ML17229A852

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

ML17229A852
Person / Time
Site:	Beaver Valley
Issue date:	08/31/1998
From:	Stall J FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-98-200, NUDOCS 9809090273
Download: ML17229A852 (66)

Text

REGULAT ACCESSION NBR:9809090273 CATEGORY 1 DOC.DATE:

SCIL:50-335 St. Lucie Plant, Unit 1, Florida 98/08/31 i

Y INFORM'ATION DISTRIBUTION SYSTEM (RIDS)

NOTARIZED: NO Power E Light Co.

DOCKET 05000335

¹ 50-3S9 St'. Lucie Plant, Unit 2, Florida Power E Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION STALL,J.A. Florida Power E Light Co.

RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 PD 1 1 GLE 1 1 R

~

INTERNAL: AEOD/HAGAN,D 1 1 FILE CENTER 2 2 Y NRR/DRPM/PERB 1 1 STRACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 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

Florida Power & Light Company. 6351 S. Ocean Drive, Jensen Beach, FL34957 August 3'1, 1998 PI@I 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.

Attachment 2 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 CAUTION statement CAUTION: THIS SECTION Clarify difference between Rate SHOULD NOT BE USED FOR classification criteria for STEAM GENERATOR TUBE primary/secondary leakage.

LEAK/RUPTURE.

UNUSUAL EVENT UNUSUAL EVENT Relief valve settings different for Units 1 and 2.

2. Indication of leaking RCS safety or relief 2. Indication of leaking RCS safety valve which causes RCS pressure to drop or relief valve which causes RCS below~1600 sia. pressure to drop below:

Unit 1 -1600 sia Unit 2-1736 sla ALERT ALERT Current section does not recognize loss of charging

1. Charging/letdown mismatch or

1. Charging/letdown mismatch or measured RCS leakage indicates capacity and conflicts with Site measured RCS leakage indicates greater Area Emergency section.

greater than 50 gpm but less than than 50 gpm but less than 132 gpm. available char in ca gelt .

Event/Class E Plan Rev. 34 Current E Plan, Rev. DRAFT Pro osed Reason for Chan e 1.A SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision does not Abnormal Primary Leak recognize loss of charging Rate (continued) 1. RCS leakage greater than 132 gpm 1. RCS leakage greater than 50 capability in some cases where occurring with RCS pressure above HPSI gpm and greater than available leakage is less than 132 gpm.

shutoffhead. charging capacity.

Current revision does not clarify OR

2. RCS leakage greater than available OR

2. Loss of RCS subcooled margin credit for normal makeup (charging) only or any makeup. ~

makeup occurring with RCS pressure due to RCS leakage (saturated Proposed revision provides for below HPSI shutoff head. conditions). clear classification criteria for LOCA greater than 50 gpm and OR greater than (normal) charging capacity, which is consistent with

3. Loss of RCS subcooled margin due to NUREG guidance and industry RCS leakage (saturated conditions). examples.

OR Criteria for radiation monitor readings are identified in

4. Containment High Range Radiation Event/Class 2.A (Uncontrolled Monitors indicate 7.3 x 10'/hr (if CHRRM Effluent Release).

inoperable, Post-LOCA monitors indicate between 100 and 1000 mR/hr).

1.B Abnormal Primary to SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision caused confusion Secondary Leak Rate to users, specifically concerning Ra id failure of steam enerator tube s Ra idfailureofsteam eneratortube s "unisolable status of slight GREATER THAN char in um ca aci GREATER THAN char in um release potential from equipment with steamrelease in ro ress ca acit withsteamreleasein ro ress (such as steam driven AFW).

3. Secondary steam release in progress 3. Secondary steam release in progress Proposed revision provides from affected generator (i.e., ADVs, Steam fromaffecled generatorieeAADDVVas additional clarification to user on stuck steam safe s unisolable types of secondary steam Safety(s), or Unisolable.)

~leak releases to be considered when classifying event.

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 2.A Uncontrolled Effluent SITE AREA EMERGENCY SITE AREA EMERGENCY Confusion by users on dose rates Release versus total dose.

2. Measured Dose Rates or Offsite Dose 2. Measured Dose Rates or Offsite Calculation (EPIP-09) worksheet values at Dose Calculation (EPIP-09) Proposed revision provides clear one mile in excess of: worksheet values at one mile in criteria based on dose rate.

excess of:

A. 50 mrem/hr (total dose TEDE) or 250 mrem/hr (thyroid dose CDE) for ~/i A. 50 mrem/hr (total dose ~rate or hour. 250 mrem/hr (thyroid dose ~rate for

/g hour.

OR OR B. 500 mrem/hr (total dose TEDE) or 2500 mrem/hr (thyroid dose CDE) for B. 500 mrem/hr (total dose ~rate or two minutes at one mile. 2500 mrem/hr (thyroid dose ~rate for two minutes at one mile.

3. Fire UNUSUAL EVENT UNUSUAL EVENT Use of "power block provides clear description of structures of Uncontrolled fire within the plant lasting Uncontrolled fire within the gower equipment that should be more than 10 minutes. block lasting more than 10 minutes. considered in this classification.

"Power block" is specifically defined in EPIP-01.

Explosion No NOTE in section. NOTE: EXPLOSION IS DEFINED NOTE provides clear definition of AS A RAPID CHEMICAL explosion event.

REACTION RESULTING IN NOISE HEAT AND THE RAPID EXPANSION OF GAS.

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e

3. Explosion (continued) ALERT ALERT Proposed revision provides clear identification of the location Damage to facility by explosion which Damage to (Protected Area) where affects plant operation. structures/com onents within consideration for ciassiTieation of the Protected Area by explosion explosions occur.

which affects plant operation.

SITE AREA EMERGENCY SITE AREA EMERGENCY Proposed revision provides clear criteria for the meaning of severe Severe damage to safe shutdown Severe damage to safe shutdown damage to safe shutdown equipment from explosion. equipment from explosion Ji.e. equipment, which applies both trains rendered ino erable . regulatory guidance definition for loss of equipment functions.

4.B Fuel Handling SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision does not provide Accident specific radiation dose rate Major damage to irradiated fuel in Major damage to irradiated fuel in threshold.

Containment or Fuel Handling Building Containment or Fuel Handling Building Current revision criteria requires

1. Step increase in the reading of knowledge of extent of damage radiation monitors in the plant vent 1. Affected area radiation ("more than one irradiated fuel and/or in the Fuel Handling Building monitor levels reater than assembly" ) which will likely not be 1000 mr/hr. known.

AND AND Proposed revision provides

2. Damage to more than one irradiated specific radiation dose rate fuel assembly. ~2. Ma or Damage to one or more threshold (consistent with other irradiated fuel assemblies classification criteria) and does OR not limit classification based on unknown extent of damage.

OR

3. Uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.

3. Ma or dama e resultin from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 5.A Earthquake UNUSUAL EVENT UNUSUAL EVENT Current classification does not

2. An earthquake is detected by provide for classification based on

2. An earthquake is detected by plant plant seismic monitor instruments information received by other seismic monitor instruments. or other means. (non-plant) seismic monitors, such as from other nuclear sites, colleges, or scientific monitoring equipment.

ALERT ALERT The current revision does not consistently identify the location A confirmed earthquake occurs which A confirmed earth uake has of the increased seismic activity registers GREATER THAN 0.05 g. occurred (within the Owner Controlled Area, as in UNUSUAL EVENT).

