View source for L-98-200, Requests Approval,Prior to Implementation of Change to Plant Radiological Emergency Plan.Proposed Change Clarifies Criteria Used in Classification of Radiological Emergency. Attachment 1 Provides Explanation of Changes

{{Adams
| number = ML17229A852
| issue date = 08/31/1998
| title = Requests Approval,Prior to Implementation of Change to Plant Radiological Emergency Plan.Proposed Change Clarifies Criteria Used in Classification of Radiological Emergency. Attachment 1 Provides Explanation of Changes
| author name = Stall J
| author affiliation = FLORIDA POWER &amp; LIGHT CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000335, 05000389
| license number = 
| contact person = 
| document report number = L-98-200, NUDOCS 9809090273
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 66
}}

=Text=
{{#Wiki_filter:CATEGORY 1i REGULAT Y INFORM'ATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9809090273 DOC.DATE: 98/08/31 NOTARIZED: NO SCIL:50-335 St. Lucie Plant, Unit 1, Florida Power E Light Co.
50-3S9 St'. Lucie Plant, Unit 2, Florida Power E Light Co.
AUTH.NAME AUTHOR AFFILIATION STALL,J.A.
Florida Power E Light Co.
RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
DOCKET &#xb9; 05000335 05000389

==SUBJECT:==
Requests approval, prior to implementation of change to plant C
radiological emergency plan. Proposed change clarifies criteria used in classification of radiological emrgency.
A Attachment 1 provides explanation of changes.
T.
DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
Emergency Preparedness Plans, 'Implement'g Pro edures, (8
NOTES:
RECIPIENT ID CODE/NAME PD2-3 PD
~ INTERNAL: AEOD/HAGAN,D NRR/DRPM/PERB EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME GLE FILE CENTER STRACT NRC PDR COPIES LTTR ENCL 1
1 2
2 1
1 1
1 R
Y 0
U NOTE TO ALL nRIDS n RECIPIENTS PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 9
ENCL 9

~5

PI@I Florida Power &Light Company. 6351 S. Ocean Drive, Jensen Beach, FL34957 August 3'1, 1998 L-98-200 10 CFR 550.54(q)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Pro osed Chan e to Emer enc Plan Table 3-1: Classification of Emer encies Pursuant to 10 CFR 50.54(q), Florida Power & Light Company (FPL) requests
: approval, prior to implementation, of a change to the St. Lucie Plant Radiological Emergency Plan.
The proposed change clarifies the criteria used in the classification of a radiological emergency.
Emergency action levels remain consistent with the classification criteria currently approved by the NRC.
Attachment 1 provides an explanation of changes to the emergency classification table contained in the St. Lucie Plant Radiological Emergency Plan, Table 3-1. provides a draft revision of Table 3-1 as it would appear in the Radiological Emergency Plan.
Vertical lines are used to indicate changes to the table.
The proposed change was reviewed by the St. Lucie Plant Facility Review Group on July 14, 1998.
On receipt of approval from the NRC of the proposed change, FPL will revise the St.
Lucie Plant Emergency Plan and Emergency Plan Implementing Procedure EPIP-01 to implement the revised classification criterion.
Ifyou have any questions, please contact Mr. Ed Weinkam at 561-467-7162.
Sincerely, J. A. Stall Vice President St. Lucie Nuclear Plant Attachment Q
wJ'c:
Regional Administrator, USNRC Region II (2 copies)
Senior Resident Inspector, USNRC, St. Lucie Plant 98090'F0278 980831 PDR ADOCK 05000335 F
PDR an FPL Group company

I
'l

Attachment 1
Explanation of Proposed Changes to St. Lucie Radiological Emergency Plan Table 3-1; Emergency Classification Table

==Background:==
Emergency Classification Table 3-1 (Revision 34 of the Emergency Plan) was reviewed to identify sections where the descriptive instruction to licensed operators and Plant management could be improved. Specifically, the review addressed areas where clarification could be provided to emergency action levels without changing the intent of the classification criteria. Regulatory guidance and industry standards have been consulted as part of this review. The following changes are proposed:
Event/Class E Plan Rev.34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e
1.A Abnormal Primaiy Leak No CAUTIONstatement Rate CAUTION: THIS SECTION SHOULD NOT BE USED FOR STEAM GENERATOR TUBE LEAK/RUPTURE.
Clarify difference between classification criteria for primary/secondary leakage.
UNUSUALEVENT
: 2. Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below~1600 sia.
UNUSUALEVENT
: 2. Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below:
Unit 1 -1600 sia Unit 2-1736 sla Relief valve settings different for Units 1 and 2.
ALERT
: 1. Charging/letdown mismatch or measured RCS leakage indicates greater than 50 gpm but less than 132 gpm.
ALERT
: 1. Charging/letdown mismatch or measured RCS leakage indicates greater than 50 gpm but less than available char in ca gelt.
Current section does not recognize loss of charging capacity and conflicts with Site Area Emergency section.

Event/Class 1.A Abnormal Primary Leak Rate (continued) 1.B Abnormal Primary to Secondary Leak Rate E Plan Rev. 34 Current SITE AREA EMERGENCY
: 1. RCS leakage greater than 132 gpm occurring with RCS pressure above HPSI shutoffhead.
OR
: 2. RCS leakage greater than available makeup occurring with RCS pressure below HPSI shutoff head.
OR
: 3. Loss of RCS subcooled margin due to RCS leakage (saturated conditions).
OR
: 4. Containment High Range Radiation Monitors indicate 7.3 x 10'/hr (ifCHRRM inoperable, Post-LOCA monitors indicate between 100 and 1000 mR/hr).
SITE AREA EMERGENCY Ra id failure of steam enerator tube s GREATER THAN char in um ca aci with steamrelease in ro ress E Plan, Rev. DRAFT Pro osed SITE AREA EMERGENCY
: 1. RCS leakage greater than 50 gpm and greater than available charging capacity.
OR
: 2. Loss of RCS subcooled margin due to RCS leakage (saturated conditions).
SITE AREA EMERGENCY Ra idfailureofsteam eneratortube s
GREATER THANchar in um ca acit withsteamreleasein ro ress Reason for Chan e
Current revision does not recognize loss of charging capability in some cases where leakage is less than 132 gpm.
Current revision does not clarify credit for normal makeup (charging) only or any makeup. ~
Proposed revision provides for clear classification criteria for LOCAgreater than 50 gpm and greater than (normal) charging capacity, which is consistent with NUREG guidance and industry examples.
Criteria for radiation monitor readings are identified in Event/Class 2.A (Uncontrolled Effluent Release).
Current revision caused confusion to users, specifically concerning "unisolable status of slight release potential from equipment (such as steam driven AFW).
: 3. Secondary steam release in progress from affected generator (i.e., ADVs, Steam Safety(s), or Unisolable.)
: 3. Secondary steam release in progress fromaffecled generatorieeAADDVVas stuck steam safe s
unisolable
~leak Proposed revision provides additional clarification to user on types of secondary steam releases to be considered when classifying event.

Event/Class 2.A Uncontrolled Effluent Release
: 3. Fire Explosion E Plan Rev. 34 Current SITE AREA EMERGENCY
: 2. Measured Dose Rates or Offsite Dose Calculation (EPIP-09) worksheet values at one mile in excess of:
A.
50 mrem/hr (total dose TEDE) or 250 mrem/hr (thyroid dose CDE) for ~/i hour.
OR B.
500 mrem/hr (total dose TEDE) or 2500 mrem/hr (thyroid dose CDE) for two minutes at one mile.
UNUSUALEVENT Uncontrolled fire within the plant lasting more than 10 minutes.
No NOTE in section.
E Plan Rev. DRAFT Pro osed SITE AREA EMERGENCY
: 2. Measured Dose Rates or Offsite Dose Calculation (EPIP-09) worksheet values at one mile in excess of:
A. 50 mrem/hr (total dose ~rate or 250 mrem/hr (thyroid dose ~rate for
/g hour.
OR B. 500 mrem/hr (total dose ~rate or 2500 mrem/hr (thyroid dose ~rate fortwo minutes at one mile.
UNUSUALEVENT Uncontrolled fire within the gower block lasting more than 10 minutes.
NOTE: EXPLOSION IS DEFINED AS A RAPID CHEMICAL REACTION RESULTING IN NOISE HEAT AND THE RAPID EXPANSION OF GAS.
Reason for Chan e
Confusion by users on dose rates versus total dose.
Proposed revision provides clear criteria based on dose rate.
Use of "power block provides clear description of structures of equipment that should be considered in this classification.
"Power block" is specifically defined in EPIP-01.
NOTE provides clear definition of explosion event.

Event/Class E Plan Rev. 34 Current
: 3. Explosion (continued)
ALERT SITE AREA EMERGENCY Severe damage to safe shutdown equipment from explosion.
Damage to facility by explosion which affects plant operation.
E Plan Rev. DRAFT Pro osed ALERT Damage to structures/com onents within the Protected Area by explosion which affects plant operation.
SITE AREA EMERGENCY Severe damage to safe shutdown equipment from explosion Ji.e.
both trains rendered ino erable Reason for Chan e
Proposed revision provides clear identification of the location (Protected Area) where consideration for ciassiTieation of explosions occur.
Proposed revision provides clear criteria for the meaning of severe damage to safe shutdown equipment, which applies regulatory guidance definition for loss of equipment functions.
4.B Fuel Handling Accident SITE AREA EMERGENCY Major damage to irradiated fuel in Containment or Fuel Handling Building 1.
Step increase in the reading of radiation monitors in the plant vent and/or in the Fuel Handling Building AND 2.
Damage to more than one irradiated fuel assembly.
OR 3.
Uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.
SITE AREA EMERGENCY Majordamage to irradiated fuel in Containment or Fuel Handling Building 1.
Affected area radiation monitor levels reater than 1000 mr/hr.
AND
~2.
Ma or Damage to one or more irradiated fuel assemblies OR 3.
Ma or dama e resultin from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool Current revision does not provide specific radiation dose rate threshold.
Current revision criteria requires knowledge of extent of damage
("more than one irradiated fuel assembly" ) which will likely not be known.
Proposed revision provides specific radiation dose rate threshold (consistent with other classification criteria) and does not limitclassification based on unknown extent of damage.

