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| {{#Wiki_filter:3etp~t't'LORIDA POWER&LIGHTCOMPANYST.LUCIEUNITi'llE-PLANIMPLEMENTING PROCEDURE 3100025EREVISION61.0Title:FIREEMERGENCIES 2.0~Atoval:ReviewedbyFacilityReviewGroupApprovedbyK.N.HarrisPlantManagerJuly25,1975Jul29,1975Revision6ReviewedbyFRGApprovedby3.0~3coe:PlantManager/is,19K/Z,19~3.1PurposeThisprocedure providesinstructions tocontrolandextinguish fires,minimizedamageandpreventpersonalinjuries. | | {{#Wiki_filter:3 e tp~t't'LORIDA POWER&LIGHT COMPANY ST.LUCIE UNIT i'll E-PLAN IMPLEMENTING PROCEDURE 3100025E REVISION 6 1.0 Title: FIRE EMERGENCIES 2.0~Atoval: Reviewed by Facility Review Group Approved by K.N.Harris Plant Manager July 25,1975 Jul 29,1975 Revision 6 Reviewed by F R G Approved by 3.0~3co e: Plant Manager/is , 19K/Z, 19~3.1 Purpose This procedure provides instructions to control and extinguish fires, minimize damage and prevent personal injuries.3.2 Discussion 3.2.1 Any uncontrolled fire is considered a Fire Emergency. |
| 3.2Discussion 3.2.1Anyuncontrolled fireisconsidered aFireEmergency. | | In order to control and extinguish a fire, a fire fighting organization has been established. |
| Inordertocontrolandextinguish afire,afirefightingorganization hasbeenestablished.
| | 3.2.2 The Fire Team is composed of members of the Operating group assigned to the St.Lucie Plant.The members of the Fire Teams are qualified in fire fighting.3.2.3 For a list of the locations of fire fighting equipment, refer to the Mechanical Maintenance preventive maintenance program as delineated in Admin.Procedure No., 0010431"Preventive Maintenance Program".3.2.4 The emergency classification system includes certain fire related events.Thus, fires may be classified as Unusual Events, Alerts, or Site Area Emergencies. |
| 3.2.2TheFireTeamiscomposedofmembersoftheOperating groupassignedtotheSt.LuciePlant.ThemembersoftheFireTeamsarequalified infirefighting. | | 3.3~Auttotlt This procedure implements the St.Lucie Plant Emergency Plan and Fire Protection Plan.4.0 Precautions: |
| 3.2.3Foralistofthelocations offirefightingequipment, refertotheMechanical Maintenance preventive maintenance programasdelineated inAdmin.Procedure No.,0010431"Preventive Maintenance Program". | | 4.1 Class"C" fire extinguishers (C02 or Dry Chemical)or fog type fire hose nozzles shall be used on combustible liquid fires, electrical fires or on fires which might involve energized conductors and/or equipment. |
| 3.2.4Theemergency classification systemincludescertainfirerelatedevents.Thus,firesmaybeclassified asUnusualEvents,Alerts,orSiteAreaEmergencies. | | 8l09020026 810827,'DR ADOCK 05000335'P.DR, 1 1 0 t Page 2 of 4 E-PLAN IMPLEMENTING PROCEDURE 3100025E FIRE EMERGENCIES REVISION 6 4.0 Precautions (continued) 4.2 Foam type fire extinguishing materials shall not be used on electrical fires.4.3 When fighting fires in the Radiation Controlled Area that may involve radioactive materials, the members of the Fire Team shall use additional protective equipment specified by the Radiation Team Leader and shall follow any instructions he issues regarding precautions to observe while fighting the fire.5.0 Responsibilities: |
| 3.3~Auttotlt Thisprocedure implements theSt.LuciePlantEmergency PlanandFireProtection Plan.4.0Precautions: | | 5.1 The Nuclear Watch Engineer is the Fire Team Leader.If he is not available, the Nuclear Turbine Operator acts as his alternate.. |
| 4.1Class"C"fireextinguishers (C02orDryChemical) orfogtypefirehosenozzlesshallbeusedoncombustible liquidfires,electrical firesoronfireswhichmightinvolveenergized conductors and/orequipment. | | It shall be the responsibility of the Fire Team Leader to: 5.1.1 Direct all phases of the fire fighting activities. |
| 8l09020026 810827,'DRADOCK05000335'P.DR, 110 tPage2of4E-PLANIMPLEMENTING PROCEDURE 3100025EFIREEMERGENCIES REVISION64.0Precautions (continued) 4.2Foamtypefireextinguishing materials shallnotbeusedonelectrical fires.4.3WhenfightingfiresintheRadiation Controlled Areathatmayinvolveradioactive materials, themembersoftheFireTeamshalluseadditional protective equipment specified bytheRadiation TeamLeaderandshallfollowanyinstructions heissuesregarding precautions toobservewhilefightingthefire.5.0Responsibilities: | | |
| 5.1TheNuclearWatchEngineeristheFireTeamLeader.Ifheisnotavailable, theNuclearTurbineOperatoractsashisalternate.. | | ====5.1.2 Coordinate==== |
| Itshallbetheresponsibility oftheFireTeamLeaderto:5.1.1Directallphasesofthefirefightingactivities.
