of BOTH Main Feedwater Trains and BOTH EFW 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 LJ
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 53 of 124 1903.010 EMER*ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
(
V 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:
Same as the condition stated above.
RELATED EALS: TAB ongoing security Threat Inside Protected Area Fence but outside 7 plant buildings n-
PROCJWORK PLAN NO. PROCEDUREMf0RK PLAN TITLE: PAGE: 54 of 124 1903.010 EMER:IENCY ACTION LEVEL CLASSIFICATION Rm 33 CHANGE:
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 l
CRITERIA:
Same as the Condition stated above.
RELATED EALS: TAB ongoing security threat within plant buildings but not in Control 7 Room or vital areas.
m)
PROCJWORK PLAN NO. PROCEDURFJWORK PLAN TITLE: PAGE: 65 of 124 1903.010 EMER!ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE: ,
fy
(
'v). 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 i
RELATED EALS: TAB !
Ongoing security Threat within Control Room or Vital Areas 7 l l
v\
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 6 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REv: 33 CHANGE:
ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.4 CONDITION
Ongoing security threat within the Control Room or vital areas .
EMERGENCY CLASSIFICATION:
General Emergency MODES All l
CRITERIA: !
I I
Same as the Condition stated above.
l b
u l
RELATED CALS: , TAB None
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAor: 57 of 124 1903.010- EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
NT ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.5 CONDITION
Fire or Explosion Onsite EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Fire within the Protected Area Security Fence which is not extinguished within 10 minutes.
bi V 9.B
- 2. Explosion causing facility damage.
RELATED EALS: TAB Fire or Explosion Onsite Affecting One Train of an ES System 7 e)
_- . . . - - . ~,- . - - . ..
PRoCJwoRK PLAN No. PROCEtd9tEMORK PLAN TITLE: PAGE: 54 Cf 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION RW: 33 CHANGE
'h ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.6 CONDITION
Fire or Explosion Onsite Affecting One Train of ANY ES Systems l
l EMERGENCY CLASSIFICATION:
Alert l
l MODES All 1
I l
CRITERIA:
- 1. Fire or explosion onsite
- 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 l
i
'u i II l
PROCJWORK PLAN NO. PROCEDURflWORK PLAN MLE: PAGE: 59 of 124 1903.010 EMER2ENCY ACTION LEVEL Cl.ASSIFICATION Rm 33 CHANGE:
U ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.7 CONDITION
Fire or Explosion Onsite Affecting Both Trains of ANY ES Systems EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Fire or explosion onsite
/
U ^"
- 2. A potential or actual loss of Both trains of ANY ES system as a result of the fire or explosion i
RELATED EALS: TAB Control Room Evacuation and control of shutdown systems not 6 established in 15 minutes ;
I 1
i
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 60 c. II4 1903.010 EMER!ENCY ACTION LEVEL CLASSIFICATION W: 33 CHANGE:
.O\
U ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.8 CONDITTON
Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine Failure, Toxic or Flammable Gas Release EMERGENCY CLASSIFICATION:
Notification of Unusual Event I
MODES All i
l CRITERIA: I 1
1.
ANY of the following: I
\s-) A. Aircraft crash onsite.
1 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 restricts access to areas required for security or safe operation of the plant.
RELATED 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 b
O
4 PROCJWORK PLAN No. PROCEDUREUWORK PLAN TITLE: PAGE: 61 of 124 1903.010 EMERCENCY ACTION LEVEL CLASSIFICATION REv: 33 CHANGE:
- Q U 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 k-EMERGENCY CLASSIFICATION:
Alert MODES All t
1 CRITERIA:
a
- 1. ANY of the following:
,m i e S
' V A. Aircraft crash onsite.
B. Missiles / Projectiles from any source C. Toxic or flammable gas release AND
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 i
V
_ . . . . . . . =. - .
)
i PROCJWORK PLAN NO. PROCEDURE / WORK Pt.AN TITLE: PAGE: 62 of 124 ]
1903.010 EMEROENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
)
/~'s
(.) ATTACHMENT 3 UNIT 1 l
1 HAZARDS TO STATION OPERATION 7.10
, COND1 TION:
Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains of ANY ES j System i
EMERGENCY CLASSIFICATION: 1 1
Site Area Emergency I
- MODES All l
CRITERIA:
- l. ANY of the following:
1 O
'gj A. Aircraft crash onsite.
B. Missiles / Projectiles from any source C. Toxic or flammable gas release I
AND
RELATED EALS: TAB Fire or Explosion Onsite Affecting Both Trains of an ES System 7 1
!'NG'
}
PROCJWORK PLAN NO. PROCEDUREMf0RK Pl.AN TITLE: PAGE: 63 ef 124 1903.010 EMER ENCY ACTION LEVEL CLASSIFICATl:N REV: 33 CHANGE:
O v 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 s.) B. Flood - Lake level 3340' elev. and rising, with forecasted lake level 1350' elev.
C. Low Level - Lake level <337' elev. AND forecasted by U.S.
Army Corp 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 Earthquake:
l l
O I U '
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 64 of 124
-1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REY: 33 CHANGE.
,e~.
ATTACHMENT 3 UNIT 1 NATURAL EVENTS
8.2 CONDITION
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
'l l
- 1. ANY of the following:
[k A. Tornado striking vital facility structures (e.g. housing ES related equipment)
J B. High Winds - Sustained winds of >60 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. j D.