1. A confirmed earthquake occurs which registers GREATER The proposed revision relates the THAN 0.05 g within the Owner measurement of seismic activity Controlled Area. to the Owner Controlled Area and provides for direct indications for OR effects of the earthquake on plant conditions (turbine or reactor trip).

2. A confirmed earth uake has occurred that could cause or has caused a tri of the turbine enerator or reactor.

Class/Event E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 5.A Earthquake SITE AREA EMERGENCY SITE AREA EMERGENCY The current revision does not (continued) consistently identify the location A confirmed earthquake occurs which A confirmed earth uake has of the increased seismic activity registers GREATER THAN 0.1 g. with plant occurred (within the Owner Controlled not in cold shutdown. Area, as in UNUSUAL EVENT).

1. A confirmed earth uake occurs which re isters The proposed revision relates the GREATER THAM 0.1 . within measurement of seismic activity the Owner Controlled Area to the Owner Controlled Area and and the lant is not in cold provides for direct indications for shutdown. effects of the earthquake on plant conditions (loss of safety related OR 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 The current revision did not ALERT identify specific affected areas of Any tornado striking facility. the plant to be considered for a Any tomario striking ~the ower tornado strike.

block.

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 E Plan Rev. 34 Current E Plan Rev. DRAFT Current Reason for Chan e 6.A Increased ALERT ALERT The current revision causes Awareness or Potential confusion to whether use of Core Melt Emergency Coordinator's judgement that Emergency Coordinator's emergency response facilities or plant conditions exist which warrant: judgement that plant conditions activation of any emergency exist which have a otential to response personnel in its self

1. Increased awareness and activation of de rade the level of safet at the justifies ALERT classification.

Emergency Response personnel. plant.

Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of an ALERT.

SITE AREA EMERGENCY The current revision causes SITE AREA EMERGENCY confusion to whether use of Emergency Coordinator's judgement that emergency response facilities in plant conditions exist which warrant: ~ifs self ustifies SITE AREA

1. Emergency Coordinator's EMERGENCY classification.

judgement that plant conditions (Classification of SITE AREA exist which are si nificantl

1. Activation of emergency response EMERGENCY always results in facilities and monitoring teams or a notification of the public.)

uncontrollable manner.

precautionary notification of the public near the site. Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of a SITE AREAEMERGENCY.

GENERALEMERGENCY GENERAL EMERGENCY Current revision does not contain specific time criteria in

2. LOCA with initially successful ECCS 2. LOCA with initially successful classification considerations.

and subsequent failure of containment ECCS and subsequent failure of hear removal systems for several containment heat removal Proposed revision provides hours. specific time span, after which a hours. GENERALEMERGENCY classification is warranted.

Event/Class E Plan, Rev. 34 Current E Plan, Rev. DRAFT Pro osed Reason for Chan e 6.A Increased GENERAL EMERGENCY GENERALEMERGENCY The current revision causes Awareness or Potential confusion with user in regard to Core Melt (continued) 4. Failure of off-site and on-site power 4. Failure of off-site and on-site what is "emergency feedwater".

along with loss of emergency feedwater power along with loss of ave:gemy The plant does not designate any makeup capability for several hours.

P "

feedwater makeup capability for equipment as'emergency feedwater.

Current revision does not contain specific time criteria in classification considerations.

The proposed revision provides clear indication that if there is no feedwater for'greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then a GENERAL EMERGENCY classification is warranted.

7.A Loss of Power ALERT ALERT Current revision does not address t

ability of diesel generator to

2. Failure of both emergency diesel 2. Failure of both emergency diesel perform its intended function (load generators to start or synchronize. generators to start or load. onto emergency buses)

SITE AREA EMERGENCY SITE AREA EMERGENCY Proposed revision provides clear indication that if the diesel is not

2. Sustained failure of both emergency 2. Sustained failure of both loaded, then classification is diesel generators to start or synchronize. emergency diesel generators to start warranted.

or load.

Event/Class E Plan, Rev. 34 Current E Plan, Rev. DRAFT Current Reason for Chan e 8.8 UNUSUAL EVENT UNUSUAL EVENT Current revision does not provide for a quantitative value for loss of Loss of 3. Unplanned loss of most or all Safety 1. Unplanned loss of most ig rester "most'nnunciators.

Alarms/Communication/ System annunciators for greater than ~than 75% or alt Safety System Monitoring 15 minutes. annunciators for greater than 15 Proposed revision indicates a minutes. specific percentage of annunciators lost SITE AREA EMERGENCY SITE AREA EMERGENCY needed to classify an UNUSUAL EVENT. ~

Current revision does not provide

1. Inability to monitor a significant transient 1. Inability to ~effecttvet monitor a guidance on degree of ability in in progress. significant transient in progress. which a transient can be monitored in classifying the event.

NOTE: Si nificant transient exam les include: reactor tri Current revision does not provide turbine runback reater than 25% definition of significant transient.

and thermal oscillations reater than 10%. Proposed revision provides additional guidance for the user to determine that, if a transient can not be effectively monitored, then a SITE AREA EMERGENCY is warranted. Additionally, examples of significant transients are provided.

9.A Aircraft/Missile ALERT ALERT Current revision does not provide

1. Aircraft crash in the Owner Controlle'd 1. Aircraft crash in the ower reference to crash or missile Area damaging plant structures. block. impact to specific plant structures.

OR OR Proposed revision provides clear indication (i.e., the power block)

2. Visual or audible indication of missile 2. Visual or audible indication of where a crash or missile impact impact on plant structures. would warrant classification of ALERT.

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 9.A Aircraft/Missile SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision does not provide (continued) reference to crash or missile

1. Aircraft crash in the Owner Controlled 1. Aircrah crash ~in the ower impact on specific plant Area damaging vital plant systems. block damaging vital plant structures.

systems.

OR Proposed revision defines specific OR area of the plant where damage is

2. Damage to safe shutdown equipment considered classifiable.

from any missile. 2. Damage resultin in loss of safe shutdown equipment from Proposed revision identifies effect any missile. 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 SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision caused confusion Gas with user differentiating between Toxic or flammable gas has diffused into Toxic or flammable gas has ALERT and SITE AREA vital areas affecting access to or the diffused into vital areas EMERGENCY. Current revision operation of safe shutdown equipment. compromising the function of safety does not consistently relate loss related equipment (i.e., both trains of safety system function with rendered inoperable) 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 CLASSIFICATION TABLE

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITEAREAEMERGENCY GENERALEMERGENCY t.A. ABNIBRMA, r ln T THAN - L R AT R THAN QR IMA~Y~IQ <~in ~~m~ r r r I ln in

1. RCS leakage GREATER THAN 1. Charging/letdown mismatch or 1. RCS leakage greater than 1. Containment High Range 10 gpm as indicated by: measured RCS leakage available than 50 gpm and Radiation monitor greater than CAUTtON indicates greater than 50 gpm greater than available charging 1 46 X 10s R/hr (If CHRRM This section should A. Control Room observation but less than avaihble charging capacity. inoperable, Post-LOCA monitors NOT be used for a QB capacity. QB greater than 1000 mR/hr).

steam generator tube B. Inventory balance 2. Loss of RCS subcooled margin QB leak/rupture. calculation due to RCS leakage (saturated 2. Performance of EPIP-09 (Off-site QB conditions). Dose Calculations) or measured C. Field observation dose rates from off-site sun/eys QB indicate site boundary (1 mile)

D. Emergency Coordinator exposure levels have been judgement exceeded as indicated by either QB A,B,C,orDbelow:

2. Indication of leaking RCS A. 1000 mrem/hr safety or relief valve which (total dose rate) causes RCS pressure to drop below: B. 1000 mrem (total dose - TEDE)

- Unit 1-1600 PSIA

- Unit 2-1736 PSIA 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. LOCAor Tuberuptureon 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

TABLE 3-1 EMERGENCY CLASSlFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1.B. ~BN ~RMA R PRI/ E L k R i r filr ft i r failure of stea Loss of 2 of the 3 fission roduct

~PRiMARYT n r t rt ITHIN nrtrt R AT arri withimmin nt I f th

~EQNDAfIY 1. Measured RCS to secondary char in m i with l THAN r in m ~thir (any two of the following exist

~LEAK RAT leakage exceeds Tech. Spec. e~iff.site w r with lo f ff- it w r and the third is imminent).

limits.