| | the activities of any outside fire fighting organization called in to assist with the emergency. |
| 5.1.2Coordinate theactivities ofanyoutsidefirefightingorganization calledintoassistwiththeemergency. | | 5.2 It shall be the responsibility of each Fire Team member to be thoroughly familiar with the contents of this procedure and the location of fire fighting equipment in the plant.5.3 All personnel shall be familiar with the location of, and be familiar with operation of fire equipment in their designated work stations.5.4 On the basis of observations, the Nuclear, Plant Supervisor is responsible for classification of the emergency. |
| 5.2Itshallbetheresponsibility ofeachFireTeammembertobethoroughly familiarwiththecontentsofthisprocedure andthelocationoffirefightingequipment intheplant.5.3Allpersonnel shallbefamiliarwiththelocationof,andbefamiliarwithoperation offireequipment intheirdesignated workstations. | | He is also responsible for making notifications and taking other actions appropriate to the emergency class.6.0 |
| 5.4Onthebasisofobservations, theNuclear,PlantSupervisor isresponsible forclassification oftheemergency. | |
| Heisalsoresponsible formakingnotifications andtakingotheractionsappropriate totheemergency class.6.0
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| ==References:== | | ==References:== |
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| 6.1St.LuciePlantEmergency Plan.6.2E-PlanImplementing Procedure EP3100023E | | 6.1 St.Lucie Plant Emergency Plan.6.2 E-Plan Implementing Procedure EP3100023E |
| ,On-SiteEmergency Organization/and Roster.6.3St.LuciePlantAdministrative Procedure No.1800022FireProtection Plan".6.4St.LuciePlantAdministrative Procedure No.0010431"Preventive Maintenance Program". | | , On-Site Emergency Organization/and Roster.6.3 St.Lucie Plant Administrative Procedure No.1800022 Fire Protection Plan".6.4 St.Lucie Plant Administrative Procedure No.0010431"Preventive Maintenance Program".7.0 Records: Any actions taken shall be recorded in the Nuclear Plant Supervisor's Log Book. |
| 7.0Records:AnyactionstakenshallberecordedintheNuclearPlantSupervisor's LogBook. | |
| l~ | | l~ |
| 0E-PLANIMPLEMENTING PROCEDURE 3100025EFIREEMERGENCIES REVISION6Page3of48.0Instructions:
| | 0 E-PLAN IMPLEMENTING PROCEDURE 3100025E FIRE EMERGENCIES REVISION 6 Page 3 of 4 8.0 Instructions: |
| 8.1Whenanindividual discovers afirewhichcanbesafelyextinguished usingfirefightingequipment athand,heshalldosoandthenpromptlynotifytheNuclearPlantSupervisor. | | 8.1 When an individual discovers a fire which can be safely extinguished using fire fighting equipment at hand, he shall do so and then promptly notify the Nuclear Plant Supervisor. |
| 8.2Whenanindividual discovers afireor.explosion resulting inafirewhichcannotbeextinguished usingfirefightingequipment athand,heshallnotifytheNuclearPlantSupervisor overthePAsystemorthecontrolroombydialing333onanyPAXtelephone. | | 8.2 When an individual discovers a fire or.explosion resulting in a fire which cannot be extinguished using fire fighting equipment at hand,he shall notify the Nuclear Plant Supervisor over the PA system or the control room by dialing 333 on any PAX telephone. |
| Thefollowing information shallbegiven:8.2.1Locationofthefire.8.2.2Typeoffire,ifknown.8.2.3Whetherornotthereareanyinjuredpersonnel.