Low Level - Lake level 5335' elev E. Earthquake - VERIFIED earthquake of magnitude of 3.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 Prodact Barriers 1
l PRoCJwoRK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 65 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REY: 33 CHANGE:
(d 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 followings i s A. High Winds - Sustained winds of >67 mph (10 minute average L/ -
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 ES system.
RELATED EALS: TAB Loss of or challenge to all 3 Fission Product Barriers 1 O
V
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN MLE: PAGE: 66 of 124
]
1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 !
CHANGE:
O ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS
.) 9.1 l l
CONDITION:
1 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. i 1
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All l
CRITERIA:
A k_) An event has occurred and the following conditions exist:
- 1. This event is not covered by any other EAL AND ;
- 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.
RELATED EALS: TAB Plant Conditions Exist that Warrant Precautionary Activation of the 9 TSC
PROCJWORK PLAN NO. PROCEDUREANORK PLAN TITLE: PAGE: 67 of 124 1903.010 EMEREENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
("h ATTACHMENT 3 UNIT 1 MISCELLANEOUS l 9.2 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:
l 3
The following conditions must exist '
\
- 1. This event is not covered by any other EAL. l l
AND l
1
- 2. This event must either challenge or cause the loss of a fission product l barrier.
J 0E Plant conditions exist that warrant activation of the Emergency Response organization.
RELATED EALS: TAB ;
i Plant Conditions Exist that Warrant Activation of the Emergency 9 i Response Centers. 1 I
l 1
L)
1 l
PROCJWORK PLAN NO. PROCEDUREMf0RK PLAN TITLE: PAGE: 68 of 124 !
1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION REV: 33 i
CHANGE:
,f
'\ ATTACHMENT 3 UNIT 1 l MISCELLANEOUS l 9.3 CONDITION: ..
1 4
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.
)
i EMERGENCY CLASSIFICATION:
Site Area Emergency
\
MODES All e
CRITERIA:
.O 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 RELATED EALS: TAB
{
Plant Conditions Exist that Make Release of Large Amounts of 9 Radioactivity Possible l
g ;
C/ I l
i
'I
_ _ . . . . _ . __ ___ . .. _ ~ _ . _ . . - _ . _ .
PRoCJWORK PLAN NO. PROCEDURE / WORM PLAN TITLE: PAGE: 69 ef 124 1903.010 EMERUENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
(~~%
ATTACHMENT 3 UNIT 1
, MISCELLANEOUS i l 9.4 CONDITION: (
Plant Conditions Exist That Make Release of Large Amounts of Radioactivity Possible f
EMERGENCY CLASSIFICATION:
] General Emergency MODES All d
C_RITERIA:
The following conditions must exist:
4
. /%
- 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.
1 RELATED EALS: TAB l
None
! l l
l o
~O l
1
. ._ _ _ .- . . ~ .. .. ._ _ . __
PROCJWORK PLAN NO. PROCEDURIUWORK PLAN TITLE: PAGE: 70 of 124 1903.010 EMER2ENCY ACTl2N LEVEL CLASSlFICATION REV: 33 CHANGE:
b) ATTACHMENT 4 UNIT 2 RCS ACTIVITY f 1.1 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*'2) >5.5E CPM 5 (2RR4806 on 2C14 or 2RITS 4806B on 2C22) k'O B. Specific I tal 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,[ \
PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITL2: PAGE: 71 of 124 1903.010 EMER!ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
n
(
G)~- ATTACHMENT 4 UNIT 2 RCS ACTIVITY l 1.2 CONDITION:
RCS Activity indicates >1.0% failed fuel EMERGENCY CLASSIFICATION:
Alert MODES 1-5 l
CRITERIA:
- 1. Greater than 1% failed I31 fuel as indicated by RCS Sample Analysis
>378 pCi/gm specific I 10 1 V i l
l l
RELATED EALS: TAB General Area Radiation / Airborne 5 Containment Radiation 1 Loss of or Challenge to 3 Fission Product Barriers )
1 '
Core Damage /ICC 1 l l
4 v
e
l l
PROC./ WORK PLAN No. PROCEDUREMORK Pt.AN TITLE: PAGE: 72 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REv: 33 CHANGE:
/%
id ATTACHMENT 4 UNIT 2 Core Damage /ICC l l 1.3 CONDITION:
Core Damage Indicated with an Inadequate Core Cooling Condition EMERGENCY CLASSIFICATION:
1 Site Area Emergency MODES 1-5 l
l l
CRITERIA:
- 1. Greater than 1% failed Ifuel as indicated by RCS sample analysis
>378 pCi/gm Specific I'3 I
-(/ AND l_ 2. Inadequate core cooling capacity exists 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 l
rd
' i l
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 73 of 124 l 1903.010 EMER0ENCY ACTION LEVEL CLASSIFICATION REV: 33 )
CHANGE:
b) i_ ATTACHMENT 4 UNIT 2 CONTAINMENT PARAMETERS l 1.4 I
l CONDITION: !
Containment Radiation readings which indicate 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 6)
AND
- 2. LOCA occurring within the Containment Building l
RELATED EALS: TAB Containment Radiation 1 Loss of or challenge to 3 Fission Product Barriers 1 Radiological Effluents S Core Melt 1
~
Proc > work PLAN No. PROCEDUREMORK PLAN TITLE: PAGE: 74 Of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
ATTACHMENT 4 UNIT 2 CONTAINMENT RADIATION l 1.5 CONDITION:
Containment Radiction readings which indicate LOCA and >50% fuel overheat .
EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
- 1. Containment Radiation Levels correspond to a General Emergency as determined from the containment radiation EAL plot (Att 6)
G AND
- 2. l LOCA occurring within the Containment Building
{
l 1
J l
RELATED EALS: TAB Loss of or challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 l
Core Melt 1 i
O
PROCJWORK PLAN No. PROCEDURE / WORK PLAN TITLE: PAGF.: 75 of 124 1903.010 EMER3ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE-f' (L l ATTACHMENT 4 UNIT 2 CORE MELT 1.6
)
CONDITION:
Core Melt with Containment Integrity Lost or Challenged EMERGENCY CLASSIFICATION:
General Emergency j i
MODES All '
CRITERIA:
- 1. ANY of the following events occur O A. Small or Large LOCA and a complete failure of ALL ECCS systems occurs.
B. Loss of ALL feedwater AND S/G Level in both S/G's is <70" (Wide Range)
AND a complete failure of ALL ECCS Systems occurs.
C. Anticipated transient without a Rx trip AND l 2. Containment Integrity is lost OR challenged as defined by 4.15.3 or 4.16.3 (Definitions)
RELATED EALS: TAB Loss of or challenge to 3 Fission Product Barriers 1 Containment Radiation 1 Radiological Effluents 5 f%
)
i PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 76 of 124 1903.010 EMER ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
f\
b/ ATTACHMENT 4 UNIT 2 LOSS OF OR CHALLENGE TO 3 FISSION PRODUCT BARRIERS l l 1.7 CONDITION:
Loss of or challenge to all 3 Fission Product Barriers EMERGENCY CLASSIFICATION:
General Emergency MODES All i
CRITERIA: l
)
- 1. Either of the following conditions exist:
A. Fuel Cladding Failure (refer to section 4.15.1)
B. Challenge to Fuel Cladding (refer to section 4.16.1)
AND
- 2. Either nf the following conditions exist:
A. RCS boundary failure (refer to section 4.15.2)
B. Challenge to RCS boundary (refer to section 4.16.2)
AND
- 3. Either of the following condition exist A. Containment Integrity failure (refer to section 4.15.3)
B. Challenge to Containment Integrity (refer to section 4.16.3)
I l
l RELATED EALS: TAB Containment Radiation 1 Core Melt 1 Radiological Ef fluents 5 Natural Events 8
/O L]
PROCJWORK PLAN NO. PROCEDUREMORK PLAN Tm.E: PAGE: 77 of 124 ,
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rev: 33 ,
CHANGE:
b ATTACHMENT 4 UNIT 2 RCS LEAKAGE
2.1 CONDITION
RCS Leakage > Tech. Spec. Limits requiring a plant S/D or C/D ;
i EMERGENCY CLASSIFICATION:
Notification of Unusual Event ]
l MODES 1-4 j 1
l CRITERIA:
- 1. RCS Leakage exceeds ANY of the following limits: (T.S. 3.4.6.2)
A. RCS pressure boundary leakage >0 y B. Unidentified RCS Leakage >l gpm C. Identified RCS Leakage >10 gpm D. RCS Pressure Isolation Valves Leakage > T.S. Table 3.4.6.-l limits AND
- 2. A Plant S/D or C/D is required.
RELATED EALS: TAB RCS Leakage 2 T.S. L.C.O.'s 6 Primary to Secondary Leakaqf. 3 General Area Radiation /Aig,vrne 5 O
PROCJWORK PLAN NO. PROCEDUREUWORK PLAN TITLE: PAGE: 78 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
d ATTACHMENT 4 UNIT 2 j RCS LEAKAGE j
- i 2.2 I l
CONDITION:
l RCS Leakage > 44 gpm
}
l EMERGENCY CLASSIFICATION:
Alert MODES 1-4 CRITERIA:
l
- 1. RCS Leakage is >44 gpm (Capacity of a single Charging Pump). l e
v RELATED EALS: TAB RCS Leakage 2 General Area Radiation / Airborne 5 Containment Radiation 1 Decay Heat Removal 6 Primary to Secondary Leakage 3 O
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 79 of 124 1903.010 EMER0ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
f~
ATTACHMENT 4 UNIT 2 RCS LEAKAGE
2.3 CONDITION
RCS Leakage > 44 gpm with ICC Conditions EMERGENCY CLASSIFICATION:
Site Area Emergency MODES 1-4 CRITERIA:
- 1. RCS Leakage is >44 gpm (Capacity of a single Charging Pump).
s 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 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 temperature increasing.
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 O
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 80 of 124 1903.010 EMERCENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
(^\
'N ATTACHMENT 4 UNIT 2 MSIS 3.1 CONDITION:
Uncontrolled S/G Depressurization Resulting in MSIS Actuation ,
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 l
CRITERIA:
- 1. Any actuation of MSIS due to uncontrolled Steam Generator depressurization.