Event/Class 5.A Earthquake E Plan Rev. 34 Current UNUSUALEVENT
: 2. An earthquake is detected by plant seismic monitor instruments.
ALERT A confirmed earthquake occurs which registers GREATER THAN 0.05 g.
E Plan Rev. DRAFT Pro osed UNUSUALEVENT
: 2. An earthquake is detected by plant seismic monitor instruments or other means.
ALERT A confirmed earth uake has occurred 1.
A confirmed earthquake occurs which registers GREATER THAN 0.05 g within the Owner Controlled Area.
OR 2.
A confirmed earth uake has occurred that could cause or has caused a tri of the turbine enerator or reactor.
Reason for Chan e
Current classification does not provide for classification based on information received by other (non-plant) seismic monitors, such as from other nuclear sites, colleges, or scientific monitoring equipment.
The current revision does not consistently identify the location of the increased seismic activity (within the Owner Controlled Area, as in UNUSUALEVENT).
The proposed revision relates the measurement of seismic activity to the Owner Controlled Area and provides for direct indications for effects of the earthquake on plant conditions (turbine or reactor trip).

Class/Event 5.A Earthquake (continued)
E Plan Rev. 34 Current SITE AREA EMERGENCY A confirmed earthquake occurs which registers GREATER THAN 0.1 g. with plant not in cold shutdown.
E Plan Rev. DRAFT Pro osed SITE AREA EMERGENCY A confirmed earth uake has occurred 1.
A confirmed earth uake occurs which re isters GREATER THAM 0.1
. within the Owner Controlled Area and the lant is not in cold shutdown.
OR Reason for Chan e
The current revision does not consistently identify the location ofthe increased seismic activity (within the Owner Controlled Area, as in UNUSUALEVENT).
The proposed revision relates the measurement of seismic activity to the Owner Controlled Area and provides for direct indications for effects of the earthquake on plant conditions (loss of safety related functions).
2.
A confirmed earth uake has occurred that has caused loss of an safet related s stem function i.e. both 5.C Tornado ALERT Any tornado striking facility.
ALERT Any tomario striking ~the ower block.
The current revision did not identify specific affected areas of the plant to be considered for a tornado strike.
Use of "power block" provides clear description of structures of equipment that should be considered in this classification.
'Power block" is specifically defined in EPIP-01.

Event/Class 6.A Increased Awareness or Potential Core Melt E Plan Rev. 34 Current ALERT Emergency Coordinator's judgement that plant conditions exist which warrant:
1.
Increased awareness and activation of Emergency Response personnel.
E Plan Rev. DRAFT Current ALERT Emergency Coordinator's judgement that plant conditions exist which have a otential to de rade the level of safet at the plant.
Reason for Chan e
The current revision causes confusion to whether use of emergency response facilities or activation of any emergency response personnel in its self justifies ALERTclassification.
Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of an ALERT.
1.
Emergency Coordinator's judgement that plant conditions exist which are si nificantl uncontrollable manner.
: 1. Activation of emergency response facilities and monitoring teams or a precautionary notification of the public near the site.
SITE AREA EMERGENCY SITE AREA EMERGENCY Emergency Coordinator's judgement that plant conditions exist which warrant:
The current revision causes confusion to whether use of emergency response facilities in
~ifs self ustifies SITE AREA EMERGENCY classification.
(Classification of SITE AREA EMERGENCY always results in notification of the public.)
Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of a SITE AREAEMERGENCY.
GENERALEMERGENCY 2.
LOCAwith initiallysuccessful ECCS and subsequent failure of containment hear removal systems for several hours.
GENERAL EMERGENCY 2.
LOCA with initiallysuccessful ECCS and subsequent failure of containment heat removal hours.
Current revision does not contain specific time criteria in classification considerations.
Proposed revision provides specific time span, after which a GENERALEMERGENCY classification is warranted.

Event/Class 6.A Increased Awareness or Potential Core Melt (continued)
E Plan, Rev. 34 Current GENERAL EMERGENCY
: 4. Failure of off-site and on-site power along with loss of emergency feedwater makeup capability for several hours.
E Plan, Rev. DRAFT Pro osed GENERALEMERGENCY
: 4. Failure of off-site and on-site power along with loss of ave:gemy feedwater makeup capability for P"
Reason for Chan e
The current revision causes confusion with user in regard to what is "emergency feedwater".
The plant does not designate any equipment as'emergency feedwater.
Current revision does not contain specific time criteria in classification considerations.
The proposed revision provides clear indication that ifthere is no feedwater for'greater than 2 hours, then a GENERAL EMERGENCY classification is warranted.
7.A Loss of Power ALERT
: 2. Failure of both emergency diesel generators to start or synchronize.
SITE AREA EMERGENCY
: 2. Sustained failure of both emergency diesel generators to start or synchronize.
ALERT
: 2. Failure of both emergency diesel generators to start or load.
SITE AREA EMERGENCY
: 2. Sustained failure of both emergency diesel generators to start or load.
Current revision does not address ability of diesel generator to perform its intended function (loadt onto emergency buses)
Proposed revision provides clear indication that ifthe diesel is not loaded, then classification is warranted.

Event/Class 8.8 Loss of Alarms/Communication/
Monitoring 9.A Aircraft/Missile E Plan, Rev. 34 Current UNUSUALEVENT 3.
Unplanned loss of most or all Safety System annunciators for greater than 15 minutes.
SITE AREA EMERGENCY
: 1. Inability to monitor a significant transient in progress.
ALERT 1.
Aircraftcrash in the Owner Controlle'd Area damaging plant structures.
E Plan, Rev. DRAFT Current UNUSUALEVENT 1.
Unplanned loss of most igrester
~than 75% or alt Safety System annunciators for greater than 15 minutes.
SITE AREA EMERGENCY
: 1. Inability to ~effecttvet monitor a significant transient in progress.
NOTE: Si nificant transient exam les include: reactor tri turbine runback reater than 25%
and thermal oscillations reater than 10%.
ALERT 1.
Aircraft crash in the ower block.
Reason for Chan e
Current revision does not provide for a quantitative value for loss of "most'nnunciators.
Proposed revision indicates a specific percentage of annunciators lost needed to classify an UNUSUAL ~
EVENT.
Current revision does not provide guidance on degree of ability in which a transient can be monitored in classifying the event.
Current revision does not provide definition of significant transient.
Proposed revision provides additional guidance for the user to determine that, ifa transient can not be effectively monitored, then a SITE AREA EMERGENCY is warranted.
Additionally, examples of significant transients are provided.
Current revision does not provide reference to crash or missile impact to specific plant structures.
OR
: 2. Visual or audible indication of missile impact on plant structures.
OR
: 2. Visual or audible indication of Proposed revision provides clear indication (i.e., the power block) where a crash or missile impact would warrant classification of ALERT.

Event/Class 9.A Aircraft/Missile (continued)
E Plan Rev. 34 Current SITE AREA EMERGENCY 1.
Aircraft crash in the Owner Controlled Area damaging vital plant systems.
OR 2.
Damage to safe shutdown equipment from any missile.
E Plan Rev. DRAFT Pro osed SITE AREA EMERGENCY 1.
Aircrah crash
~in the ower block damaging vital plant systems.
OR 2.
Damage resultin in loss of safe shutdown equipment from any missile.
Reason for Chan e
Current revision does not provide reference to crash or missile impact on specific plant structures.
Proposed revision defines specific area of the plant where damage is considered classifiable.
Proposed revision identifies effect on safe shutdown equipment as criteria for determining classification of SITE AREA EMERGENCY.
Use of "power block" provides clear description of structures of equipment that should be considered in this classification.
"Power block" is specifically defined in procedure.
9.C Toxic or Flammable Gas SITE AREA EMERGENCY Toxic or flammable gas has diffused into vital areas affecting access to or the operation of safe shutdown equipment.
SITE AREA EMERGENCY Toxic or flammable gas has diffused into vital areas compromising the function of safety related equipment (i.e., both trains rendered inoperable)
Current revision caused confusion with user differentiating between ALERT and SITE AREA EMERGENCY. Current revision does not consistently relate loss of safety system function with other classification criteria.
Proposed revision provides clear difference between ALERTand SITE AREA EMERGENCY.
10