| | The following information shall be given: 8.2.1 Location of the fire.8.2.2 Type of fire, if known.8.2.3 Whether or not there are any injured personnel. |
| 8.2.4Extentofdamagetoplantcomponents. | | 8.2.4 Extent of damage to plant components. |
| NOTE:Speedinnotification ismuchmoreimportant thanthecompleteness oftheinitialreport.8.3TheNuclearPlantSupervisor shallinstructtheindividual totakeanyimmediate actionheisqualified toperformtoextinguish thefire.8.4TheNuclearPlantSupervisor shallcross-connect thePAsystem,declareaFireEmergency, announcethelocationofthefire,andsoundthefirealarm..Ifsufficient information isavailable, heshallclassifythe-emergency andimplement theEmergency Plan.(1)TheNuclearWatchEngineerwilldirect,byuseofthepage.system,whichmemberswillmeethimatthefiresite,andwhichmemberswillgotothefirehouse.(2)IfthefireisfoundtobeintheRadiation Controlled Area,theRadiation Teamshallbeactivated bytheEmergency Coordinator (NuclearPlantSupervisor). | | NOTE: Speed in notification is much more important than the completeness of the initial report.8.3 The Nuclear Plant Supervisor shall instruct the individual to take any immediate action he is qualified to perform to extinguish the fire.8.4 The Nuclear Plant Supervisor shall cross-connect the PA system, declare a Fire Emergency, announce the location of the fire, and sound the fire alarm..If sufficient information is available, he shall classify the-emergency and implement the Emergency Plan.(1)The Nuclear Watch Engineer will direct, by use of the page.system, which members will meet him at the fire site, and which members will go to the fire house.(2)If the fire is found to be in the Radiation Controlled Area, the Radiation Team shall be activated by the Emergency Coordinator (Nuclear Plant Supervisor). |
| (3)Ifthefireorexplosion isintheRadiation Controlled Area,theyshallwearappropriate protective clothingandrespiratory equipment andpersonnel monitoring devices,attempttostayupwindofthefire,andcoordinate theiractionswiththeRadiation Team.(4)Other'lant personnel excepttheoperators onwatchshallreporttothemaintenance shopandbereadytoassistinthe.fireorexplosion fightingoperations whencalledupon. | | (3)If the fire or explosion is in the Radiation Controlled Area, they shall wear appropriate protective clothing and respiratory equipment and personnel monitoring devices, attempt to stay upwind of the fire, and coordinate their actions with the Radiation Team.(4)Other'lant personnel except the operators on watch shall report to the maintenance shop and be ready to assist in the.fire or explosion fighting operations when called upon. |
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| | 0 E-PLAN IMPLEMENTING PROCEDURE 3100025E FIRE EMERGENCIES REVISION 6 Page 4 of 4 8.4 (continued) |
| | (5)During normal working hours additional personnel are available from the maintenance department to support fire fighting efforts until outside assistance is obtained.(6)The Emergency Coordinator (Nuclear Plant Supervisor) shall designate additional available on-site personnel to assist in extinguishing the fire, as required by the situation. |
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| 0E-PLANIMPLEMENTING PROCEDURE 3100025EFIREEMERGENCIES REVISION6Page4of48.4(continued)
| | ====8.4.1 Requesting==== |
| (5)Duringnormalworkinghoursadditional personnel areavailable fromthemaintenance department tosupportfirefightingeffortsuntiloutsideassistance isobtained.
| | Outside Fire Assistance: |
| (6)TheEmergency Coordinator (NuclearPlantSupervisor) shalldesignate additional available on-sitepersonnel toassistinextinguishing thefire,asrequiredbythesituation.
| | (1)If the fire is too large to be controlled by available plant forces, the St.Lucie County-Ft. |
| 8.4.1Requesting OutsideFireAssistance:
| | Pierce Fire District shall be called by the Emergency Coordinator. |
| (1)Ifthefireistoolargetobecontrolled byavailable plantforces,theSt.LucieCounty-Ft. | | (2)The main guard station shall be notified of the location of-the fire and the expected arrival of the off-site fire fighting equipment. |
| PierceFireDistrictshallbecalledbytheEmergency Coordinator.