\j RELATED EALS: TAB Primary to Secondary Leakage 3 Radiological Effluents 5 r$
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 81 of 124 1903.010 EMER2ENCY ACTICN LEVEL CLASSIFICATION REV: 33 CHANGE:
I
% ATTACHMENT 4 UNIT 2 PRIMARY TO SECONDARY LEAKAGE
3.2 CONDITION
S/G Tube Leak > Tech Spec Limits EMERGENCY CLASSIFICATION:
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 e
B. Leaka7e to 1 S/G is >.5 gpm RELATED EALS: TAB RCS Leakage 2 Primary to Secondary Leakage 3 Radiological Effluents 5 o
I i
PROCJWORK PLAN NO. PROCEDUREMf0RK PLAN TITLE: PAGE: 82 cf 124 1903.010 EMEREENCY ACTION LEVEL CLASSIFICATION RW: 33 CHANGE:
f\.
h ATTACHMENT 4 UNIT 2 PRIMARY TO SECONDARY LEAKAGE ;
3.3 CONDITION
S/G Tube Leak >10 gpm with an ongoing Steam Release '
EMERGENCY CLASSIFICATION:
Alert MODES 1-4 .
I CRITERIA: '
- 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 maintaing S/G Pressure B. SDBCS Atmosf :,ric Dump Valves in Use C. Steam Line Break Outside of Containment D. 2P7A is in tse 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 i
I
. V
PROC./ work PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 83 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
O ATTACHMENT 4 UNIT 2 PRIMARY TO SECONDARY LEAKAGE
3.4 CONDITION
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:
- 1. S/G tube leak >44 gpm with a Steam Release in Progress as indicated by ANY of the following:
p)
( A. Main Steam Safety Valve (s) maintaining S/G Pressure B. SDBCS Atmospheric Dump Valve (s) 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 1 Electrical Power 4
{J
\
u
PROCJWORK PLAN NO. PftOCEDUREMOftK PLAN TITLE: PAGE: 84 Of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
p
(
ATTACHMENT 4 UNIT 2 ELECTRICAL POWER
4.1 CONDITION
Degraded Power EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All Modes .
CRITERIA:
- 1. Temporary Loss of Normal Control Room Lighting O 2.
No voltage indicated on Both 4.16 KV nonvital busses (2Al & 2A2)
AND l 3. One Emergency Diesel or Station Blackout Diesel started and supplying a vital bus (2A3 or 2A4)
RELATED EALS: TAB Electrical Power 4 MSIS 3 '
Primary to Secondary Leak 3 i
V
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 85 of 124 1903.010- EMER!ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
f%
> t
.V ATTACHMENT'4 UNIT 2 4
ELECTRICAL POWER
4.2 CONDITION
Station Blackout EMERGENCY CLASSIFICATION:
Alert MODES All Modes CRITERIA:
- 1. Loss of all Control Room Lighting except emergency DC Lights
- g) AND
- 2. No voltage indicated on Both 4.16 KV nonvital busses. (2Al and 2A2) 4 AND
- 3. No voltage indicated on Both 4.16 KV vital busses (2A3 and 2A4)
RELATED EALS: TAB Electrical Power 4-Communications, Dose Assessment 6 Primary to Secondary Leak 3 Decay Heat Removal 6 Core Melt 1
PROCJWORK PLAN NO. PROCEDUREMIORK PLAN TITLE: PAGE: SS Of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REv: 33 CHANGE:
v 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:
T A. 2D01 and 2D02
{Q B.
C.
2RA1 and 2RA2 2D21 and 2D23 D. 2D22 and 2D24 RELATED EALS: TAB Electrical Power 4 Communications, Dose Assessment 6 so
PROC > work PLAN NO. PROCEDURFJWORK PLAN TITLE: PAGE: 87 of 124 1903.010' EMER2ENCY ACTION LEVEL CLASSIFICATION N: 33 CHANGE:
/%
\
ATTACHMENT 4 UNIT 2 ELECTRICAL POWER
4.4 CONDITION
Blackout >l5 minutes.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Blackout has occurred as indicated by ALL of the following:
/~%
. A. Loss of all Control Room lighting except emergency DC lights ,
B. No voltage indicated on Both 4.16 KV nonvital busses (2A1 and 2A2) '
g C. Neither Vital 4.16 KV Buss energized (2A3 or 2A4)
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 l Radiological Effluents 5 i
I 1
PROCJWORK PLAN NO. PROCEDUREMMK PLAN TITLE: PAGE: 88 ef 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rs: 33 CHANGE:
o V
t ATTACHMENT 4 UNIT 2 ELECTRICAL POWER
4.5 CONDITION
Loss of ALL Vital DC for >15 minutes EMERGENCY CLASSIFICATION:
Site Area Emergency
. MODES All __ ;
l l
CRITERIA: '
- l. Loss of both of the following trains of DC Busses has occurred:
(~5 g RED TRAIN GREEN TRAIN U 2D01 2D02 2RA1 2RA2 2D21 2D22 2D23 2D24 AND
- 2. Power is not restored to at least one train within 15 minutes i
RELATED EALS: TAB Communications, Dose Assessment 6 Decay Heat Removal 6 Core Melt 1 Radiological Effluents 5 O
PROCJWORK PLAN NO. PROCEDUREhWORK PLAN TITLE: PAGE: 89 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSlFICATION RR 33 CHANGE:
/]
ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.1 CONDITION
Projected or measured activity at the site Boundary, averaged over one hour, is l greater than or equal to .05 mrem /hr TEDE or .15 mrem /hr Child Thyroid CDE 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 n method, indicate greater than or equal to .05 mrem /hr TEDE or .15 l mrem /hr Child Thyroid CDE.
