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#REDIRECT [[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]]
| 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 & 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: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 hours, 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                ri''I  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 hour, 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 hour, 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 hours prior to the          provide an accurate onset ot hurricane force              projection of viind speeds winds. If that projection is not      on-site 24 hours prior to the available within 12 hours ot          onset of hurricane torce entering into the warning,            winds. If that projection is not classify the event using              available within 12 hours 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 hour 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 hour 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 hours.
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 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
 
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:
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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 hours, 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 hour, 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 hour, 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 hours pifor to the          provide an accurate onset of humcane force                projection of wind speeds winds. It that projection is not      on-site 24 hours prior to the    .,
available within 12 hours of          onset of hurricane force entering into the warning,            winds. If that projection is not cfassity the event using              avaiiabfe within 12 hours 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 hour 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 hours.
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 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
 
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}}

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