| | (3)Working commuinications shall be established between the Emergency Coordinator, the person in charge of the off-site fire fighting organization, the Radiation Team Leader, if the fire is in the Radiation Controlled Area, and the Fire Team Leader.St.Lucie County-Ft. |
| (2)Themainguardstationshallbenotifiedofthelocationof-thefireandtheexpectedarrivaloftheoff-sitefirefightingequipment. | | Pierce OR St.Lucie County Emergency Center 461-1547 464-1122 911 (4)In the case of an uncontrolled fire, not involving a safety system, but requiring off-site support, the Nuclear Plant Supervisor shall declare an UNUSUAL EVENT.(5)In the case of an uncontrolled fire, potentially affecting safety systems and requiring off-site support, the Nuclear Plant.Supervisor shall declare an ALERT.(6)In the case of a fire resulting in degradation of safety systems, the Nuclear Plant Supervisor shall declare a SITE AREA EMERGENCY. |
| (3)Workingcommuinications shallbeestablished betweentheEmergency Coordinator, thepersoninchargeoftheoff-sitefirefightingorganization, theRadiation TeamLeader,ifthefireisintheRadiation Controlled Area,andtheFireTeamLeader.St.LucieCounty-Ft. | | NOTE: See E-Plan Implementing Procedure 3100023E, Emergency Roster, for specific information regarding means of communication and telephone numbers. |
| PierceORSt.LucieCountyEmergency Center461-1547464-1122911(4)Inthecaseofanuncontrolled fire,notinvolving asafetysystem,butrequiring off-sitesupport,theNuclearPlantSupervisor shalldeclareanUNUSUALEVENT.(5)Inthecaseofanuncontrolled fire,potentially affecting safetysystemsandrequiring off-sitesupport,theNuclearPlant.Supervisor shalldeclareanALERT.(6)Inthecaseofafireresulting indegradation ofsafetysystems,theNuclearPlantSupervisor shalldeclareaSITEAREAEMERGENCY.
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| NOTE:SeeE-PlanImplementing Procedure | |
| : 3100023E, Emergency Roster,forspecificinformation regarding meansofcommunication andtelephone numbers.
| |
| ~I~~4~c~a}} | | ~I~~4~c~a}} |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999
Rev 35 to HP-90, Emergency Equipment.
ML17309A9941999-06-17017 June 1999
Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples.
ML17241A3541999-06-0101 June 1999
Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17309A9951999-05-27027 May 1999
Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples.
ML17241A3451999-05-24024 May 1999
Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks
ML17229B0711999-03-19019 March 1999
Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit
ML17229B0441999-03-0202 March 1999
Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr
ML17229B0201999-02-23023 February 1999
Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution
ML17229B0361998-12-22022 December 1998
Rev 20 to Procedure C-200, Odcm.
ML17229A9551998-12-16016 December 1998
Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9161998-11-25025 November 1998
Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases
ML17229A9251998-11-22022 November 1998
Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9131998-11-19019 November 1998
Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML20155C3061998-10-29029 October 1998
Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses
ML20153G0781998-08-26026 August 1998
Rev 19 to Plstqp, Guard Training & Qualification Plan
ML17229A8441998-08-24024 August 1998
Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal
ML17229A7731998-06-15015 June 1998
Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b
ML17229A7601998-06-0303 June 1998
Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank
ML17229A7441998-05-27027 May 1998
Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A7481998-05-27027 May 1998
Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7511998-05-27027 May 1998
Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A6751998-03-27027 March 1998
Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr
ML17229A6501998-03-0303 March 1998
Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls
ML17229A6381998-02-12012 February 1998
Rev 19 to C-200, Offsite Dose Calculation Manual.
ML17229A6151998-01-12012 January 1998
Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan.
ML17229A6141998-01-12012 January 1998
Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1.
ML17229A5691997-12-31031 December 1997
Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9131997-12-29029 December 1997
Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5851997-12-12012 December 1997
Rev 0 to ADM-29.01, IST Program for Pumps & Valves.
ML17229A5491997-12-0101 December 1997
Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion
ML17309A9171997-11-26026 November 1997
Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis.
ML17229A5931997-09-26026 September 1997
Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures.
ML17229A5921997-09-18018 September 1997
Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening.