\_-)
B. Offsite monitoring teams report activity at the Site Boundary which, I when averaged over the previous one hour, exceeds .05 mrem /hr TEDE or l .15 mrem /hr Child Thyroid CDE. )
i M
C. Liquid radiological effluents exceed Tech. Spec. Limits. l RELATED EALS: TAB Radiological Effluents 5 General Area Radiation / Airborne 5 Primary to Secondary Leak 3 l
v i
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 90 of 124 1903.010 EMERCENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
,rx
's ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.2 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is l greater than or equal to .5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid CDE or Liquid
, 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 g method, indicate greater than or equal to .5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid CDE.
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 l 1.5 mrem /hr Child Thyroid CDE.
O,,,3 C. Liquid radiological effluents exceed 10 times Tech. Spec. Limits.
RELATED EALS: TAB Radiological Effluents 5 Primary to Secondary Leak 3 Containment Radiation 1 v
a PRoCJwoRK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 91 of 124 1903.010 EMER2ENCY ACT12N LEVEL CLASSIFICATION m: 33 CHANGE:
ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.3 CONDITION
Radiological Effluents are greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr f Child Thyroid CDE at the Site Boundary. 1 I
EMERGENCY CLASSIFICATION:
{
Site Area Emergency MODES All l 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 CDE.
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 l CDE.
I l
i RELATED EALS: TAB i
Radiological Effluents 5 I Containment Radiation 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt i v
PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 92 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
f%
ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.4 CONDITION
i Radiological Effluents are greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr )
l Child Thyroid CDE'at the Site Boundary.
EMERGENCY CLASSIFICATION:
1 General Emergency i MODES All CRITERIA:
)
- 1. Radiological Release which exceeds ANY of the following limits O )
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 l mrem /hr Child Thyroid CDE.
O8 I B. Offsite monitoring teams report dose rates at the Site Boundary are i greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr child Thyroid CDE.
RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation 1 O
PROCJWORK PLAN NO. PROCEDURElWORK PLAN TITLE: PAGE: 93 of 124 1903.010 EMERCENCY ACTION LEVEL CLASSIFICATION Rn: 33 CHANGE:
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 following:
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:
e Auxiliary Building >100 DAC (General Area)
- Turbine Building >10 DAC NOTE: " Loss of Control" Shall be defined as: d Radioactive An 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 v
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 94 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REY: 33 CHANGE:
r ~x lV\
ATTACHMENT 4 UNIT 2 l SPENT FUEL ACCIDENT
5.6 CONDITION
Spent Fuel Accident EMERGENCY CIASSIFICATION:
, Site Area Emergency MODES All 1
CRITERIA:
- 1. The loss'of water OR damage to a spent fuel assembly occurs in the
,- spent fuel pool, refueling canal, or Rx core (head removed).
(\
AND
l RELATED EALS: TAB !
Radiological Effluents 5 General Area Radiation / Airborne 5 l
J
-O I O i i
.. .____ . . . _ - ~ . . . __ .. -. _ _ _ -
PROCJWORK PLAN NO. PROCEDURE / WORK PUUd Tm2: PAGE: 95 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION RH: 33 CHANGE:
't ATTACHMENT 4 UNIT 2 T.S. L.C.O.'s
6.1 CONDITION
Deviation from T.S. action statements when required to shutdown or cooldown or l deviations pursuant to 10CFR50.54(x)
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 CRITERIA:
- 1. EITHER of the following conditions exist:
A. Inability to reach required mode within Tech. Spec. limits.
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
V
PROCJWORK PLAN No. PROCEDUREMORK PLAN TITLE: PAGE: 96 of 124 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
ATTACHMENT 4 UNIT 2 RPS FAILURE
6.2 CONDITION
Reactor Protection System Failure to Complete an Automatic Trip EMERGENCY CLASSIFICATION:
Alert MODES 1-2 CRITERIA:
- 1. A valid RPS trip setpoint is exceeded AND
\[j'N
- 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.
RELATED EALS: TAB RPS Failure 6 Core Melt 1 Core Damage /ICC 1 O
d
I 1
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 97 of 124 1903.010 EMER!ENCY ACTl2N LEVEL CLASSIFICATION RW: 33 CHANGE:
[]
U ATTACHMENT 4
)
UNIT 2 j RPS FAILURE I
6.3 l l
CONDITION: l I
Reactor Protection System Failure to Complete a Manual Trip i
I EMERGENCY CIASSIFICATION:
Sito Area Emergency ;
MODES 1-2 i
CRITERIA:
- 1. A valid RPS trip setpoint is exceeded
/
AND
) 2. 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.) '
l RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1 Core Damage /ICC 1 i
v
PRocAvoRK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 98 of 124 1903.010 EMER!ENCY ACTION LEVEL CLASSIFICATION REv: 33 CHANGE:
ATTACHMENT 4 UNIT 2 LOSS OF COMMUNICATIONS / DOSE ASSESSMENT
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 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 />.
93
- 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 />.
9B
- 3. Reactor Building Purge penetration is not isolable and both the applicable SPING and the Process Radiation Monitor are inoperable.
93
- 4. All of the following conditions ekist for any source of gaseous effluents in l 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 s
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 99 cf 124 1903.010 EMEROENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
f%
b ATTACHMENT 4 UNIT 2 LOSS OF COMMUNICATIONS / DOSE ASSESSMENT 6.5 i
CONDITION: '
Loss of Communications I EMERGENCY CLASSIFICATION: I Notification of Unusual Event 1 MODES All l
1 l
CRITERIA:
- 1. Complete loss of ANY TWO of the following:
. ,. A. Plant telephone systems (Commercial telephones and microwave) b B. Station Radio C. Emergency Notification System
)
l RELATED EALS: TAB None l v) .