AND 1. Measured RCS to secondary 1. Measured RCS to secondary 1. Fuel element failure (confirmed

2. Secondary plant activity is leakage greater than Tech. leakage is greater than DEQ l-131 activity greater than detected. Spec. Umits and within charging pump capacity. 275 pCi/mL).

charging pump capacity. ~ND ~ND AND 2. Secondary plant activity is 2. LOCA or Tube rupture on

2. Secondary plant activity is detected. unisolable steam generator.

detected. AND AND

~ND 3. Loss of both Non-Vital 4.16 KV 3. Containment integrity breached.

3. Loss of both Non-Vital 4.16 KV buses.

buses.

NOTE Also refer to 'Potential Core R i filr ft m nrtr R i fiir f t m nrtr Me!t'vent/Class 6.A.

tube REATERTHAN h r in t REATER THAN r in

~um >~ca acittf} m i with t mr I

~in r err,~

1. Measured RCS to secondary leakage greater than charging 1. Measured RCS to secondary pump capacity. leakage greater than charging

~ND pump capacity.

2. Secondary plant activity is AND detected. 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.)

/RNRC EP3I4 3-6 St. Lucie, Rev. NRC DRAFT

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY 1.C. LOSS OF Ra id e re urizationof M r t ml kwith Maorst amleakwith releas has rr ri i SECONDARY ~ondan~lant REAT RTHAN1 m RE T R HAN rn r ress r ultin in COOLANT rim n I k ri n I ka nd fuel

1. Rapid drop in either steam ini td 1. Containment High Range generator pressure to less than 1. Rapid drop in either steam Radiation monitor greater than-600 psia. generator pressure to less than 1. Rapid drop in either steam 1.46 X 10'/hr (If CHRRM 600 psia. generator pressure to less than inoperable, Post-LOCA monitors AND 600 psia. greater than 1000 mR/hr).

2. Known pri/sec leak of greater ~ND QR than 10 gpm. 2. Known pri/sec leak of greater 2. Performance of EPIP%9

~ND than 50 gpm. (Off-site Dose Calculations) or

3. Secondary plant activity is ~ND measured dose rates from detected. 3. Secondary plant activity is off-site surveys indicate site detected. boundary (1 mile) exposure AND levels have been exceeded as Total loss of feedwater 4. Fuelelementdamageis indicated by either A, B, C, or D indicated (Refer to 'Fuel below:

1. No main or auxiliary feedwater Element Failure'vent/Class flow available for greater than 4.A). A. 1000 mrem/hr 15 minutes when required for (total dose rate) heat removaL AND TL F with -thr h lin B. 1000 mrem

2. Steam Generator levels are ~initi t d (total dose - TEDE) less than 40% wide range.

1. No main or auxiliary feedwater C. 5000 mrem/hr flow available. (thyroid dose rate)

AND

2. PORV(s) have been opened to D. 5000 mrem facilitate core heat removal. (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 actiVity greater 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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY i I i I Ar lea h rr ri i ri in rr rl i QFFQQNT r h is 10 times the r r r I in in r r r I in in

~EE~AI=, ~ffl i~nflr+I

1. Plant effluent monitor(s) exceed 1. Containment High Range 1. Containment High Range alarm setpoint(s). 1. Plant effluent monitor(s) Radiation Monitor greater than Radiation monitor greater than

~N significantly exceed alarm 7.3 X 10'/hr (Post-LOCA 1.46 X 10'/hr (If CHRRM

2. Confirmed analysis results for setpoints. monitors indicate between 100 inoperable, Post-LOCA monitors gaseous or liquid release which AND and 1000 mR/hr, if CHRRM greater than 1000 mR/hr).

exceeds ODCM limits. 2. Confirmed analysis results for inoperable). QQ gaseous or liquid release which QQ 2. Performance of EPIP-09 (Off-site

2. Measured Dose Rates or Dose Calculations) or measured

~O Off-site Dose Calculation dose rates from off-site surveys If analysis is not available within one hour, and it is (EPIP-09) worksheet values at indicate site boundary (1 mile)

NOTE one mile ln excess of: exposure levels have been expected that release is If analysis is not available exceeded as indicated by either greater than ODCM limit, viithin one hour, and it is dassify as +~~I. expected that release is equal A. 50 mrem/hr (total dose rate) A, B, C, or D belovr.

gVVN: '

or 250 mrem/hr (thyroid to or greater than 10 times dose rate) for 1/2 hour. A. 1000 mrem/hr ODCM limit, dassify as

~T'. QB (total dose rate)

B. 500 mrem/hr (total dose rate) or 2500 mrem/hr B. 1000 mrem (thyroid dose rate) for two (total dose - TEDE) minutes at one mile.

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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY i ii Ivl ri

~VII

~PNT I m n mi v r inwhi I nin h r f i iv ri I

1. Any valid area monitor alarm from indeterminable source with meter near or greater than full scale deflection (10'R/hr).

QQ

2. Unexpected plant iodine or particulate airborne concentration of 1000 DAC as 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 rii i 'hi h wr ~nfLnnrll,~flr ir mrmiin h n i I i

! I m i Refer to 'Potential Core

1. Potentially affecting safety rn r in r I 6.A. Melt'vent/Class systems.

~N

2. Requiring off-site support in the opinion of the NPS/EC.

XPLO ION rr n f n x I I n wi hln r/ m nn v r m f

'n h wnr nrll Ar wihin h Pr Ar imnfrm I x I Inwhih ff In h inrn r in I gfKEQiin

~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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY 4A. jgg~~E ul I n F I lmnfilr I m n f il r wit I riI I

~IQQg n t r Iin r Itin in

1. Processmonitorsorarea 1. Process monitors or area radiation surveys indicate radiation surveys indicate 1. RCS DEQ I-131 activity greater Containment High Range increased letdown activity increased letdown activity and than or equal to 275 pCi/mL. Radiation monitor greater than

~N confirmed RCS Samples ~ND 1.46 X 10'/hr (If CHRRM

2. Confirmed RCS sample indicating DEQ I-131 activity 2. Highest CET per core quadrant inoperable, Post-LOCA monitors indicating: greater than or equal to 275 indicates greater than 10'F greater than 1000 mR/hr).

pCI/mL superheat or 700'F. QR A. Coolant activity greater than 2. Performance of EPIP%9 (Off-site the Tech Spec limit for Dose Calculations) or measured

~NO iodine spike (Tech Spec dose rates from off-site surveys If analysis is not available Figure 3.4-1.). indicate site boundary (1 mile) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and it is

~O exposure levels have been B. Coolant activity greater than expected that RCS activity for exceeded as indicated by either 100/E pCi/gram specific DEQ 1-131 is greater than 275 A, B, C, or D below:

activity. pCi/mL, dassify as an A. 1000 mrem/hr (total dose rate)

~T If analysis is not available B. 1000 mrem within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and it is dassify as

~NT'.