ML20211Q5841997-09-10010 September 1997
Rev 18 to Training & Qualification Plan
ML17229A4621997-08-22022 August 1997
Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8
ML17229A4341997-08-0101 August 1997
Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE
ML17309A8951997-06-11011 June 1997
Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project.
ML17229A3601997-05-29029 May 1997
Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases
ML17229A2981997-03-0606 March 1997
Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A.
ML17229A1831996-12-20020 December 1996
Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings
ML17229A1611996-12-0909 December 1996
Proposed Tech Specs 1.9a Re Core Operating Limits Rept
ML17229A1191996-10-31031 October 1996
Proposed Tech Specs 6.0 Re Administrative Controls
ML17229A1111996-10-30030 October 1996
Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel
ML17229A1061996-10-28028 October 1996
Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel
ML17229A1091996-10-28028 October 1996
Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A0951996-10-24024 October 1996
Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage.
ML17229A0861996-10-18018 October 1996
Startup Physics Testing Rept. W/961018 Ltr
ML17229A2441996-09-23023 September 1996
Rev 18 to Offsite Dose Calculation Manual (Odcm).
ML17228B5641996-07-15015 July 1996
Revised Tech Specs Re Core Alteration Definition
ML17229A0961996-06-12012 June 1996
Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination.
1999-06-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17309A9961999-06-30030 June 1999
Rev 35 to HP-90, Emergency Equipment.
ML17309A9941999-06-17017 June 1999
Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples.
ML17309A9951999-05-27027 May 1999
Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples.
ML17229B0361998-12-22022 December 1998
Rev 20 to Procedure C-200, Odcm.
ML20153G0781998-08-26026 August 1998
Rev 19 to Plstqp, Guard Training & Qualification Plan
ML17229A6381998-02-12012 February 1998
Rev 19 to C-200, Offsite Dose Calculation Manual.
ML17229A6151998-01-12012 January 1998
Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan.
ML17229A6141998-01-12012 January 1998
Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1.
ML17229A5851997-12-12012 December 1997
Rev 0 to ADM-29.01, IST Program for Pumps & Valves.
ML17229A5931997-09-26026 September 1997
Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures.
ML17229A5921997-09-18018 September 1997
Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening.
ML20211Q5841997-09-10010 September 1997
Rev 18 to Training & Qualification Plan
ML17309A8951997-06-11011 June 1997
Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project.
ML17229A2981997-03-0606 March 1997
Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A.
ML17229A2441996-09-23023 September 1996
Rev 18 to Offsite Dose Calculation Manual (Odcm).
ML17229A0971996-06-10010 June 1996
Rev 0 to TP-9419-CSE96-2104, Steam Generator Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination.
ML20137P3651996-05-20020 May 1996
Rev 5 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms)
ML17228B4921996-04-22022 April 1996
FPL St Lucie Unit 1 SG Program.
ML20137P3381996-03-0404 March 1996
Rev 0 to Procedure 1-1400207, Calibr of Containment Process Monitor
ML20137K6111995-12-0707 December 1995
Auxiliary Feedwater Pump 1C Disassembly Insp & Reassembly Mechanical Maint Procedure for St Lucie Plant,Unit 1
ML17228B3461995-11-16016 November 1995
Rev 0 to Plant Administrative Procedure 2-0010024, Inservice Testing Program for Pumps & Valves.
ML20137P3061995-08-31031 August 1995
Rev 2 to Procedure 2-1220057, Functional Testing of RM-80 Power Supply Assemblies
ML17228B0491995-02-0303 February 1995
Rev 0 to Subsequent Inservice Exam Plan for Pressurizer Instrument Nozzles.
ML17228B0171995-01-0606 January 1995
Rev 5 to Second 10-Yr ISI Interval IST Program for Pumps & Valves St Lucie Nuclear Power Plant Unit 1.
ML17228A8811994-09-28028 September 1994
Rev 0 to PSL-200-AOA-94-1, St Lucie Nuclear Plant,Unit 2 ISI Interval Request for Authorization of Alternative Exam. W/Attachment Re Implementation of Reg Guide 1.150
ML20137M1611994-09-15015 September 1994
Rev 2 to Procedure 1-1220053, Calibr of Control Room Outside Air Intake Monitors
ML20080M4881994-06-14014 June 1994
Rev 15 to Chemistry Procedure C-200, Odcm
ML20080M4791994-01-14014 January 1994
Rev 14 to Chemistry Procedure C-200, Odcm
ML17228A4621994-01-14014 January 1994
Rev 4 to Second Ten-Yr ISI Interval IST Program.