ATTACHMENT2 DRAFT REVISION OF ST. LUCIE RADIOLOGICALEMERGENCY PLAN TABLE 3-1 EMERGENCY CLASSIFICATIONTABLE

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS t.A.
: ABNIBRMA, QRIMA~Y~IQ UNUSUALEVENT r
ln ALERT SITEAREAEMERGENCY T
THAN L
R AT R THAN
<~in
~~m~
GENERALEMERGENCY r
r r
I ln in CAUTtON This section should NOT be used for a steam generator tube leak/rupture.
1.
RCS leakage GREATER THAN 10 gpm as indicated by:
A. Control Room observation QB B. Inventory balance calculation QB C. Field observation QB D. Emergency Coordinator judgement QB 2.
Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below:
- Unit 1-1600 PSIA
- Unit2-1736 PSIA 1.
Charging/letdown mismatch or measured RCS leakage indicates greater than 50 gpm but less than avaihble charging capacity.
1.
RCS leakage greater than available than 50 gpm and greater than available charging capacity.
QB 2.
Loss of RCS subcooled margin due to RCS leakage (saturated conditions).
1.
Containment High Range Radiation monitor greater than 1 46 X 10s R/hr (IfCHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
QB 2.
Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site sun/eys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A,B,C,orDbelow:
A.
1000 mrem/hr (total dose rate)
B.
1000 mrem (total dose - TEDE)
C.
5000 mrem/hr (thyroid dose rate)
D.
5000 mrem (thyroid dose - CDE)
Lhhif(any two of the folloviing~xi and the third is imminent).
1.
Fuel element failure (confirmed DEQ l-131 activity greater than 275 IiCI/mL).
~N 2.
LOCAorTuberuptureon unlsolable steam generator.
~N 3.
Containment Integrity Breached.
~NT Also refer to 'Potential Core Melt'vent/Class 6.A.
/RNRC EP3:4 3-5 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSlFICATIONTABLE EVENT/CLASS 1.B.
~BN
~RMA
~PRiMARYT
~EQNDAfIY
~LEAK RAT UNUSUALEVENT R
PRI/
E L
k 1.
Measured RCS to secondary leakage exceeds Tech. Spec.
limits.
AND 2.
Secondary plant activity is detected.
ALERT R
i r
filr ft n r t rt ITHIN char in m
i with l e~iff.site w r 1.
Measured RCS to secondary leakage greater than Tech.
Spec. Umits and within charging pump capacity.
AND 2.
Secondary plant activity is detected.
~ND 3.
Loss of both Non-Vital 4.16 KV buses.
R i filr ft m nrtr tube REATERTHAN h r in
~um >~ca acittf}
1.
Measured RCS to secondary leakage greater than charging pump capacity.
~ND 2.
Secondary plant activity is detected.
SITE AREA EMERGENCY i
r failure of stea nrtrt R AT THAN r in m
with lo f ff-it w r 1.
Measured RCS to secondary leakage is greater than charging pump capacity.
~ND 2.
Secondary plant activity is detected.
AND 3.
Loss of both Non-Vital 4.16 KV buses.
R i fiir f t m nrtr t
REATER THAN r in m
i with t mr I
~in r err,~
1.
Measured RCS to secondary leakage greater than charging pump capacity.
AND 2.
Secondary plant activity is detected.
AND 3.
Secondary steam release in progress from affected generator.
(e.g., ADVs, Stuck Steam Safety(s), or Unisolable Leak.)
GENERAL EMERGENCY Loss of 2 of the 3 fission roduct arri withimmin nt I f th
~thir (any two of the following exist and the third is imminent).
1.
Fuel element failure (confirmed DEQ l-131 activity greater than 275 pCi/mL).
~ND 2.
LOCAor Tube rupture on unisolable steam generator.
AND 3.
Containment integrity breached.
NOTE Also refer to 'Potential Core Me!t'vent/Class 6.A.
/RNRC EP3I4 3-6 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS 1.C.
LOSS OF SECONDARY COOLANT UNUSUALEVENT Ra id e re urizationof
~ondan~lant 1.
Rapid drop in either steam generator pressure to less than 600 psia.
ALERT M
r t
ml kwith REAT RTHAN1 m
rim n
I k
1.
Rapid drop in either steam generator pressure to less than 600 psia.
AND 2.
Known pri/sec leak of greater than 10 gpm.
~ND 3.
Secondary plant activity is detected.
Total loss of feedwater 1.
No main or auxiliary feedwater flowavailable for greater than 15 minutes when required for heat removaL AND 2.
Steam Generator levels are less than 40% wide range.
SITE AREA EMERGENCY Maorst amleakwith RE T R HAN rn ri n
I ka nd fuel ini td 1.
Rapid drop in either steam generator pressure to less than 600 psia.
~ND 2.
Known pri/sec leak of greater than 50 gpm.
~ND 3.
Secondary plant activity is detected.
AND 4.
Fuelelementdamageis indicated (Refer to 'Fuel Element Failure'vent/Class 4.A).
TL F with
-thr h
lin
~initi t d 1.
No main or auxiliary feedwater flowavailable.
AND 2.
PORV(s) have been opened to facilitate core heat removal.
GENERALEMERGENCY releas has rr ri i
r ress r ultin in 1.
Containment High Range Radiation monitor greater than-1.46 X 10'/hr (IfCHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
QR 2.
Performance of EPIP%9 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C, or D below:
A.
1000 mrem/hr (total dose rate)
B.
1000 mrem (total dose - TEDE)
C.
5000 mrem/hr (thyroid dose rate)
D.
5000 mrem (thyroid dose - CDE)
Loss of 2 of the fission roduct barriers with imminent loss of th third (any two of the following~xi and the third is imminent).
1.
Fuel element failure (confirmed DEQ I-131 actiVitygreater than 275 pCi/mL).
~ND 2.
LOCA or Tube rupture on unisolable steam generator.
AND 3.
Containment Inte ri Breached.
NOTE Also refer to 'Potential Core Melt'vent/Class 6.A.
EP3:4 3-7 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS UNUSUALEVENT i I i
I ALERT Ar lea h
rr ri i SITE AREA EMERGENCY ri in GENERAL EMERGENCY rr rl i
QFFQQNT
~EE~AI=,
1.
Plant effluent monitor(s) exceed alarm setpoint(s).
~N 2.
Confirmed analysis results for gaseous or liquid release which exceeds ODCM limits.
~O Ifanalysis is not available within one hour, and it is expected that release is greater than ODCM limit, dassify as +~~I.
gVVN:'
r h
is 10 times the
~ffli~nflr+I 1.
Plant effluent monitor(s) significantly exceed alarm setpoints.
AND 2.
Confirmed analysis results for gaseous or liquid release which NOTE Ifanalysis is not available viithinone hour, and it is expected that release is equal to or greater than 10 times ODCM limit,dassify as
~T'.
r r
r I in in 1.
Containment High Range Radiation Monitor greater than 7.3 X 10'/hr (Post-LOCA monitors indicate between 100 and 1000 mR/hr, ifCHRRM inoperable).
QQ 2.
Measured Dose Rates or Off-site Dose Calculation (EPIP-09) worksheet values at one mile ln excess of:
A. 50 mrem/hr (total dose rate) or 250 mrem/hr (thyroid dose rate) for 1/2 hour.
QB B. 500 mrem/hr (total dose rate) or 2500 mrem/hr (thyroid dose rate) for two minutes at one mile.
r r
r I in in 1.
Containment High Range Radiation monitor greater than 1.46 X 10'/hr (IfCHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
QQ 2.
Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C, or D belovr.
A.
1000 mrem/hr (total dose rate)
B.
1000 mrem (total dose - TEDE)
C.
5000 mrem/hr (thyroid dose rate)
D.
5000 mrem (thyroid dose - CD ODCM - Refers to Chemistry Procedure C-200, 'Off-site Dose Calculation Manual (ODCM).
/RNRC EP3I4 3-8 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS
~VII
~PNT UNUSUALEVENT ALERT i
ii Ivl ri m
n mi inwhi I
v r I nin h
r f
i iv ri I SITE AREA EMERGENCY GENERAL EMERGENCY 1.
Anyvalid area monitor alarm from indeterminable source with meter near or greater than fullscale deflection (10'R/hr).
QQ 2.
Unexpected plant iodine or particulate airborne concentration of 1000 DACas seen in routine surveying or sampling.
QB 3.
Unexpected direct radiation dose rate reading or unexpected airborne radioactivity concentration from an undeterminable source in excess of 1000 times normal levels.
3.
PIIIE XPLO ION rii i
'hi h
wr I
i rr n f
n x
I I n wi hln h
wnr nrll Ar
~nfLnnrll,~flr 1.
Potentially affecting safety systems.
~N 2.
Requiring off-site support in the opinion of the NPS/EC.
r/
m nn wihin h Pr Ar x
I Inwhih ff In gfKEQiin ir mrmiin h
n i
I m
i rn r
in r
I v r m
f imnfrm I 'n h
inrn r
in I
Refer to 'Potential Core Melt'vent/Class 6.A.
~NT Explosion is defined as a rapid chemical reaction resulting in noise, heat, and the rapid expansion of gas.
/RNRC EP3:4 3-9 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS 4A. jgg~~E
~IQQg UNUSUALEVENT ul I
n 1.
Processmonitorsorarea radiation surveys indicate increased letdown activity
~N 2.
Confirmed RCS sample indicating:
A. Coolant activity greater than the Tech Spec limitfor iodine spike (Tech Spec Figure 3.4-1.).
~O B. Coolant activitygreater than 100/E pCi/gram specific activity.
~T Ifanalysis is not available within 1 hour, and it is expected that activity is greater than Tech Spec limit, dassify as~
~NT'.
ALERT F
I lmnfilr 1.
Process monitors or area radiation surveys indicate increased letdown activity and confirmed RCS Samples indicating DEQ I-131 activity greater than or equal to 275 pCI/mL
~NO Ifanalysis is not available within 1 hour, and it is expected that RCS activity for DEQ 1-131 is greater than 275 pCi/mL, dassify as an SITE AREA EMERGENCY I m n f il r wit n
t r
Iin 1.
RCS DEQ I-131 activity greater than or equal to 275 pCi/mL.
~ND 2.
Highest CET per core quadrant indicates greater than 10'F superheat or 700'F.
GENERALEMERGENCY I
ri''I I r
Itin in Containment High Range Radiation monitor greater than 1.46 X 10'/hr (IfCHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
QR 2.
Performance of EPIP%9 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C, or D below:
A.
1000 mrem/hr (total dose rate)
B.
1000 mrem (total dose - TEDE)
C.
5000 mrem/hr (thyroid dose rate)
D.
5000 mrem (thyroid dose - CDE)
F Ih n Iin i
esult inth r I f
di ivi I
nt inm n rF I
Handlin 8 il in 1.
NPS/EC determines that an irradiated fuel assembly may have been damaged.
~ND 2.
Associated area or process radiation monitors are in alarm.
r m
t irr i
li ContainmentorF elH n Iin 1.
Affected area radiation monitor levels greater than 1000 mR/hr.
AND 2.
Major damage to more than one irradiated fuel assembly.
QQ 3.
Major damage resulting from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.
/RNRC EP3:4 3-10 SL Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS 5.A.
QAA'~QAl<g UNUSUALEVENT nfirmed rth uake ha 1.
Aconfirmed earthquake has been experienced within the Owner Controlled Area.
QQ 2.
An earthquake is detected by plant seismic monitor instruments or other means.
ALERT A
nfirm rth k
h occurred 1.
Aconfirmed earthquake occurs which registers GREATER THAN0.05 g within the Owner Controlled Area QR 2.
A confirmed earthquake has occurred that could cause or has caused trip of the turbine generator or reactor.
SITE AREA EMERGENCY nfirm rth k
h gcg~rr II 1.
Aconfirmed earthquake occurs which registers GREATER THAN0.1 g within the Owner Controlled Area and the plant not in cold shutdown.
QR 2.
A confirmed earthquake has occurred that has caused loss of any safety system function (Le., both trains inoperable).
GENERALEMERGENCY NOTE Refer to 'Potential Core Melt'vent/Class 6.A.
5.B.
HIIRRI~AN n Wmin 1.
Confirmed humcane warning is in effect.
Hurricanew min withwind n r
~ded s bess 1.
Confirmed humcane warning is in effect and winds are expected to exceed 175 mph within the Owner Controlled Area.
NOTE At FPL's request, NOAAwill provide an accurate projection of wind speeds on-site 24 hours prior to the onset ot hurricane force winds. Ifthat projection is not available within 12 hours ot entering into the warning, classify the event using current track and wind speeds to project on-site conditions.
For example, projected on-site wind speed would be less than maximum hurricane wind speed ifthe track is away from PSL H rri n
w min with viin R AT RTHAN i n i
1.
Plant not at cold shutdown.
AND 2.
Confirmed hurricane warning is in effect and winds are expected to exceed 194 mph within the Ovmer Controlled Area.
NOTE At FPL's request, NOAAwill provide an accurate projection of viind speeds on-site 24 hours prior to the onset of hurricane torce winds. Ifthat projection is not available within 12 hours of entering into the warning, dassify the event using current track and wind speeds to project on-site conditions.
For example, projected on-site wind speed would be less than maximum hurricane viind speed ifthe track is away trom PSL.
NOTE Refer to 'Potential Core Melt'vent/Class 6.A.
/RNRC EP3:4 3-11 St. Lucie, Rev. NRC DRAFT