~

expected that activity is greater than Tech Spec limit, C.

D.

(total dose - TEDE) 5000 mrem/hr (thyroid dose rate) 5000 mrem (thyroid dose - CDE)

F Ih n Iin i r m t irr i li esult inth r I f ContainmentorF elH n Iin di ivi I nt inm n rF I Handlin 8 il in

1. Affected area radiation monitor

1. NPS/EC determines that an levels greater than 1000 mR/hr.

irradiated fuel assembly may AND have been damaged. 2. Major damage to more than

~ND one irradiated fuel assembly.

2. Associated area or process QQ radiation monitors are in alarm. 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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY 5.A. QAA'~QAl<g nfirmed rth uake ha A nfirm rth k h nfirm rth k h NOTE occurred gcg~rr II Refer to 'Potential Core 6.A. Melt'vent/Class

1. A confirmed earthquake has 1. A confirmed earthquake occurs 1. A confirmed earthquake occurs been experienced within the which registers GREATER which registers GREATER Owner Controlled Area. THAN 0.05 g within the Owner THAN 0.1 g within the Owner QQ Controlled Area Controlled Area and the plant

2. An earthquake is detected by QR not in cold shutdown.

plant seismic monitor 2. A confirmed earthquake has QR instruments or other means. occurred that could cause or 2. A confirmed earthquake has has caused trip of the turbine occurred that has caused loss generator or reactor. of any safety system function (Le., both trains inoperable).

5.B. HIIRRI~AN n Wmin Hurricanew min withwind n r H rri n w min with viin NOTE

~ded s bess R AT RTHAN i n i Refer to 'Potential Core

1. Confirmed humcane warning is 6.A. Melt'vent/Class in effect. 1. Confirmed humcane warning 1. Plant not at cold shutdown.

is in effect and winds are AND expected to exceed 175 mph 2. Confirmed hurricane warning within the Owner Controlled is in effect and winds are Area. expected to exceed 194 mph within the Ovmer Controlled Area.

NOTE At FPL's request, NOAA will provide an accurate NOTE projection of wind speeds At FPL's request, NOAA will on-site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the provide an accurate onset ot hurricane force projection of viind speeds winds. If that projection is not on-site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the available within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ot onset of hurricane torce entering into the warning, winds. If that projection is not classify the event using available within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of current track and wind speeds entering into the warning, to project on-site conditions. dassify the event using For example, projected on- current track and wind speeds site wind speed would be less to project on-site conditions.

than maximum hurricane wind For example, projected on-speed if the track is away site wind speed would be less from PSL than maximum hurricane viind speed if the track is away trom PSL.

/RNRC EP3:4 3-11 St. Lucie, Rev. NRC DRAFT

~

~

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE

!'VENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 5.C. ~TNA ~ rikin h Pwr ril r EQIK Refer to 'Potential Core 6.A. Melt'vent/Class 5.0. ~N(~RMA n I vl ii r W~AT ~VFQ ffin I w r h n I v h n iw niin in ilr f

1. Low intake canal level of -10.5 granii ~n ft. MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more.

QQ 1. The storm drain's capacity is 1. Flood/surge water tevel

2. Visual sightings by station exceeded during hurricane reaching elevation+19.5 ft.

personnel that water levels are surge or known flood (turbine building/RAB ground approaching storm drain conditions. floor).

system capacity. QQ QQ

2. Low Intake canal level of -10.5 2. Low intake canal level has ft. MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more viith caused the loss of all ICW flow.

emergency barrier valves open.

/RNRC EP3I4 3-12 St. Lucie, Rev. NRC DRAFT

~ ~

'f I II tgq 1

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE 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 UNUSUAL EVENT mn whi h

w I

In n ln ni n ALERT Emer en d mnth xi whi v n niin ni SITE AREA EMERGENCY mr xi mn n

whi h

r i r' ni'n nifi n GENERAL EMERGENCY h

r n

n niin fi r i

rn un r'n xi h mk QQ~MI T W thlevlf f I

h r in ln n n n r I I

i i' h ri (Page of 2) i gLi~hri ii~

ffn I I m nn r ~~l~li ly (Any core melt 1 situation.)

1. The plant is shutdown under 1. LOCA with failure of ECCS abnormal conditions (e.g., leading to severe core exceeding cooldown rates or degradation or melt.

primary system pipe cracks are QQ found during operation). 2. LOCA with initially successful QQ ECCS and subsequent failure of

2. Any plant shutdovm required by containment heat removal Technical Specifications in systems for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

which the required shutdown Is QQ not reached within action limits. 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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

A~

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 6.A ~IN R~AEIED

~NOTE

1. Most likely containment

~PTENTtAL failure mode is melt-QQRE MELT through with release of gases only. Quicker (Page 2 of 2) 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.

t ti nBI k t t I sofA tation Bl k u otal Lo fA NOTE on-site A wer ca bili f r REAT RTHAN1 minut Refer to 'Potential Core

1. Loss of off-site AC power.

6.A. Melt'vent/Class

1. Loss of off-site AC power. AND 1. Loss of off-site AC power.

QR 2. Failure of both emergency AND

2. Loss of capability to power at diesel generators to start or 2. Sustained failure of both least one vital 4.16 kv bus from load.  ! emergency diesel generators to a~n available emergency diesel start or load.

generator. AND L f lion-siteD w r 3. Failure to restore AC power to at least one vital 4.16 kv bus

1. DropinAandBDCbus within 15 minutes.

voltages to less than 70 VDC.

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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY f In ntrlFn in Criti I f Pl n ntr

~ONTRO ~n~ti n

~FN~TII~N 1. Complete loss of any function Refer to 'Potential Core needed for plant cold 1. Loss of any function or system 6.A. Melt'vent/Class shutdown. which, in the opinion of the QQ Emergency Coordinator,

2. Failure of the Reactor predudes placing the plant in Protection System to bring the Hot Shutdown.

reactor subcritical when QQ needed. 2. FailureoftheRPStotiipthe QQ reactor when needed, and

3. Control Room is evacuated (for operator actions fail to bring the other than drill purposes) viith reactor subcritical.

control established locally at QB the Hot Shutdown Control 3. Control Room is evacuated Panel. (for other than drill purposes) and control cannot be established locally at the Hot f h t wn Iin Shutdown Control Panel within 15 minutes.

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'.

S.B. LOSS OF ALARMS/ i nifi n I f ffl n ~L~fl~rm

~MONIT RIN mmni tin i i i n 1. Unplanned loss of glI safety 1. Inability to emergency monitor I I t whi im ir system annunciators. a significant transient in

~N progress.

r n mn 2. Plant transient in progress.

1. Loss of effluent or radiological monitoring capability requiring Significant transient examples plant shutdown. include: Reactor trip, turbine QB runback greater than 25%

2. Lossofallpnmary~nbackup and thermal oscillations communication capability with greater than 10%.

off-site locations.

QQ

3. Unplannedlossofmost (greater than 75%) or all safety system annunciators for greater than 15 minutes.

/RNRC EP3:4 3-15 SL Lucie, Rev. NRC DRAFT

A TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY OA ~ICRAFT n I lrr 'i ir i il i D m vi I m fr

~~IL gllr;ryt~mI i~i

1. Aircraft crash in the Owner 1. Aircraft crash in the Power Controlled Area or unusual Block. 1. Aircraft crash in the Power aircraft activity over facility that QQ Block damaging vital plant in the opinion of the NPS/EC, 2. Visual or audible Indication of systems.

could threaten the safety of the missile impact on the Power QQ plant or personnel. Block. 2. Damage resulting in loss of safe shutdown equipment from any missile.