1 l
l PROCAWORK PLAN NO. PROCEDUREMf0RK PLAN TITLE: PAGE: 100 cf 124 1903.010 EMERCENCY ACTION LEVEL CLASSIFICATION Rn: 33 CHANGE:
6 V ATTACHMENT 4 UNIT 2 CONTROL ROOM EVACUATION
6.6 CdNDITION
l l
Control Room Evacuation EMERGENCY CLASSIFICATION: l Alert MODES All CRITERIA:
- 1. Control Room evacuation is expected to occur OR has already occurred l
[
V RELATED EALS: TAB Control Room Evacuation 6
PaoCJWORK PLAN No. PROCEDURE / WORK PLAN MLE: PAGE: 101 ef 124 1903.010 EMER0ENCY ACTION LEVEL CLASSlFICATION REV: 33 CHANGE:
A' ATTACHMENT 4 UNIT 2 CONTROL ROOM EVACUATION 6.7 l
CONDITION:
Control Room Evacuation and control of shutdown systems not established in 15 l minutes.
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EMERGENCY CLASSIFICATION:
1 Site Area Emergency I 1
MODES 1-4 CRITERIA:
l
- 1. Control Room evacuation has occurred AND control of shutdown systems is not O established from local stations within 15 minutes.
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RELATED EALS: TAB l Core Damage /ICC 1 Decay Heat Removal 6 Core Melt 1 I
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PROCJWORK PLAN NO. PROCEDUREMORK PUW TITLE: PAGE: 102 of 124 ,
1903.010 EMERGENCY ACTION LEVEL CL ASSIFICATION REV: 33 CHANGE:
O I ATTACHMENT 4 l UNIT 2 l
[ DECAY HEAT REMOVAL 6.8 I 1
l CONDITION:
Loss of Decay Heat Removal Capabilities EMERGENCY CLASSIFICATION:
Alert l MODES 5-6 l
l CRITERIA: l I
- 1. Loss of Decay Heat Removal capabilities shall be ider.tified as ANY of the !
followings i
,O I V A. RCS indicates saturated conditions )
B. Loss of both shutdown cooling trains for >l hr and S/G's not available l for decay heat removal (NA if Fuel Transfer Canal >23 ft) )
l C. HPSI injection required for cooling the core l
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RELATED EALS: TAB spent Fuel Accident 5 Core Damage /ICC 1 i Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 High Radiation / Airborne 5 Core Melt 1 l
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I PRoCJWORK PLAN NO. PROCEDURElWORK PLAN TITLE: PAGE: 103 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE: ,
\._. ATTACHMENT 4 UNIT 2 DECAY HEAT REMOVAL
6.9 CONDITION
l Loss of Both S/Gs as a Heat Removal Method j EMERGENCY CLASSIFICATION:
a Site Area Emergency i
MODES 1-4 CRITERIA:
- 1. ALL of the following conditions exist: ;
A. S/G 1evel in BOTH S/Gs is <70" AND B. ECCS Vent System is' utilized RELATED EALS: TAB Containment Radiation 1 RCS Leakage 2 Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 O
O PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 104 of 124 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
' ry 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 BOTH AC and DC power to 9 or more of the Control Room Annunciator Panels.
RELATED EALS: TAB Loss of Control Room Annunciators with a Transient in progress 6 Electrical Power 4 i
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PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 105 of 124 1903.010 EMERIENCY ACTION LEVEL CLASSlFICATION REV: 33 CHANGE:
J V ATTACHMENT 4 j
UNIT 2 LOSS OF CONTROL ROOM ANNUNCIATORS 6.11 CONDITION:
Loss of Control Room Annunciators with a Transient in Progress EMERGENCY CLASSIFICATION:
)
l Site Area Emergency MODES ALL j
CRITERIA:
- 1. Loss of BOTH AC and DC power to 9 or more of the Control Room Annunciator l Panels. '
AND
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- 2. A plant transient is initiated OR in progress. (See Section 4.17 of this procedure for the definition of a Plant Transient).
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I RELATED EALS: TAB Electrical Power 4 l
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PROCJWORK PLAN NO. PROCEDUREMORK PLAN TTTLE: PAGE: 106 of 124 j l 1903.010 EMER0ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
ATTACHMENT 4 I UNIT 2 I SECURITY THREAT l
7.1 CONDITION
i 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:
/~
Same as the Condition stated above.
f
\-
RELATED EALS: TAB Security Threat 7 l
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. -. -. . .. ~.- . . - - . _
PROCJWORM PLAN NO. PROCEDUREMPORK PUW TITLE: PAGE: 107 of 124 1903.010 EMER0ENCY ACTION LEVEL CLASSIFICATION Rm 33 CHANGE.
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' V ATTACHMENT 4 UNIT 2 l
SECURITY THREAT 7.2 i CONDITION: l
! I j
Ongoing security threat within the Protected Area Security Fence but outside of plant buildings.
EMERGENCY CLASSIFICATION:
Alert l
MODES All I CRITERIA:
Same as the condition stated above.
l RELATED EALS: TAB Security Threat 7 Fire or Explosion 7 l
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l l PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 108 of 124 1 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION ": 33 CHANGE:
l C\
ATTACHMENT 4 I
! UNIT 2 l
SECURITY THREAT l . j l 7.3 1 1
CONDITION. l l I Ongoing security threat within plant buildings but not within the Control Room or l l vital areas. !