~
~
!'VENT/CLASS 5.C. ~TNA~
5.0.
~N(~RMA W~AT ~VFQ EP3I4 UNUSUALEVENT ril r
n I
vl ii r
ffin 1.
Low intake canal level of -10.5 ft. MLWfor 1 hour or more.
QQ 2.
Visual sightings by station personnel that water levels are approaching storm drain system capacity.
TABLE3-1 EMERGENCY CLASSIFICATIONTABLE SITE AREA EMERGENCY ALERT rikin h Pwr I
w r
h n
I v
niin in ilr f
h n
iw granii ~n 1.
The storm drain's capacity is exceeded during hurricane surge or known flood conditions.
QQ 2.
Low Intake canal level of -10.5 ft. MLWfor 1 hour or more viith emergency barrier valves open.
1.
Flood/surge water tevel reaching elevation+19.5 ft.
(turbine building/RAB ground floor).
QQ 2.
Low intake canal level has caused the loss of all ICW flow.
3-12 GENERAL EMERGENCY EQIK Refer to 'Potential Core Melt'vent/Class 6.A.
St. Lucie, Rev. NRC DRAFT
/RNRC

~
~
'f I II tgq 1

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE NOTE Activation of the Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification.
EVENT/CLASS 6.A.
LNNI~AcjgQ
~PTF~NTIA QQ~MIT (Page 1 of 2)
UNUSUALEVENT mn h
I In ni n
whi w
n ln W
i ffn I
I gLi~hriii~
ALERT Emer en d mnth n
niin ni I xi whi v
thlevlf f
h SITE AREA EMERGENCY mr n
mn h
i r'ni'n xi whi r
nifi n
r in ln n
n n r I
m nn r GENERAL EMERGENCY r
n i r'n h
n niin xi h
mk I
fi r rn un i
i' h
ri
~~l~li ly (Any core melt situation.)
1.
The plant is shutdown under abnormal conditions (e.g.,
exceeding cooldown rates or primary system pipe cracks are found during operation).
QQ 2.
Any plant shutdovm required by Technical Specifications in which the required shutdown Is not reached within action limits.
1.
LOCAwith failure of ECCS leading to severe core degradation or melt.
QQ 2.
LOCAwith initiallysuccessful ECCS and subsequent failure of containment heat removal systems for greater than 2 hours.
QQ 3.
Total loss of feedwater followed by failure of once-through-cooling (ECCS) to adequately cool the core.
QQ 4.
Failure of off-site and on-site power along with total loss of emergency feedwater makeup capability for greater than 2 hours.
QQ 5.
ATWS occurs which results in core damage or causes failure of core cooling and make-up systems.
QQ 6.
Any major Internal or external event (e.g., fire, earthquake or tornado substantially beyond design basis) which in the EC's opinion has or could cause massive damage to plant systems resulting in any of the above.
(continued on next page)
/RNRC EP3:4 3-13 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE A ~
EVENT/CLASS 6.A
~IN R~AEIED
~PTENTtAL QQRE MELT (Page 2 of 2)
UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
~NOTE
: 1. Most likelycontainment failure mode is melt-through with release of gases only. Quicker releases are expected for failure of containment isolation system.
: 2. General Emergency must be declared for the above listed events.
The likelihood of corrective action (repair of AFW pump, etc.) should not be considered.
on-site A wer ca bili 1.
Loss of off-site AC power.
QR 2.
Loss of capability to power at least one vital 4.16 kv bus from a~n available emergency diesel generator.
t ti nBI k
t t
I sofA 1.
Loss of off-site AC power.
AND 2.
Failure of both emergency diesel generators to start or load.
L f lion-siteD w r 1.
DropinAandBDCbus voltages to less than 70 VDC.
tation Bl k u otal Lo f A f r REAT RTHAN1 minut 1.
Loss of off-site AC power.
AND 2.
Sustained failure of both emergency diesel generators to start or load.
AND 3.
Failure to restore AC power to at least one vital 4.16 kv bus within 15 minutes.
NOTE Refer to 'Potential Core Melt'vent/Class 6.A.
Loss of ail vital on-site D for reater than 1
minutes 1.
SustaineddropinAandBDC bus voltages to 70 VDC for greater than 15 minutes.
/RNRC EP3:4 3-14 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS
~ONTRO
~FN~TII~N UNUSUALEVENT ALERT f In ntrlFn in 1.
Complete loss of any function needed for plant cold shutdown.
QQ 2.
Failure of the Reactor Protection System to bring the reactor subcritical when needed.
QQ 3.
Control Room is evacuated (for other than drillpurposes) viith control established locally at the Hot Shutdown Control Panel.
f h t wn Iin 1.
Complete loss of functions needed to maintain cold shutdown.
A. Failure of shutdown cooling systems, resulting in loss of cold shutdown conditions.
~N B. RCS subcooiing can not be maintained greater than O'.
SITE AREA EMERGENCY Criti I
f Pl n ntr
~n~ti n 1.
Loss of any function or system which, in the opinion of the Emergency Coordinator, predudes placing the plant in Hot Shutdown.
QQ 2.
FailureoftheRPStotiipthe reactor when needed, and operator actions fail to bring the reactor subcritical.
QB 3.
Control Room is evacuated (for other than drill purposes) and control cannot be established locally at the Hot Shutdown Control Panel within 15 minutes.
GENERALEMERGENCY Refer to 'Potential Core Melt'vent/Class 6.A.
S.B. LOSS OF ALARMS/
~MONIT RIN i nifi n
I f ffl n
mmni tin i
i i
n I
I t
whi im ir r
n mn 1.
Loss of effluent or radiological monitoring capability requiring plant shutdown.
QB
: 2. Lossofallpnmary~nbackup communication capability with off-site locations.
QQ 3.
Unplannedlossofmost (greater than 75%) or all safety system annunciators for greater than 15 minutes.
1.
Unplanned loss of glI safety system annunciators.
~N 2.
Plant transient in progress.
~L~fl~rm 1.
Inabilityto emergency monitor a significant transient in progress.
Significant transient examples include: Reactor trip, turbine runback greater than 25%
and thermal oscillations greater than 10%.
/RNRC EP3:4 3-15 SL Lucie, Rev. NRC DRAFT