VI II < i h T in in nnfilr 'n n n r 9.C. ~TXI~ ni r I i f xi rflmm I in T xi r mm I ni II ff in I n i in vi I r wn r I h I mrmiin h n in f I ff I n n f I imn n r din r I T~HgfQ'TY KGllEXX Th I M Yh RITYEMER EN Y nv Ivin immin n fl kvrfh ln II h ri F r i n II h ri F n I I i h r r n n n r fh fin In h f h nrlr r r r I ri I

i I vi I h fh fin in h f r

1. Bomb threat

2. Attack threat S. Civil disturbance

4. Protected Area intrusion

5. Sabotage attempt

6. Internal disturbance

7. Vital area intrushn

8. Security force strike 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 DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co. 05000335 50-389 St.'ucie Plant, Unit 2, Florida Power S Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION STALL,J.A. Florida Power S Light Co.

RECIP.NAME RECXPIENT AFFILIATION Records Management Branch (Document Control Desk)

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 COPIES RECXPIENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD2-3 PD 1 1 GLEAVES,W 1 1 INTERNAL: AEOD/HAGAN,D 1 1 CENTER 01 2 2 NRR/DRPM/PERB 1 1 NUDOCS -AB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 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.

Attachment 2 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.

/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 No CAUTION statement CAUTION: THIS SECTION Clarify difference between Rate SHOULD NOT BE USED FOR classification criteria for STEAM GENERATOR TUBE primary/secondary leakage.

LEAK/RUPTURE.

UNUSUAL EVENT UNUSUAL EVENT Relief valve settings different for Units 1 and 2.

2. Indication of leaking RCS safety or relief 2. Indication of leaking RCS safety valve which causes RCS pressure to drop or relief valve which causes RCS below ~1600 ele. pressure to drop below:

Unit 1 -1600 sia Unit 2 -1736 sia ALERT ALERT Current section does not

1. Charging/letdown mismatch or recognize loss of charging

.1. Charging/letdown mismatch or measured RCS leakage indicates capacity and conflicts with Site measured RCS leakage indicates greater greater than 50 gpm but less than Area Emergency section.

than 50 gpm but less than 132 gpm. available char in ca aci

Event/Class E Plan, Rev. 34 Current E Plan, Rev. DRAFT Pro osed 1.A SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision does not Abnormal Primary Leak recognize loss of charging Rate (continued) 1. RCS leakage greater than 132 gpm 1. RCS leakage greater than 50 capability in some cases where occurring with RCS pressure above HPSI gpm and greater than available leakage is less than 132 gpm.

shutoff head. charging capacity.

Current revision does not ctadfy OR OR credit for normal makeup (charging) only or any makeup.

2. RCS leakage greater than available 2. Loss of RCS subcooled margin makeup occurring with RCS pressure due to RCS leakage (saturated Proposed revision provides for below HPSI shutoff head. conditions). clear classification criteria for LOCA greater than 50 gpm and OR greater than (normal) charging capacity, which is consistent with

3. Loss of RCS subcooled margin due to NUREG guidance and industry RCS leakage (saturated conditions). examples.

OR Criteria for radiation monitor readings are identified in

4. Containment High Range Radiation - Event/Class 2.A (Uncontrolled Monitors indicate 7.3 x 10'/hr (if CHRRM Effluent Release).

inoperable, Post-LOCA monitors indicate.

between 100 and 1000 mR/hr).

1.8 Abnormal Primary to SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision caused confusion Secondary Leak Rate to users, specifically concerning Ra id failure of steam enerator tube s Ra ldfailureofsteam eneratortube s "unisolable status of slight-GREATERTHAN char in um ca aci GREATER THAN char in um release potential from equipment with steam release in ro ress ca aci with steam release in ro ress (such as steam driven AFW).

3. Secondary steam release in progress Proposed revision provides

3. Secondary steam release in progress from affed ed generator ~e.. ADVs additional clarification to user on from affected generator (i.e., ADVs, Steam stuck steam safe s unlsolable types of secondary steam Safety(s), or Unisoiable.)

~leak releases to be considered when classifying event.

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 2.A Uncontrolled Effluent SITE AREA EMERGENCY SITE AREA EMERGENCY Confusion by users on dose rates Release . versus total dose.

2. Measured Dose Rates or Offsite Dose 2. Measured Dose Rates or Offsite Calculation (EPIP-09) worksheet values at Dose Calculation (EPIP-09) Proposed revision provides clear one mile in excess of: worksheet values at one mile in criteria based on dose rate.

excess of:

A. 50mrem/hr(totaldose TEDE) or250 mrem/hr (thyroid dose CDE) for I* A. 50 mrem/hr (total dose ~rate or hour. 250 mrem/hr (thyroid dose ~rate for

/~ hour.

OR OR B. 500 mrem/hr (total dose TEDE) or 2500 mrem/hr (thyroid dose CDE) for B. 500 mrem/hr (total dose ~rate or two minutes at one mile. 2500 mrem/hr (thyroid dose ~rate for two minutes at one mile.

3. Fire UNUSUAL EVENT UNUSUAL EVENT Use of "power block provides clear description of structures of Uncontrolled fire within the plant lasting Uncontrolled fire within the power equipment that should be more than 10 minutes. block lasting more than 10 minutes. considered in this classification.

Power block" is specifically defined in EPIP-01.

Explosion No NOTE in section. NOTE'XPLOSION IS DEFINED NOTE provides clear definition of AS A RAPID CHEMICAL explosion event.

REACTION RESULTING IN NOISE HEAT AND THE RAPID EXPANSION OF GAS.

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e

3. Explosion (continued) ALERT ALERT Proposed revision provides clear identification of the location Damage to facility by explosion which Damage to (Protected Area) where affects plant operation. structures/com onents within consideration for classification of the Protected Area by explosion explosions occur.

which affects plant operation.

SITE AREA EMERGENCY SITE AREA EMERGENCY Proposed revision provides clear criteria for the meaning of severe Severe damage to safe shutdown Severe damage to safe shutdown damage to safe shutdown equipment from explosion. equipment from explosion ~i.e. equipment, which applies both trains rendered ino erable . regulatory guidance definition for loss of equipment functions.

4.B Fuel Handling SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision does not provide Accident specific radiation dose rate Major damage to irradiated fuel in Major damage to irradiated fuel in threshold.

Containment or Fuel Handling Building Containment or Fuel Handling Building Current revisiori criteria requires

1. Step increase in the reading of knowledge of extent of damage radiation monitors in the plant vent Affected area radiation ("more than one irradiated fuel and/or in the Fuel Handling Building monitor levels reater than assembly" ) which will likely not be 1000 mr/hr. known.

AND AND Proposed revision provides

2. Damage to more than one irradiated specific radiation dose rate fuel assembly. ~2. Ma or Damage to one or more threshold (consistent with other irradiated fuel assemblies classification criteria) and does OR not limit classification based on unknown extent of damage.

OR

3. Uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.

3. Ma or dama e resultin from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool

Event/Class E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 5.A Earthquake UNUSUAL EVENT UNUSUAL EVENT Current classification does not 2 An earthquake is detected by provide for classification based on

2. An earthquake is detected by plant plant seismic monitor instruments information received by other seismic monitor instruments. or other means. (non-plant) seismic monitors, such as from other nuclear sites, colleges, or scientiTic monitoring equipment.