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
Same as the Condition stated above.
O RELATED EALS: TAB Security Threat 7 Fire / Explosion 7 1
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1G
. . =. - . _ . . - . . . . - . - -
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 109 of 124 )
4 1903.010 EMERIENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
ATTACHMENT 4 UNIT 2 SECURITY THREAT l
7.4 CONDITION
Ongoing security threat within the Control Room or vital areas.
T EMERGENCY CLASSIFICATION:
General Emergency i MODES All CRITERIA:
1 Same as the Condition stated above.
(h
, V RELATED EALS: TAB None l
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PRoCJWORK PLAN No. PROCEDURE / WORK PLAN TITLE: PAGE: 110 of 124 1903.010 EMER ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
(V3 ATTACHMENT 4 UNIT 2 FIRE / EXPLOSION 7.5 l
l CONDITION.
Fire or Explosion Onsite l
EMERGENCY CLASSIFICATION:
Notification of Unusual Event ;
MODES All CRITERIA:
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- 1. Fire within the Protected Area Security Fence which is not extinguished '
within 10 minutes.
- 2. Explosion causing facility damage.
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RELATED EALS: TAB l Fire or Explosion 7 Security Threat 7 O
_ . . _ . - -= -
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PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 111 of 124 l 1903.010 EMERZENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
- V ATTACHM"NT 4 l
UNIT 2 FIRE / EXPLOSION
7.6 CONDITION
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Fire or Explosion Onsite affecting One Train of ESF Systems <
l EMERGENCY CLASSIFICATION:
Alert i MODES All l l
l CRITERIA:
- 1. Fire or explosion onsite
,O AND
, V 2.
A potential or actual loss of a single train of ANY ESF system as a result of the fire or explosion.
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l RELATED EALS: TAB Fire or Explosion 7 l Communications, Dose Assessment 6 Control Room Evacuation 6 l
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PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 112 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
(s< ATTACHMENT 4 l
l UNIT 2 l FIRE / EXPLOSION I
7.7
]
CONDITION:
Fire or Explosion Onsite affecting Both Trains of ESF Systems l
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Fire or explosion onsite )
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- 2. A potential or actual loss of Both trains of ANY ESF system as a result of l the fire or explosion. !
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RELATED EALS: TAB Communications, Dose Assessment 6 Control Room Evacuation ,
6
1 PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 113 of 124 1903.010 EMEREENCY ACTION LEVEL CLASSIFICATION Rm 33 CHANGE:
O 4
\
L/ ATTACHMENT 4 UNIT 2 OTHER HAZARDS I
7.8 CONDITION
Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine failure, Toxic or Flammable Gas EMERGENCY CLASSIFICATION: l Notification of Unusual Event MODES All CRITERIA: _
- l. 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. Toxic or flammable gas release which limits or restricts 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
PROCJWORK PLAN NO.. PROCEDURENWORK PLAN MLE: PAGE: 114 cf 124 1903.010 EMER!ENCY ACTION LEVEL CLASSIFICATION N: 33 CHANGE:
rN ATTACHMENT 4 UNIT 2 OTHER HAZARDS 7.9 CONDITION:
Aircraf t Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ESF Systems EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following
- O A. Aircraft crash onsite
'%Y 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 RELATED EALS: TAB Fire or Explosion 7 Other Hazards 7
i PRoCJWORK PLAN NO. PROCEDUREMPORK PLAN TITLE: PAGE: 115 of 124 1903.010 EMERCENCY ACTION LEVEL CLASSlFICATION REV: 33 CHANGE:
?
\s ATTACHMENT 4 UNIT 2 OTHER HAZARDS 7.10 CONDITION:
- Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Redundant ESF Trains EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. ANY of the following V A. Aircraft crash onsite B. Missiles / Projectiles from any source C. Toxic or flammable gas release AND
- 2. A potential y actual loss of BOTH trains of ANY ESF system RELATED EALS: TAB ;
Fire or Explosion 7 ,
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PROC.Mf0RK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 116 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION Rn: 33 CHANGE. j
(')
(/ ATTAR.HMENT 4 I
UNIT 2 NATURAL PHENOMENON 8.1 ;
CONDITION:
Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION: l I
Notification of Unusual Event !
MODES All i
CRITERIA:
- 1. ANY of the following A. Tornado observed on the ground within the Exclusion Area B. Flood - Lake level >340' elev. and rising with forecasted lake level
>350' elev.
C. Low Level - Lake level 3337' AND forecasted by U.S. Army Corp of Engineers to reach 335' D. Earthquake - VERIFIED earthquake of magnitude of .01g l
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RELATED EALS: TAB !
Natural Phenomenon 8 i
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[
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PROCJWORK PLAN NO. PROCEDURE > WORK PLAN TITLE: PAGE: 117 Ef 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION Rm 33 CHANGE:
/
(,>3 ATTACHMENT 4 UNIT 2 NATURAL PHENOMENON
8.2 CONDITION
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
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- 1. ANY of the following )
i A. Tornado striking vital facility structures (e.g. housing ES related ;
equipment) 1 O
i j B. High Winds - Sustained winds of 172 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments).
l C. Flood - Flood waters 1350' and are forecasted by U.S. Army Corp of I Engineers to reach or exceed 354'
)
D. Low Level - Lake level $335' elevation E. Earthquake - VERIFIED Earthquake of magnitude 2.lg RELATED EALS: TAB Natural Phenomenon 8 Loss of or challenge to all 3 Fission Product Barriers 1 !