A

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS OA ~ICRAFT
~~IL UNUSUALEVENT n
I lrr
'i 1.
Aircraftcrash in the Owner Controlled Area or unusual aircraft activity over facilitythat in the opinion of the NPS/EC, could threaten the safety of the plant or personnel.
T in in nnfilr ALERT ir i
il i 1.
Aircraftcrash in the Power Block.
QQ 2.
Visual or audible Indication of missile impact on the Power Block.
VI I I i
h
'n n
n r
SITE AREA EMERGENCY D m vi I
m fr gllr;ryt~mI i~i 1.
Aircraftcrash in the Power Block damaging vital plant systems.
QQ 2.
Damage resulting in loss of safe shutdown equipment from any missile.
GENERALEMERGENCY 9.C. ~TXI~
ni r
I i
wn r
I h
I ff I n n
f f
xi rflmm I
in ni II ff in I n T xi r
mm I
i in vi I
r mrmiin h
n in f
I I
imn n
r din r
I KGllEXX T~HgfQ'TY Th II h
ri F r i
n n
r fh i
I 1.
Bomb threat 2.
Attack threat S.
Civildisturbance 4.
Protected Area intrusion 5.
Sabotage attempt 6.
Internal disturbance 7.
Vitalarea intrushn 8.
Security force strike I
M Yh n
II h
ri F
fin In h f
RITYEMER EN Y nv Ivin immin n n
h nrlr r
r r
vi I
h ri fh fin in h f
r fl kvrfh ln I
I i
h r
r n
I I
EP3I4 3-16 St. Lucie, Rev. NRC DRAFT

CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9809090273 DOC.DATE: 98/08/31 NOTARIZED: NO FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co.
50-389 St.'ucie Plant, Unit 2, Florida Power S Light Co.
AUTH.NAME AUTHOR AFFILIATION STALL,J.A.
Florida Power S Light Co.
RECIP.NAME RECXPIENT AFFILIATION Records Management Branch (Document Control Desk)
DOCKET 05000335 05000389

==SUBJECT:==
Requests approval, prior to implementation of change to plant C
radiological emergency plan. Proposed change clarifies criteria used in classification of radiological emrgency.
A Attachment 1 provides explanation of changes.
T DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
Emergency Preparedness Plans, 'Implement'g Pro edures, CE NOTES:
G RECIPIENT ID CODE/NAME PD2-3 PD INTERNAL: AEOD/HAGAN,D NRR/DRPM/PERB EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 RECXPIENT XD CODE/NAME GLEAVES,W CENTER 01 NUDOCS -AB NRC PDR COPIES LTTR ENCL 1
1 2
2 1
1 1
1 NOTE TO ALL "RIDS n RECIPIENTS PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COP'IES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 9
ENCL 9

Florida Power & Light Company,6351 S. Ocean Drive, Jensen Beach, FL34957 August 31, 1998 L-98-200 10 CFR 550.54(q)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Pro osed Chan e to Emer enc Plan Table 3-1: Classification of Emer encies Pursuant to 10 CFR 50.54(q), Florida Power & Light Company (FPL) requests
: approval, prior to implementation, of a change to the St. Lucie Plant Radiological Emergency Plan.
The proposed change clarifies the criteria used in the classification of a radiological emergency.
Emergency action levels remain consistent with the classification criteria currently approved by the NRC.
Attachment 1 provides an explanation of changes to the emergency classification table contained in the St. Lucie Plant Radiological Emergency Plan, Table 3-1. provides a draft revision of Table 3-1 as it would appear in the Radiological Emergency Plan.
Vertical lines are used to indicate changes to the table.
The proposed change was reviewed by the St. Lucie Plant Facility Review Group on July 14, 1998.
On receipt of approval from the NRC of the proposed change, FPL willrevise the St:
Lucie Plant Emergency Plan and Emergency Plan Implementing Procedure EPIP-01 to implement the revised classification criterion.

Ifyou have any questions, please contact Mr. Ed Weinkam at 561-467-7162.
/j
'Sincerely, J. A. Stall Vice President St. Lucie Nuclear Plant Attachment cc:
Regional Administrator, USNRC Region II (2 copies)
Senior Resident Inspector, USNRC, St. Lucie Plant 9809090273 98083i PDR ADQCK 05000335 F
PDR an FPL Group company

Attachment 1
Explanation of Proposed Changes to St. Lucie Radiological Emergency Plan Table 3-1; Emergency Classification Table

==Background:==
Emergency Classification Table 3-1 (Revision 34 of the Emergency Plan) was reviewed to identify sections where the descriptive
, instruction to licensed operators and Plant management could be improved. SpeciTically, the review addressed areas where clarification could be provided to emergency action levels without changing the intent of the classiTication criteria. Regulatory guidance and industry standards have been consulted as part of this review. The following changes are proposed:
Event/Class E Plan Rev.34 Current EPlan Rev.DRAFT Pro osed ReasonforChan e
1.A Abnormal Primary Leak Rate No CAUTIONstatement UNUSUALEVENT
: 2. Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below ~1600 ele.
CAUTION: THIS SECTION SHOULD NOT BE USED FOR STEAM GENERATOR TUBE LEAK/RUPTURE.
UNUSUALEVENT
: 2. Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below:
Unit 1 -1600 sia Unit 2 -1736 sia Clarify difference between classification criteria for primary/secondary leakage.
Relief valve settings different for Units 1 and 2.
ALERT
.1. Charging/letdown mismatch or measured RCS leakage indicates greater than 50 gpm but less than 132 gpm.
ALERT
: 1. Charging/letdown mismatch or measured RCS leakage indicates greater than 50 gpm but less than available char in ca aci Current section does not recognize loss of charging capacity and conflicts with Site Area Emergency section.

Event/Class E Plan, Rev. 34 Current E Plan, Rev. DRAFT Pro osed 1.A Abnormal Primary Leak Rate (continued) 1.8 Abnormal Primary to Secondary Leak Rate SITE AREA EMERGENCY
: 1. RCS leakage greater than 132 gpm occurring with RCS pressure above HPSI shutoff head.
OR
: 2. RCS leakage greater than available makeup occurring with RCS pressure below HPSI shutoff head.
OR
: 3. Loss of RCS subcooled margin due to RCS leakage (saturated conditions).
OR
: 4. Containment High Range Radiation Monitors indicate 7.3 x 10'/hr (ifCHRRM inoperable, Post-LOCA monitors indicate.
between 100 and 1000 mR/hr).
SITE AREA EMERGENCY Ra id failure of steam enerator tube s GREATERTHAN char in um ca aci with steam release in ro ress
: 3. Secondary steam release in progress from affected generator (i.e., ADVs, Steam Safety(s), or Unisoiable.)
SITE AREA EMERGENCY
: 1. RCS leakage greater than 50 gpm and greater than available charging capacity.
OR
: 2. Loss of RCS subcooled margin due to RCS leakage (saturated conditions).
SITE AREA EMERGENCY Ra ldfailureofsteam eneratortube s
GREATER THANchar in um ca aci with steam release in ro ress
: 3. Secondary steam release in progress from affed ed generator ~e.. ADVs stuck steam safe s
unlsolable
~leak Current revision does not recognize loss of charging capability in some cases where leakage is less than 132 gpm.
Current revision does not ctadfy credit for normal makeup (charging) only or any makeup.
Proposed revision provides for clear classification criteria for LOCAgreater than 50 gpm and greater than (normal) charging capacity, which is consistent with NUREG guidance and industry examples.
Criteria for radiation monitor readings are identified in
- Event/Class 2.A (Uncontrolled Effluent Release).
Current revision caused confusion to users, specifically concerning "unisolable status of slight-release potential from equipment (such as steam driven AFW).
Proposed revision provides additional clarification to user on types of secondary steam releases to be considered when classifying event.

Event/Class 2.A Uncontrolled Effluent Release
: 3. Fire E Plan Rev. 34 Current SITE AREA EMERGENCY
: 2. Measured Dose Rates or Offsite Dose Calculation (EPIP-09) worksheet values at one mile in excess of:
A. 50mrem/hr(totaldose TEDE) or250 mrem/hr (thyroid dose CDE) for I*
hour.
OR B.
500 mrem/hr (total dose TEDE) or 2500 mrem/hr (thyroid dose CDE) for two minutes at one mile.
UNUSUALEVENT Uncontrolled fire within the plant lasting more than 10 minutes.
E Plan Rev. DRAFT Pro osed SITE AREA EMERGENCY
: 2. Measured Dose Rates or Offsite Dose Calculation (EPIP-09) worksheet values at one mile in excess of:
A. 50 mrem/hr (total dose ~rate or 250 mrem/hr (thyroid dose ~rate for
/~ hour.
OR B. 500 mrem/hr (total dose ~rate or 2500 mrem/hr (thyroid dose ~rate for two minutes at one mile.
UNUSUALEVENT Uncontrolled fire within the power block lasting more than 10 minutes.
Reason for Chan e
Confusion by users on dose rates versus total dose.
Proposed revision provides clear criteria based on dose rate.
Use of "power block provides clear description of structures of equipment that should be considered in this classification.
Power block" is specifically defined in EPIP-01.
Explosion No NOTE in section.
NOTE'XPLOSION IS DEFINED AS A RAPID CHEMICAL REACTION RESULTING IN NOISE HEAT AND THE RAPID EXPANSION OF GAS.
NOTE provides clear definition of explosion event.