ALERT ALERT The current revision does not consistently identify the location A confirmed earthquake occurs which A confirmed earth uake has of the increased seismic activity registers GREATER THAN 0.05 g. occurred (within the Owner Controlled Area, as in UNUSUAL EVENT).

1. A confirmed earthquake occurs which registers GREATER The proposed revision relates the THAN 0.05 g within the Owner measurement of seismic activity Controlled Area. to the Owner Controlled Area and provides for direct indications for OR effects of the earthquake on plant conditions (turbine or reactor trip).

2. A confirmed earth uake has occurred that could cause or has caused a tri of the turbine enerator or reactor.

Class/Event E Plan Rev. 34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 5.A Earthquake SITE AREA EMERGENCY SITE AREA EMERGENCY The current revision does not (continued) consistently identify the location A confirmed earthquake occurs which A confirmed earth uake has of the increased seismic activity registers GREATER THAN 0.1 g. with plant occurred (within the Owner Controlled not in cold shutdown. Area, as in UNUSUAL EVENT).

1. A confirmed earth uake occurs which re isters The proposed revision relates the GREATER THAN 0.1 . within measurement of seismic activity the Owner Controlled Area to the Owner Controlled Area and and the lant is not in cold provides for direct indications for shutdown. effects of the earthquake on plant conditions (loss of safety related OR 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 The current revision did not ALERT, identify specific affected areas of Any tornado striking facility. the plant to be considered for a Any tomedo striking tahe ower tornado strike.

block.

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 E Plan Rev. 34 Current E Plan Rev. DRAFT Current Reason for Chan e 6.A Increased ALERT ALERT The current revision causes Awareness or Potential confusion to whether use of Core Melt Emergency Coordinator's judgement that Emergency Coordinator's emergency response facilities or plant conditions exist which warrant: judgement that plant conditions activation of any emergency exist which have a otential to response personnel in its self

1. Increased awareness and activation of de rade the level of safe at the justifies ALERT classification.

Emergency Response personnel. plant.

Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of an ALERT.

SITE AREA EMERGENCY The current revision causes SITE AREA EMERGENCY confusion to whether use of Emergency Coordinator's judgement that emergency response facilities in plant conditions exist which warrant: its se)f justifies SITE AREA

1. Emergency Coordinator's judgement that plant conditions EMERGENCY classification.

(Classification of SITE AREA

1. Activation of emergency response EMERGENCY always results in facilities and monitoring teams or a notification of the public.)

uncontrollable manner.

precautionary notification of the public near the site. Proposed revision makes judgement criteria clear that degradation of plant conditions justify classification of a SITE AREAEMERGENCY.

GENERAL EMERGENCY GENERALEMERGENCY Current revision does not contain specific time criteria in

2. LOCA with initially successful ECCS 2. LOCA with initially successful classification considerations.

and subsequent failure of containment ECCS and subsequent failure of hear removal systems for several containment heat removal Proposed revision provides hours. specific time span, after which a hours. GENERAL EMERGENCY classification is warranted.

Event/Class E Plan, Rev. 34 Current E Plan, Rev. DRAFT Pro osed Reason for Chan e 6.A Increased GENERAL EMERGENCY GENERALEMERGENCY The current revision causes Awareness or Potential confusion with user in regard to Core Melt (continued) 4. Failure of off-site and on-site power 4. Failure of off-site and on-site what is "emergency feedwater".

along with loss of emergency feedwater power along with loss of emergency The plant does not designate any makeup capability for several hours.

8 '""'

feedwater makeup capability for equipment as'emergency feedwater.

Current revision does not contain specific time criteria in classification considerations.

The proposed revision provides clear indication that if there is no feedwater for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then a GENERAL EMERGENCY cIassification is warranted.

7.A Loss of Power ALERT ALERT Current revision does not address ability of diesel generator to

2. Failure of both emergency diesel 2. Failure of both emergency diesel perform its intended function (load generators to start or synchronize. generators to start or load. onto emergency buses)

SITE AREA EMERGENCY SITE AREA EMERGENCY Proposed revision provides clear indication that if the diesel is not

2. Sustained failure of both emergency 2. Sustained failure of both loaded, then classification is diesel generators to start or synchronize. emergency diesel generators to start warranted.

or load.

Event/Class E Plan, Rev. 34 Current E Plan Rev. DRAFT Current Reason for Chan e 8.8 UNUSUAL EVENT UNUSUALEVENT Current revision does not provide for a quantitative value for loss of Loss of 3. Unplanned loss of most or all Safety 1. Unplanned lossofmostigreater "most annunciators.

Alarms/Communication/ System annunciators for greater than t~han 75% or atl Safety System Monitoring 15 minutes. annunciators for greater than 15 Proposed revision indicates a minutes. specific percentage of annunciators lost needed to classify an UNUSUAL EVENT.

SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision does not provide

1. Inability to monitor a significant transient 1. Inability to e~ffeottvet monitor a guidance on degree of ability in in progress. significant transient in progress. which a transient can be monitored in classifying the event.

NOTE: Si nificant transient exam les include: reactor tri Current revision does not provide turbine runback reater than 25% definition of significant transient.

and thermal oscillations reater than 10%. Proposed revision provides additional guidance for the user to determine that, if a transient can not be effectively monitored, then a SITE AREA EMERGENCY is warranted. Additionally, examples of significant transients are provided.

9.A Aircraft/Missile ALERT ALERT Current revision does not provide

1. Aircraft crash in the Owner Controlled reference to crash or missile Area damaging plant structures. block. impact to specific plant structures.

OR OR Proposed revision provides clear indication (i.e., the power block)

2. Visual or audible indication of missile 2. Visual or audible indication of where a crash or missile impact impact on plant structures. would warrant classificatio of ALERT.

Event/Class E Plan Rev.34 Current E Plan Rev. DRAFT Pro osed Reason for Chan e 9.A Aircraft/Missile SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision does not provide (continued) reference to crash or missile

1. Aircraft crash in the Owner Controlled 1. Aircraft crash ~to the ower impact on specific plant Area damaging vital plant systems. block damaging vital plant structures.

systems.

OR Proposed revision defines specific OR area of the plant where damage is

2. Damage to safe shutdown equipment considered classifiable.

from any missile. 2. Damage resultin in loss of safe shutdown equipment from Proposed revision identifies effect any missile. 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 SITE AREA EMERGENCY SITE AREA EMERGENCY Current revision caused confusion Gas with user differentiating between Toxic or flammable gas has diffused into Toxic or flammable gas has ALERT and SITE AREA vital areas affecting access to or the diffused into vital areas EMERGENCY. Current revision operation of safe shutdown equipment. compromising the function of safety does not consistently relate loss related equipment (i.e., both trains of safety system function with rendered inoperable) 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 CLASSIFICATION TABLE

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY 1A. /~Nfl

/~MA EGG

1. RCS leakage GREATER THAN 1. Charging/letdovm mismatch or 1. RCS leakage greater than 1. Containment High Range 10 gpm as indicated by: measured RCS leakage available than 50 gpm and Radiation monitor greater than QAAQIQIJi Indicates greater than 50 g pm greater than available charging 1.46 X 10'/hr (If CHRRM This section shouki but less than available charging A. Control Room observation capacity. inoperable, Post. LOCA mon! tors NOT be used for a QB capacity. QB greater than 1000 mR/hr).