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PROCJWORM PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 118 of 124 1903.010 EMER"ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
A l )
sd ATTACHMENT 4 UNIT 2 NATURAL PHENOMENON
8.3 CONDITION
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION:
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 arr k
%J
PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 119 of 124 1903.010 EMER!ENCY ACTION LEVEL CLASSIFICATION RW: 33 CHANGE:
ps.
ATTACHMENT 4 UNIT 2 MISCELLANEOUS l 9.1 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.
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
,3 An event has occurred and the following conditions exist:
I \
V 1. This event is not covered by any other EAL AND
- 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.
RELATED EALS: TAB 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
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PROC.lWORK PLAN NO. PROCEDUREMf0RK PLAN TITLE: PAGE: 120 of 124 1903.010 EMER ENCY ACTION LEVEL CLASSIFICATl!N REV: 33 CHANGE:
C ATTACHMENT 4 UNIT 2 MISCELLANEOUS f 9.2 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.
l EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIAt
[ The following conditions must exist
's
- 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.
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RELATED EALS: TAB RCS Activity 1 RCS Leakage 2 Primary to Secondary Leak 3 Radiological Effluents S Decay Heat Removal 6 ry
Proc > work PLAN No. PROCEDURE / WORK PLAN TITLE: PAGE: 121 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE: j r%.
ATTACHMENT 4 UNIT 2 MISCELLANEOUS f 9.3 CONDITION:
l Other plant conditions exist that warrant activation of emergency response facilities and monitoring teams or a precautionary notification to the public near the site, i
EMERGENCY CLASSIFICATION: -
Site Area Emergency MODES All l CRITERIA:
l The following conditions must exist
- 1. This event is not covered by any other EAL
/ \ AND V !
- 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 {
l C. Failure.of 2 fission product barriers RELATED EALS: TAB Core Damage /ICC 1 Containment Radiation 1 Decay Heat Removal 6 l
i Radiological Effluents 5 RCS Leakage 2 Primary to Secondary Leak 3 l
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PROCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 122 Of 124 1903.010 EMER0ENCY ACTION LEVEL CLASSlFICATION REV: 33 CHANGE:
t/*i
'L/ ATTACHMENT 4 UNIT 2 MISCELLANEOUS l 9.4 CONDITION:
Plant Conditions Exist That Make Release of Large Amounts of Radioactivity Possible EMERGENCY CLASSIFICATION: '
General Emergency MODES All CRITERIA:
l The following conditions must exist
['
v
- 1. This event is not covered by any other EAL
(
AND
- 2. Events have occurred that nake a release of large amounts of radioactivity in a short period of time possible.
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4 RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation 1 Radiological Effluents 5 i
V
PROCJWORK Pt.AN NO. PROCEDUkE/ WORK PLAN TITLE: PAGE: 123 of 124 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
V ATTACIFINT 5 UNIT 1 CONTAINMENT RADIATION EAL PLOT 1E+06 4-2-
1E+05 h
4 '- \
1E+04 --
. e,.Ro m Rh1R 4-2-
1E+03, 4
2-1E+02 4 A
= --
SITE 2- - - -
AREA 0 2 4 6 8 10 12 14 16 18 20 22 24 TBE N HOUR INSTRUCTIONS A. . Determine the containment radiation level.
- 1. If the plant has been operating at 100% for the past 30 days, use the reading from RE-8060 or RE-8061.
- 2. If the plant has been operating at less than 100% power for the past 30 days, determine the radiaiton level as follows:
Rad level = Reading from RE-8060 or RE-8061 X 100 estimated ave. power for the past 30 days D. Determine the time after shutdown (in hours).
C. Find the intersection of the values from A an B on the graph.
D. Determine the emergency class.
- 1. SITE AREA EMERGENCY - intersection is between the two curves
- 2. GENERAL EMERGENCY - intersection is above the upper curve O
PROCJwoRK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: 124 of 124 1903.010 EMER2ENCY ACTION LEVEL CLASSIFICATION REV: 33 CHANGE:
D j ATTACHMENT 6 UNIT 2 CONTAINMENT RADIATION EAL PLOT 1E+o6_
':.(,
e.os .
4: \ l 2'
1E+04 _
OENERAL EMERGENCY RhiR 45 2
1E+03 4-2-
1E+o2 ,
4l SITE 2
AREA 0 2 4 6 8 10 12 14 16 18 20 22 24 TM" N HOUR INSTRUCTIONS A. Determine the containment radiation level.
- 1. If the plant has been operating at 100% for the past 30 days, use the reading from 2RY-8925-1 or 2RY-8925-2.
- 2. If the plant has been operating at less than 100% power for the past 30 days, determine the radiaiton level as follows:
Rad level = Reading from 2RY-8925-1 or 2RY-8925-2 X 100 estimated ave. power for the past 30 days j B. Determine the time after shutdown (in hours).
C. Find the intersection of the values from A an B on the graph.
D. Determine the emergency class.
1.
SITE AREA EMERGENCY - intersection is between the two curves p
a
- 2. GENERAL EMERGENCY - intersection is above the upper curve t