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e
: 3. Explosion (continued)
ALERT Damage to facilityby explosion which affects plant operation.
SITE AREA EMERGENCY Severe damage to safe shutdown equipment from explosion.
ALERT Damage to structures/com onents within the Protected Area by explosion which affects plant operation.
SITE AREA EMERGENCY Severe damage to safe shutdown equipment from explosion ~i.e.
both trains rendered ino erable Proposed revision provides clear identification of the location (Protected Area) where consideration for classification of explosions occur.
Proposed revision provides clear criteria for the meaning of severe damage to safe shutdown equipment, which applies regulatory guidance definition for loss of equipment functions.
4.B Fuel Handling Accident SITE AREA EMERGENCY Major damage to irradiated fuel in Containment or Fuel Handling Building 1.
Step increase in the reading of radiation monitors in the plant vent and/or in the Fuel Handling Building AND 2.
Damage to more than one irradiated fuel assembly.
OR 3.
Uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.
SITE AREA EMERGENCY Major damage to irradiated fuel in Containment or Fuel Handling Building Affected area radiation monitor levels reater than 1000 mr/hr.
AND
~2.
Ma or Damage to one or more irradiated fuel assemblies OR 3.
Ma or dama e resultin from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool Current revision does not provide specific radiation dose rate threshold.
Current revisiori criteria requires knowledge of extent of damage
("more than one irradiated fuel assembly" ) which will likely not be known.
Proposed revision provides specific radiation dose rate threshold (consistent with other classification criteria) and does not limitclassification based on unknown extent of damage.

Event/Class 5.A Earthquake E Plan Rev. 34 Current UNUSUALEVENT
: 2. An earthquake is detected by plant seismic monitor instruments.
ALERT A confirmed earthquake occurs which registers GREATER THAN 0.05 g.
E Plan Rev. DRAFT Pro osed UNUSUALEVENT 2 An earthquake is detected by plant seismic monitor instruments or other means.
ALERT A confirmed earth uake has occurred 1.
A confirmed earthquake occurs which registers GREATER THAN 0.05 g within the Owner Controlled Area.
OR 2.
A confirmed earth uake has occurred that could cause or has caused a tri of the turbine enerator or reactor.
Reason for Chan e
Current classification does not provide for classification based on information received by other (non-plant) seismic monitors, such as from other nuclear sites, colleges, or scientiTic monitoring equipment.
The current revision does not consistently identify the location of the increased seismic activity (within the Owner Controlled Area, as in UNUSUALEVENT).
The proposed revision relates the measurement of seismic activity to the Owner Controlled Area and provides for direct indications for effects of the earthquake on plant conditions (turbine or reactor trip).

Class/Event 5.A Earthquake (continued)
E Plan Rev. 34 Current SITE AREA EMERGENCY A confirmed earthquake occurs which registers GREATER THAN 0.1 g. with plant not in cold shutdown.
E Plan Rev. DRAFT Pro osed SITE AREA EMERGENCY A confirmed earth uake has occurred 1.
A confirmed earth uake occurs which re isters GREATER THAN 0.1
. within the Owner Controlled Area and the lant is not in cold shutdown.
OR Reason for Chan e
The current revision does not consistently identify the location of the increased seismic activity (within the Owner Controlled Area, as in UNUSUALEVENT).
The proposed revision relates the measurement of seismic activity to the Owner Controlled Area and provides for direct indications for effects of the earthquake on plant conditions (loss of safety related functions).
2.
A confirmed earth uake has occurred that has caused loss of an safet related s stem function i.e. both 5.C Tornado ALERT Any tornado striking facility.
: ALERT, Any tomedo striking tahe ower block.
The current revision did not identify specific affected areas of the plant to be considered for a tornado strike.
Use of "power block" provides clear description of structures of equipment that should be considered in this classification.
Power block is specifically defined in EPIP-01.

Event/Class 6.A Increased Awareness or Potential Core Melt E Plan Rev. 34 Current ALERT Emergency Coordinator's judgement that plant conditions exist which warrant:
1.
Increased awareness and activation of Emergency Response personnel.
E Plan Rev. DRAFT Current ALERT Emergency Coordinator's judgement that plant conditions exist which have a otential to de rade the level of safe at the plant.
Reason for Chan e
The current revision causes confusion to whether use of emergency response facilities or activation of any emergency response personnel in its self justifies ALERT classification.
Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of an ALERT.
SITE AREA EMERGENCY Emergency Coordinator's judgement that plant conditions exist which warrant:
: 1. Activation of emergency response facilities and monitoring teams or a precautionary notification of the public near the site.
SITE AREA EMERGENCY 1.
Emergency Coordinator's judgement that plant conditions uncontrollable manner.
The current revision causes confusion to whether use of emergency response facilities in its se)f justifies SITE AREA EMERGENCY classification.
(Classification of SITE AREA EMERGENCY always results in notification of the public.)
Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of a SITE AREAEMERGENCY.
GENERAL EMERGENCY 2.
LOCA with initiallysuccessful ECCS and subsequent failure of containment hear removal systems forseveral hours.
GENERALEMERGENCY 2.
LOCAwith initiallysuccessful ECCS and subsequent failure of containment heat removal hours.
Current revision does not contain specific time criteria in classification considerations.
Proposed revision provides specific time span, after which a GENERAL EMERGENCY classification is warranted.

Event/Class 6.A Increased Awareness or Potential Core Melt (continued)
E Plan, Rev. 34 Current GENERAL EMERGENCY
: 4. Failure of off-site and on-site power along with loss of emergency feedwater makeup capability for several hours.
E Plan, Rev. DRAFT Pro osed GENERALEMERGENCY
: 4. Failure of off-site and on-site power along with loss of emergency feedwater makeup capability for 8
Reason for Chan e
The current revision causes confusion with user in regard to what is "emergency feedwater".
The plant does not designate any equipment as'emergency feedwater.
Current revision does not contain specific time criteria in classification considerations.
The proposed revision provides clear indication that ifthere is no feedwater for greater than 2 hours, then a GENERAL EMERGENCY cIassification is warranted.
7.A Loss of Power ALERT
: 2. Failure of both emergency diesel generators to start or synchronize.
SITE AREA EMERGENCY
: 2. Sustained failure of both emergency diesel generators to start or synchronize.
ALERT
: 2. Failure of both emergency diesel generators to start or load.
SITE AREA EMERGENCY
: 2. Sustained failure of both emergency diesel generators to start or load.
Current revision does not address ability of diesel generator to perform its intended function (load onto emergency buses)
Proposed revision provides clear indication that ifthe diesel is not loaded, then classification is warranted.

Event/Class 8.8 Loss of Alarms/Communication/
Monitoring 9.A Aircraft/Missile E Plan, Rev. 34 Current UNUSUALEVENT 3.
Unplanned loss of most or all Safety System annunciators for greater than 15 minutes.
SITE AREA EMERGENCY
: 1. Inability to monitor a significant transient in progress.
ALERT 1.
Aircraftcrash in the Owner Controlled Area damaging plant structures.
OR
: 2. Visual or audible indication of missile impact on plant structures.
E Plan Rev. DRAFT Current UNUSUALEVENT 1.
Unplanned lossofmostigreater t~han 75% or atl Safety System annunciators for greater than 15 minutes.
SITE AREA EMERGENCY
: 1. Inability to e~ffeottvet monitor a significant transient in progress.
NOTE: Si nificant transient exam les include: reactor tri turbine runback reater than 25%
and thermal oscillations reater than 10%.
ALERT block.
OR
: 2. Visual or audible indication of Reason for Chan e
Current revision does not provide for a quantitative value for loss of "most annunciators.
Proposed revision indicates a specific percentage of annunciators lost needed to classify an UNUSUAL EVENT.
Current revision does not provide guidance on degree of ability in which a transient can be monitored in classifying the event.
Current revision does not provide definition of significant transient.
Proposed revision provides additional guidance for the user to determine that, ifa transient can not be effectively monitored, then a SITE AREA EMERGENCY is warranted.
Additionally, examples of significant transients are provided.
Current revision does not provide reference to crash or missile impact to specific plant structures.
Proposed revision provides clear indication (i.e., the power block) where a crash or missile impact would warrant classificatio of ALERT.

Event/Class 9.A Aircraft/Missile (continued)
E Plan Rev.34 Current SITE AREA EMERGENCY 1.
Aircraft crash in the Owner Controlled Area damaging vital plant systems.
OR 2.
Damage to safe shutdown equipment from any missile.
E Plan Rev. DRAFT Pro osed SITE AREA EMERGENCY 1.
Aircraft crash
~to the ower block damaging vital plant systems.
OR 2.
Damage resultin in loss of safe shutdown equipment from any missile.
Reason for Chan e
Current revision does not provide reference to crash or missile impact on specific plant structures.
Proposed revision defines specific area of the plant where damage is considered classifiable.
Proposed revision identifies effect on safe shutdown equipment as criteria for determining classification of SITE AREA EMERGENCY.
Use of power block provides clear description of structures of equipment that should be considered in this classification.
"Power block is specifically defined in procedure.
9.C Toxic or Flammable Gas SITE AREA EMERGENCY Toxic or flammable gas has diffused into vital areas affecting access to or the operation of safe shutdown equipment.
SITE AREA EMERGENCY Toxic or flammable gas has diffused into vital areas compromising the function of safety related equipment (i.e., both trains rendered inoperable)
Current revision caused confusion with user differentiating between ALERT and SITE AREA EMERGENCY. Current revision does not consistently relate loss of safety system function with other classification criteria.
Proposed revision provides clear difference between ALERT and SITE AREA EMERGENCY.
10