steam generator tube B. Invenlory balance 2. Loss of RCS subcooled margin QB leak/rupture. calculation due to RCS leakage (saturated 2. Performance of EPIP<9 (Off-site QB conditions). Dose Calculations) or measured C. Field observation dose rates from off-site surveys QB Indicate site boundary (1 mile)

D. Emergency Coordinator exposure levels have been Judgement exceeded as indicated by either QB A, B, C, or 0 betovc

2. Indication of leaking RCS A. 1000 mrem/hr safety or relief valve which (total dose rate) causes RCS pressure to drop below: 8. 1000 mrem (total dose - TEDE)

- Unit 1-1600 PSIA

- Unit 2-1736 PSIA 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 TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITEAREAEMERGENCY GENERALEMERGENCY

'I.B. BBBRRRMMAALL PRI/ 'I< R i r filr ft R i r ilr ft f fth fi i r

~PRIMA Y T t rt I IN n trt RAT rri with immin n I t

~EQNDARY 1. Measured RCS to secondary ri m THAN i m ~hir (any two of the following exist

~AK RATI; "

leakage exceeds Tech. Spec. ~fff-~~it ILr f ff-it r and the third is imminent).

limits.

~ND 1. Measured RCS to secondary 1. Measured RCS to secondary 1. Fuel element failure (confirmed

2. Secondary phnt activity is leakage greater than Tech. leakage is greater than DEQ I-131 activity greater than detected. Spec. Umits and within charging pump capacity. 275 pCi/mL).

charging pump capacity. ~N ~N

~ND 2. Secondary plant activity is 2. LOCA or Tube rupture on

2. Secondary phnt activity is detected. unisohbie steam generator.

detected. AND IitND

~ND 3. Loss of both Non-Vital 4.16 KV 3. Containment integrity breached.

3. Loss of both Non-Vital 4.16 KV buses.

buses.

Also refer to 'Potential Core i filr ft m n tr R i ilr ft rn nrtr Melt'vent/Chss 6.A.

R RTHAN r i t s R A RTHAN rin g~m~ggi~) with I ri

1. Measured RCS to secondary leakage greater than charging 1. Measured RCS to secondary pump capacity. leakage greater than charging ~

~ND pump capacity.

2. Secondaiy plant activity is ~ND detected. 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.)

/RNRC EP3:4 St. Lucie Rev. NRC DRAFT

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1.C. ~LQ~F id re uii ti f rla ha rr ri in

~QQNDARY ggggn~gllnI RE THAN 1 m R T THAN r r r itin in QQQPNT ii I k ri k ndf el

1. Rapid drop in either steam fI~mgg Indi~tII 1. Containment High Range generator pressure to less than 1. Rapid drop in either steam Radiation monitor greater than .

600 psia. generator pressure to less than 1. Rapid drop in either steam 1.46 X 10 R/hr (If CHRRM 600 psia. generator pressure to less than inoperable, Post-LOCA monitors AND 600 psia. greater than 1000 mR/hr).

2. Known pri/sec leak of greater ~AN QQ than 10 gpm. 2. Known pri/sec leak of greater 2. Performance of EPIP~

~ND than 50 gpm. (Off-site Dose Calculations) or

3. Secondary phnt activity is AND measured dose rates from detected. 3. Secondary plant activity is off-site surveys indicate site detected. boundary (1 mile) exposure

~AN levels have been exceeded as

4. Fuel element damage is indicated by either A, 8, C, or D indicated (Refer to 'Fuel belovr.

1. No main or auxiliary feedwater Element Failure Event/Chss flow avaihble for greater than 4.A). A. 1000 mrem/hr 15 minutes when required for (total dose rate) heat removal.

~ND F wit -thr h li B. 1000 mrem

2. Steam Generator levels are initi t (total dose - TEDE) less than 40/o wide range.

1. No main or auxiliary feedwater C. 5000 mrem/hr flow avaihble. (thyroid dose rate)

~N

2. PORV(s) have been opened to D. 5000 mrem facilitate core heat removal. (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. LOCA or 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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITEAREAEMERGENCY GENERALEMERGENCY 2.A i I I limi rr I r Ii

1. Plant effluent monitor(s) exceed 1. Containment High Range 1. ContaInment High Range alarm selpoint(s). 1. Plant effluent monitor(s) Radiation Monitor greater than Radiation monitor greater than

~N significantly exceed alarm 7.3 X 10 R/hr (Post-LOCA 1.46 X 10'/hr (If CHRRM

2. Confirmed analysis results for setpoints. monitors indicate between 100 inoperable, Post-LOCA monitors gaseous or liquid release which BED and 1000 mR/hr, if CHRRM greater than 1000 mR/hr).

exceeds ODCM limits. 2. Confirmed analysis results for Inoperable). QB gaseous or liquid release which QB 2. Performance of EPIP-09 (Off-site

2. Measured Dose Rates or Dose Calculations) or measured HQXK Off-site Dose Calculation dose rates from off-site surveys If analysis is not available (EPIP49) worksheet values at indicate site boundary (1 mile) within one hour, and it is HQK one mile In excess of: exposure levels have been dassify as

~V~

~

expected that release is greater than ODCM limit, If analysis Is not available within one hour, and it is expected that release Is equal to or greater than ~i ODCM limit, dassify as A. 50 mrem/hr (total dose rate) or 250 mrem/hr (thyroid dose rate) for 1/2 hour.

exceeded as indicated by either A, B, C,or 0belovr.

A. 1000 mrem/hr QB (total dose rate)

AiKBZ- B. 500 mrem/hr (total dose rate) or 2500 mrem/hr B. 1000 mrem (thyroid dose rate) for two (total dose - TEDE) minutes at one mile.

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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

. 2.8 i i h I

1. Any valid area monitor alarm from Indeterminable source with meter near or greater than full scale 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 hi w r gggg0~II ~ffL i n h I I i I Refer to 'Potenflal Core

1. Potentially affecting safety 6.A. Melt'venVCtass systems.

hE2

2. Requiring off-site support In the opinion of the NPS/EC.

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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4> EUElZKhKEE I il I il Evil.llBK

1. Process monitors or area 1. Process monitors or area radiation surveys indicate radiation surveys indicate 1. RCS OEQ 1-131 activity greater 1. Containment High Range increased letdown activity increased letdown activity and than or equal to 275 pCi/mL. Radiation monitor greater than

~N confirmed RCS Samp! es 1.46 X 10~ R/hr (If CHRRM

2. Confirmed RCS sample indicating DEQ I-131 activity 2. Highest CET per core quadrant inoperable, Post-LOCA monitors indicating: greater than or equal to 275 indicates greater than 10'F greater than 1000 mR/hr).

yCI/mL superheat or 700'F. QB A. Coolant activity greater than 2. Performance of EPIP49 (Off-site the Tech Spec limit for Dose Calculations) or measured iodine spike (Tech Spec dose rates from off-site surveys If analysis is not available Figure 3.4-1.). indicate site boundary (1 mile) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and it is QQ exposure levels have been B. Coolant activity greater than expected that RCS activity for exceeded as indicated by either 100/E pCi/gram specific DEQ I-131 is greater than 275 A, 8, C, or D belch.

activity. pCi/mL, dassify as an KBZ- A. 1000 mrem/hr (total dose rate)

If analysis Is not available B. 1000 mrem within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and it is (total dose - TED E) expected that activity is dassify as ~

greater than Tech Spec limit, C. 5000 mrem/hr (thyroid dose rate)

D. 5000 mrem (thyroid dose - COE) 4,B. @+~AN lin hGQDKKE

/grig P~nLfili3ijiilin,.