ATTACHMENT2 DRAFT REVISION OF ST. LUCIE RADIOLOGICALEMERGENCY PLAN TABLE 3-1 EMERGENCY CLASSIFICATIONTABLE

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS 1A. /~Nfl
/~MA EGG QAAQIQIJi This section shouki NOT be used for a steam generator tube leak/rupture.
UNUSUALEVENT 1.
RCS leakage GREATER THAN 10 gpm as indicated by:
A. Control Room observation QB B. Invenlory balance calculation QB C. Field observation QB D. Emergency Coordinator Judgement QB 2.
Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below:
- Unit 1-1600 PSIA
- Unit 2-1736 PSIA ALERT 1.
Charging/letdovm mismatch or measured RCS leakage Indicates greater than 50 gpm but less than available charging capacity.
SITE AREA EMERGENCY 1.
RCS leakage greater than available than 50 gpm and greater than available charging capacity.
QB 2.
Loss of RCS subcooled margin due to RCS leakage (saturated conditions).
GENERALEMERGENCY 1.
Containment High Range Radiation monitor greater than 1.46 X 10'/hr (IfCHRRM inoperable, Post. LOCAmon!tors greater than 1000 mR/hr).
QB 2.
Performance of EPIP<9 (Off-site Dose Calculations) or measured dose rates from off-site surveys Indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C, or 0 betovc A.
1000 mrem/hr (total dose rate) 8.
1000 mrem (total dose - TEDE)
C.
6000 mrem/hr (thyroid dose rate) 0.
6000 mrem (thyroid dose - CDE) fhh~}(any two of the following~l and the third is imminent):
1.
Fuel element failure (confirmed DEQ 1-131 activity greater than 275 yCI/mL).
hhl2 2.
LOCA or Tube rupture on unlsolable steam generator.
hHQ 3.
Containment Integrity Breached.
HITCH Also refer to 'Potential Core Melt'vent/Class 6.A.
/RNRC EP3:4 3-5 St. Lucie, Rev. NRC DRAFT

0

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS
'I.B.
BBBRRRMMAALL
~PRIMA Y T
~EQNDARY
~AKRATI; UNUSUALEVENT PRI/
'I<
1.
Measured RCS to secondary
" leakage exceeds Tech. Spec.
limits.
~ND 2.
Secondary phnt activity is detected.
ALERT R
i r
filr ft t rt I
IN ri m
~fff-~~it ILr 1.
Measured RCS to secondary leakage greater than Tech.
Spec. Umits and within charging pump capacity.
~ND 2.
Secondary phnt activity is detected.
~ND 3.
Loss of both Non-Vital 4.16 KV buses.
i filr ft m
n tr R
RTHAN r i g~m~ggi~)
1.
Measured RCS to secondary leakage greater than charging pump capacity.
~ND 2.
Secondaiy plant activity is detected.
SITEAREAEMERGENCY R
i r
ilr ft n trt RAT THAN i
m f ff-it r
1.
Measured RCS to secondary leakage is greater than charging pump capacity.
~N 2.
Secondary plant activity is detected.
AND 3.
Loss of both Non-Vital4.16 KV buses.
R i
ilr ft rn nrtr t
s R A RTHAN rin with I
ri 1.
Measured RCS to secondary leakage greater than charging
~
pump capacity.
~ND 2.
Secondary phnt activity is detected.
~N 3.
Secondary steam release in progress from affected generator.
(e.g., ADVs, Stuck Steam Safety(s), or Unisolable Leak.)
GENERALEMERGENCY f
fth fi i
r rri with immin n I
t
~hir (any two of the followingexist and the third is imminent).
1.
Fuel element failure (confirmed DEQ I-131 activity greater than 275 pCi/mL).
~N 2.
LOCA or Tube rupture on unisohbie steam generator.
IitND 3.
Containment integrity breached.
Also refer to 'Potential Core Melt'vent/Chss 6.A.
/RNRC EP3:4 St. Lucie Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS 1.C. ~LQ~F
~QQNDARY QQQPNT UNUSUALEVENT id re uii ti f
ggggn~gllnI 1.
Rapid drop in either steam generator pressure to less than 600 psia.
ALERT RE THAN 1 m
ii I
k 1.
Rapid drop in either steam generator pressure to less than 600 psia.
AND 2.
Known pri/sec leak of greater than 10 gpm.
~ND 3.
Secondary phnt activity is detected.
1.
No main or auxiliary feedwater flowavaihble for greater than 15 minutes when required for heat removal.
~ND 2.
Steam Generator levels are less than 40/o wide range.
SITE AREA EMERGENCY F wit initi t
-thr h
li 1.
No main or auxiliary feedwater flowavaihble.
~N 2.
PORV(s) have been opened to facilitate core heat removal.
R T
THAN ri k
ndf el fI~mgg Indi~tII 1.
Rapid drop in either steam generator pressure to less than 600 psia.
~AN 2.
Known pri/sec leak of greater than 50 gpm.
AND 3.
Secondary plant activity is detected.
~AN 4.
Fuel element damage is indicated (Refer to 'Fuel Element Failure Event/Chss 4.A).
GENERAL EMERGENCY rla ha rr ri in r
r r
itin in 1.
Containment High Range Radiation monitor greater than 1.46 X 10 R/hr (IfCHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
QQ 2.
Performance of EPIP~
(Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, 8, C, or D belovr.
A.
1000 mrem/hr (total dose rate)
B.
1000 mrem (total dose - TEDE)
C.
5000 mrem/hr (thyroid dose rate)
D.
5000 mrem (thyroid dose - CDE)
L I
f the fission r
rri with immin nt I I th
~thir (any two of the following exist and the third is imminent).
1.
Fuel element failure (confirmed DEQ I-131 activity greater than 275 pCi/mL).
~ND 2.
LOCAor Tube rupture on unisolable steam generator.
~ND 3.
Containment Int ri Breached.
~NTE Also refer to 'Potential Core Melt'vent/Class 6.A.
EP3:4 3-7 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS UNUSUALEVENT ALERT SITEAREAEMERGENCY GENERALEMERGENCY 2.A i I I
limi rr I
r Ii 1.
Plant effluent monitor(s) exceed alarm selpoint(s).
~N 2.
Confirmed analysis results for gaseous or liquid release which exceeds ODCM limits.
HQXK Ifanalysis is not available within one hour, and it is expected that release is greater than ODCM limit, dassify as~
~V~
1.
Plant effluent monitor(s) significantly exceed alarm setpoints.
BED 2.
Confirmed analysis results for gaseous or liquid release which HQK Ifanalysis Is not available within one hour, and it is expected that release Is equal to or greater than ~i ODCM limit,dassify as AiKBZ-1.
Containment High Range Radiation Monitor greater than 7.3 X 10 R/hr (Post-LOCA monitors indicate between 100 and 1000 mR/hr, ifCHRRM Inoperable).
QB 2.
Measured Dose Rates or Off-site Dose Calculation (EPIP49) worksheet values at one mile In excess of:
A. 50 mrem/hr (total dose rate) or 250 mrem/hr (thyroid dose rate) for 1/2 hour.
QB B. 500 mrem/hr (total dose rate) or 2500 mrem/hr (thyroid dose rate) for two minutes at one mile.
1.
ContaInment High Range Radiation monitor greater than 1.46 X 10'/hr (IfCHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
QB 2.
Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C,or 0belovr.
A.
1000 mrem/hr (total dose rate)
B.
1000 mrem (total dose - TEDE)
C.
5000 mrem/hr (thyroid dose rate)
D.
5000 mrem (thyroid dose - CD ODCM - Refers to Chemistry Procedure C-200, 'Off.site Dose Calculation Manual(ODCM).'RNRC EP3I4 3-8 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
. 2.8 i
i h
I 1.
Anyvalid area monitor alarm from Indeterminable source with meter near or greater than fullscale deflection (10'R/hr).
QB 2.
Unexpected plant iodine or particulate airborne concentration of 1000 DAC as seen In routine surveying or sampling.
QB
: 3. 'nexpected direct radiation dose rate reading or unexpected airborne radioactivity concentration from an undeterminable source in excess of 1000 times normal levels.
n rii I
I i
hi w r gggg0~II ~ffL I
1.
Potentially affecting safety systems.
hE2 2.
Requiring off-site support In the opinion of the NPS/EC.
i n
h Refer to 'Potenflal Core Melt'venVCtass 6.A.
I wi hi h
wnr rli r
HQK Explosion Is defined as a rapid chemical reaction resulting in noise, heat, and the rapid expansion of gas.
/RNRC EP3:4 3-9 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS 4>
EUElZKhKEE Evil.llBK UNUSUALEVENT 1.
Process monitors or area radiation surveys indicate increased letdown activity
~N 2.
Confirmed RCS sample indicating:
A. Coolant activity greater than the Tech Spec limitfor iodine spike (Tech Spec Figure 3.4-1.).
QQ B. Coolant activity greater than 100/E pCi/gram specific activity.
Ifanalysis Is not available within 1 hour, and it is expected that activity is greater than Tech Spec limit, dassify as~
ALERT I
il 1.
Process monitors or area radiation surveys indicate increased letdown activity and confirmed RCS Samp! es indicating DEQ I-131 activity greater than or equal to 275 yCI/mL Ifanalysis is not available within 1 hour, and it is expected that RCS activityfor DEQ I-131 is greater than 275 pCi/mL, dassify as an KBZ-SITE AREA EMERGENCY I
il 1.
RCS OEQ 1-131 activity greater than or equal to 275 pCi/mL.
2.
Highest CET per core quadrant indicates greater than 10'F superheat or 700'F.
GENERAL EMERGENCY 1.
Containment High Range Radiation monitor greater than 1.46 X 10~ R/hr (IfCHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
QB 2.
Performance of EPIP49 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, 8, C, or D belch.
A.
1000 mrem/hr (total dose rate)
B.
1000 mrem (total dose - TEDE)
C.
5000 mrem/hr (thyroid dose rate)
D.
5000 mrem (thyroid dose - COE) 4,B. @+~AN hGQDKKE lin P~nLfili3ijiilin,.
1.
NPS/EC determines that an irradiated fuel assembly may have been damaged.
~N 2.
Associated area or process radiation monitors are in alarm.
/grig 1.
Affected area radiation monitor levels greater than 1000 mR/hr.
hHQ 2.
Major damage to more than one irradiated fuel assembly.
QB 3.
Major damage resulting from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.
/RNRC EP3:4 3-10 Sl. Wcie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFjCATjONTABLE EVENT/CLASS 5.A. ~A~AK UNUSUALEVENT nfi h
k 1.
A confirmed earthquake has been experienced within the Owner Controlled Area.
QQ 2.
An earthquake is detected by plant seismic monitor instruments or other means.
ALERT firm 1.
A confirmed earthquake occurs which registers GREATER THAN0.05 g within the Owner Controlled Area QQ 2.
A confirmed earthquake has occurred that could cause or has caused trip of the turbine generator or reactor.
SITE AREA EMERGENCY it k
1.
A confirmed earthquake occurs which registers GREATER THAN0.1 g within the Owner Controlled Area and the plant not in cold shutdown.
QQ 2.
A confirmed earthquake has occurred that has caused loss of any safety system function (i.e., both trains inoperable).
GENERALEMERGENCY
~N Refer to 'Potential Core Melt'vent/Class 6.A.
5.B.
ARRI~AN n Wmin 1.
Confirmed hurricane warning is in effect.
Hu '
i with win r
it~in ~i 1.
Confirmed hurricane warning is in effect and winds are expected to exceed 175 mph within the Owner Controlled Area.
~NT At FPL's request, NOAAviill provide an accurate projection of wind speeds on-site 24 hours piforto the onset of humcane force winds. It that projection is not available within 12 hours of entering into the warning, cfassity the event using current track and wind speeds to project on-site conditions.
For example, projected on-site wind speed would be less than maximum humcane wind speed ifthe track is away from PSL R
T AN in i
1.
Plant not at cold shutdown.
~N 2.
Confirmed hurricane warning is in effect and winds are expected to exceed 194 mph within the Owner Controlled Area.
At FPL's request, NOAAwill provide an accurate projection of wind speeds on-site 24 hours prior to the onset of hurricane force winds. Ifthat projection is not avaiiabfe within 12 hours of entering Into the warning, classify the event using current track and wind speeds to project on-site conditions.
For example, projected on-site wind speed would be less than maximum hurricane wind speed it the track Is away trom PSL Refer to Potential Core Melt'vent/Class 6.A.
/RNRC EP3:4 3-11 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS S.C.
~~MA Q UNUSUALEVENT ifi n
f m
i ALERT SITEAREAEMERGENCY GENERAL EMERGENCY HQIE Refer to 'Potential Core Melt'vent/Class 6.A.
5.0. /~~A
~WAT~~
n I
I ii r
Iww r
lw v I ni'.
Low intake canal level of -10$
ft. MLWfor 1 hour or more.
QB 2.
Visual slghtings by station personnel that water levels are approaching storm drain system capacity.
1.
The storm drain's capacity is exceeded during hurricane surge or known flood conditions.
QB 2.
Low intake canal level of -10.5 ft. MLWfor1 hourormorewith emergency barrier valves open.
1.
Flood/surge water tevel reaching elevation+19.5 ft.
(turbine building/RAB ground floor).
QB 2.
Low Intake canal level has caused the loss of all ICW flow.
/RNRC EP3:4 3-12 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE HQIK Activation of the Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification.
EVENT/CLASS 6.A.
~NQfAA'jgQ Qgj'~NTIA
~)ffMQIT (Page 1 of 2)
UNUSUALEVENT n
I h
n i
I w
ninr h
f h ri ffn I
gtt~hri i~
1.
The plant is shutdovm under abnormal conditions (e.g.,
exceeding cooldown rates or primary system pipe cracks are found durfng operation).
QB 2.
Any plant shutdovm required by Technical Specifications in which the required shutdown is not reached within action limits.
ALERT SITE AREA EMERGENCY GENERAL EMERGENCY it xi gg~ifLgLLIIIIIhf,(Any core melt situation.)
1 LOCAvnth failure of ECCS leading to severe core degradation or melt.
QB 2.
LOCAwith initiallysuccessful ECCS and subsequent failure of containment heat removal systems for greater than 2 hours.
QB 3.
Total loss of feedwater followed by failure of once-through-cooling (ECCS) to adequately cool the core.
QB 4.
Failure of off-site and on-site power along with total loss of emergency feedwater makeup capability for greater than 2 hours.
QB 5.
ATWS occurs which results in core damage or causes failure of core cooling and make-up systems.
QB 6.
Any major Internal or external event (e.g., fire, earthquake or tornado substantially beyond design basis) which In the EC's opinion has or could cause.
massive damage to ptant systems resulting in any of the above.
(continued on next page)
/RNRC EP3:4 3-13 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 6A
~IN RF~AED QQTTM~TIA QQRR MELT (Page 2 of 2)
~TE
: 1. Most likelycontainment failure mode is melt-through with release of gases only. Quicker releases are expected for failure of containment isolation system.
: 2. General Emergency must be declared for the above listed events. The likelihood of corrective action (repair of AFW pump, etc.) should not be considered.
7.A.
FP W
f ff-t wr rl f
II n-it A r
1.
Loss of off-site AC power.
QR 2.
Loss of capability to power at least one vital 4.16 kv bus from
~n available emergency diesel generator.
tati nBI t
t I
f 1.
Loss of off-site AC power.
~ND 2.
Failure of both emergency diesel generators to start or load.
f II
- it 1.
DropinAand BDCbus voltages to less than 70 VDC.
tti BI k
tl f
r R AT THA in 1.
Loss of off.site AC power.
~AN 2.
Sustained failure of both emergency diesel generators to start or load.
~N 3.
Failure to restore AC power to at least one vital 4.16 kv bus within 15 minutes.
II 'I I
~ it r
r i
t
~NTE Refer to 'Potential Core Melt'vent/Class 6.A.
1.
Sustained drop in A and 8 DC bus voltages to 70 VDC for greater than 15 minutes.
/RNRC
. EP3:4 3-14 St. Lucie, Rev. NRC DRAFT