1. Affected area radiation monitor

1. NPS/EC determines that an levels greater than 1000 mR/hr.

irradiated fuel assembly may hHQ have been damaged. 2. Major damage to more than

~N one irradiated fuel assembly.

2. Associated area or process QB radiation monitors are in alarm. 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

TABLE 3-1 EMERGENCY CLASSIFjCATjON TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY 5.A. ~A~AK nfi h k firm it k

~N Refer to 'Potential Core 6.A. Melt'vent/Class

1. A confirmed earthquake has 1. A confirmed earthquake occurs 1. A confirmed earthquake occurs been experienced within the which registers GREATER which registers GREATER Owner Controlled Area. THAN 0.05 g within the Owner THAN 0.1 g within the Owner QQ Controlled Area Controlled Area and the plant

2. An earthquake is detected by QQ not in cold shutdown.

plant seismic monitor 2. A confirmed earthquake has QQ instruments or other means. occurred that could cause or 2. A confirmed earthquake has

! has caused trip of the turbine occurred that has caused loss generator or reactor. of any safety system function (i.e., both trains inoperable).

5.B. ARRI~AN n Wmin Hu i with win r it~in ~i R T AN in i Refer to Potential Core

1. Confirmed hurricane warning is 6.A. Melt'vent/Class in effect. 1. Confirmed hurricane warning 1. Plant not at cold shutdown.

is in effect and winds are ~N expected to exceed 175 mph 2. Confirmed hurricane warning within the Owner Controlled is in effect and winds are Area. expected to exceed 194 mph within the Owner Controlled Area.

~NT At FPL's request, NOAA viill provide an accurate projection of wind speeds At FPL's request, NOAA will on-site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pifor to the provide an accurate onset of humcane force projection of wind speeds winds. It that projection is not on-site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the .,

available within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of onset of hurricane force entering into the warning, winds. If that projection is not cfassity the event using avaiiabfe within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of current track and wind speeds entering Into the warning, to project on-site conditions. classify the event using For example, projected on- current track and wind speeds site wind speed would be less to project on-site conditions.

than maximum humcane wind For example, projected on-speed if the track is away site wind speed would be less from PSL than maximum hurricane wind speed it the track Is away trom PSL

/RNRC EP3:4 3-11 St. Lucie, Rev. NRC DRAFT

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUALEVENT ALERT SITEAREAEMERGENCY GENERAL EMERGENCY S.C. ~~MA Q ifi n f m i HQIE Refer to 'Potential Core 6.A. Melt'vent/Class

/~~A 5.0.

~WAT ~~ n I I ii r Iww r lw v I ni'.

Low intake canal level of -10$

ft. MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more.

QB 1. The storm drain's capacity is 1. Flood/surge water tevel

2. Visual slghtings by station exceeded during hurricane reaching elevation+19.5 ft.

personnel that water levels are surge or known flood (turbine building/RAB ground approaching storm drain conditions. floor).

system capacity. QB QB

2. Low intake canal level of -10.5 2. Low Intake canal level has ft. MLWfor1 hourormorewith caused the loss of all ICW flow.

emergency barrier valves open.

/RNRC EP3:4 3-12 St. Lucie, Rev. NRC DRAFT

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE HQIK Activation of the Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification.

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 6.A. ~NQfAA'jgQ n I h n i it xi Qgj'~NTIA I w ninr

~)ffMQIT h fh ri ffn I gg~ifLgLLIIIIIhf,(Any core melt (Page 1 of 2) gtt~hri i~ situation.)

1. The plant is shutdovm under 1 LOCA vnth failure of ECCS abnormal conditions (e.g., leading to severe core exceeding cooldown rates or degradation or melt.

primary system pipe cracks are QB found durfng operation). 2. LOCA with initially successful QB ECCS and subsequent failure of

2. Any plant shutdovm required by containment heat removal Technical Specifications in systems for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

which the required shutdown is QB not reached within action limits. 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 6A ~IN RF~AED ~TE

1. Most likely containment QQTTM~TIA failure mode is melt-QQRR MELT through with release of gases only. Quicker (Page 2 of 2) 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 tati nBI t t I f tti BI k tl f

~NTE n-it A r r R AT THA in Refer to 'Potential Core

1. Loss of off-site AC power.

6.A. Melt'vent/Class

1. Loss of off-site AC power. ~ND 1. Loss of off.site AC power.

QR 2. Failure of both emergency ~AN

2. Loss of capability to power at diesel generators to start or 2. Sustained failure of both least one vital 4.16 kv bus from load.  ! emergency diesel generators to

~n available emergency diesel start or load.

generator. ~N f II - it 3. Failure to restore AC power to at least one vital 4.16 kv bus

1. DropinAand BDCbus within 15 minutes.

voltages to less than 70 VDC.

II 'I I ~ it r r i t

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

TABLE 3-1 EMERGENCY CLASSIFICATION TABLE EVENT/CLASS UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 8> LQGRQEZLBK I 'n QQHXEQI. HQXK

~NQ~N 1. Complete loss of any function Refer to Potential Core needed for plant cold 1. Loss of any function or system 6.A. Melt'vent/Class shutdovm. which, in the opinion of the QB Emergency Coordinator,

2. Failure of the Reactor predudes pladng the plant in Protection System to bring the Hot Shutdown.

reactor subcnVcal when QB needed. 2. Failureofthe RPStotripthe QB reactor when needed, and

3. Control Room is evacuated (for operator actions fail to bring the other than drill purposes) with reactor subcri Veal.

control established locally at QB the Hot Shutdovm Control 3, Control Room is evacuated Panel. (for other than drill purposes) and control cannot be established locally at the Hot in Shutdown Control Panel within 15 minutes.

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'.

S.B. inifi nl f ffl n M~Mium M I Q~N~IQ 1. Unplanned loss of gffi safety 1. Inability to emergency monitor I n I I whi i system annunciators. a significant transient in iii if progress.

m r n 2. Plant transient in progress.

1. Loss of effluent or radiological EQIF monitoring capability requiring Significant transient examples plant shutdown. indude: Reactor trip, turbine QB runback greater than 25%

2. Loss of all primary ggII backup and thermal osdffatlons communication capability with greater flail 10%.

off-site locations.

QB

3. Unpiannedlossofmost (greater than 75%) or all safety system annunciators for greater than 15 minutes.

/RNRC EP3:4 3-15 St. Lvcie, Rev. NRC DRAFT

s TABLE 3-1 EMERGENCY CLASSlFlCATlON TABLE EVENT/CLASS UNUSUAL EVENT ALERT SITEAREAEMERGENCV GENERAL EMERGENCV 9>. ~IR RAFF) Ir I I

~MI I

1. Aircraft crash ln the Owner 1. Aircraft crash fn the Power Controlled Area or unusual Block. 1. Aircraft crash in the Power aircraft activity over facility that QB Block damaging vital plant in the opinion of the NPS/EC, 2. Visual or audible Indication of systems.

could threaten the safety of the mlssge impact on the Power QB plant or personnel. Block. 2. Damageresultinginlossof safe shutdown equipment from any missile.

I i i 9B. IN I I i 9.C. ~T)~l nn n r II i I ff i II r h n I f I I in 1o. GKLlEZf.

THffg~T II h in i fin I nin n

1. Bomb threat

2. Attack threat

3. Civil distutbance

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