TABLE3-1 EMERGENCY CLASSIFICATIONTABLE EVENT/CLASS UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 8>
LQGRQEZLBK QQHXEQI.
~NQ~N S.B.
M I
Q~N~IQ inifi nl f
ffl n
I n
I I
whi i
iii if m r n
1.
Loss of effluent or radiological monitoring capability requiring plant shutdown.
QB 2.
Loss of all primary ggII backup communication capability with off-site locations.
QB 3.
Unpiannedlossofmost (greater than 75%) or all safety system annunciators for greater than 15 minutes.
I
'n 1.
Complete loss of any function needed for plant cold shutdovm.
QB 2.
Failure of the Reactor Protection System to bring the reactor subcnVcal when needed.
QB 3.
Control Room is evacuated (for other than drillpurposes) with control established locally at the Hot Shutdovm Control Panel.
in 1.
Complete loss of functions needed to maintain cold shutdown.
A. Failure of shutdown cooling systems, resulting in loss of cold shutdown condiVons.
B. RCS subcooling cannot be maintained greater than O'.
1.
Unplanned loss of gffi safety system annunciators.
2.
Plant transient in progress.
1.
Loss ofany function or system which, in the opinion of the Emergency Coordinator, predudes pladng the plant in Hot Shutdown.
QB 2.
Failureofthe RPStotripthe reactor when needed, and operator actions fail to bring the reactor subcri Veal.
QB 3,
Control Room is evacuated (forother than drillpurposes) and control cannot be established locally at the Hot Shutdown Control Panel within 15 minutes.
M~Mium 1.
Inabilityto emergency monitor a significant transient in progress.
EQIF Significant transient examples indude: Reactor trip, turbine runback greater than 25%
and thermal osdffatlons greater flail10%.
HQXK Refer to Potential Core Melt'vent/Class 6.A.
/RNRC EP3:4 3-15 St. Lvcie, Rev. NRC DRAFT

s TABLE3-1 EMERGENCY CLASSlFlCATlONTABLE EVENT/CLASS 9>. ~IR RAFF)
~MI I
UNUSUALEVENT 1.
Aircraftcrash ln the Owner Controlled Area or unusual aircraft activityover facilitythat in the opinion of the NPS/EC, could threaten the safety of the plant or personnel.
ALERT Ir I
I 1.
Aircraftcrash fn the Power Block.
QB 2.
Visual or audible Indication of mlssge impact on the Power Block.
SITEAREAEMERGENCV 1.
Aircraftcrash in the Power Block damaging vital plant systems.
QB 2.
Damageresultinginlossof safe shutdown equipment from any missile.
GENERAL EMERGENCV 9B.
IN I
I i
I i
i 9.C. ~T)~l nn n
r II II r
h n
I f
i I
ff i
I I
in 1o. GKLlEZf.
THffg~T II h
fin I
nin n
in i
1.
Bomb threat 2.
Attack threat 3.
Civildistutbance 4.
Protected Area Intrusion 5.
Sabotage attempt 8.
Internal disturbance 7.
Vital area intrusion 8.
Security force strike
/RNRC EP3I4 3-16 St. Lucie, Rev. NRC DRAFT}}