ML17228A2471993-07-24024 July 1993
Rev 0 of PSL-201, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval ISI Selected Component Schedule.
ML17228A2461993-07-24024 July 1993
Rev 0 of PSL-200, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval Program Plan & Schedule from 930808- 200808
ML20137P3551993-03-0808 March 1993
Rev 1 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms)
ML17227A6011992-08-11011 August 1992
Rev 2 to JNS-PSL-204, First Ten-Year Inservice Inspection Interval Inservice Testing Program for Pumps & Valves, St Lucie Nuclear Power Plant,Unit 2.
ML20141M4901992-07-30030 July 1992
Rev 14 to Training & Qualification Plan
ML20137P3431992-04-10010 April 1992
Rev 1 to Procedure 1-1220053, Calibration of Control Room Putside Air Intake Monitors
ML17223B2931991-10-10010 October 1991
Rev 3 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves,St Lucie Nuclear Power Plant,Unit 1.
ML20137P2971991-07-0303 July 1991
Rev 1 to Procedure 2-1120070, Containment High Range Radiation Monitor Calibration
ML20070T9761991-03-12012 March 1991
Rev 10 to Training & Qualification Plan
ML17223A5771990-03-0707 March 1990
Rev 10 to Emergency Procedure 1-0030143, Total Loss of Ac Power.
ML17223A4501989-12-15015 December 1989
Rev 2 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves.
ML17308A1901988-08-24024 August 1988
Vols 1 & 2 to Rev 0 to JNS-PSL-100, St Lucie Plant Unit 1 Second 10-Yr Insp Plan.
ML17221A7041988-04-0404 April 1988
Rev 0 to Pump & Valve Inservice Test Program.
ML17342B0641987-12-30030 December 1987
Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co.
ML17308A1831987-09-0202 September 1987
Rev 0 to Inservice Insp Second 10-yr Summary Program.
ML17221A3781987-08-11011 August 1987
Inservice Testing Program,Section I,Valve Test Program & Section Ii,Pump Test Program.
ML17221A3961987-01-28028 January 1987
Rev 1 to St Lucie Unit 1,Extraction Steam Piping Insp Program Guidelines.
ML17347A2241986-12-22022 December 1986
Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr
ML17216A6651986-06-17017 June 1986
Rev 4 to Maint Procedure 2-0910053, 12-Month Test of Automatic Load Sequence Relays.
ML17216A6661986-03-26026 March 1986
Rev 5 to Maint Procedure 2-2200063, 2B Emergency Diesel Electrical Insp.
ML17216A6671986-03-26026 March 1986
Rev 4 to Maint Procedure 2-2200062, 2A Emergency Diesel Electrical Insp.
1999-06-30
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Text
3 e tp~t't'LORIDA POWER&LIGHT COMPANY ST.LUCIE UNIT i'll E-PLAN IMPLEMENTING PROCEDURE 3100025E REVISION 6 1.0 Title: FIRE EMERGENCIES 2.0~Atoval: Reviewed by Facility Review Group Approved by K.N.Harris Plant Manager July 25,1975 Jul 29,1975 Revision 6 Reviewed by F R G Approved by 3.0~3co e: Plant Manager/is , 19K/Z, 19~3.1 Purpose This procedure provides instructions to control and extinguish fires, minimize damage and prevent personal injuries.3.2 Discussion 3.2.1 Any uncontrolled fire is considered a Fire Emergency.
In order to control and extinguish a fire, a fire fighting organization has been established.
3.2.2 The Fire Team is composed of members of the Operating group assigned to the St.Lucie Plant.The members of the Fire Teams are qualified in fire fighting.3.2.3 For a list of the locations of fire fighting equipment, refer to the Mechanical Maintenance preventive maintenance program as delineated in Admin.Procedure No., 0010431"Preventive Maintenance Program".3.2.4 The emergency classification system includes certain fire related events.Thus, fires may be classified as Unusual Events, Alerts, or Site Area Emergencies.
3.3~Auttotlt This procedure implements the St.Lucie Plant Emergency Plan and Fire Protection Plan.4.0 Precautions:
4.1 Class"C" fire extinguishers (C02 or Dry Chemical)or fog type fire hose nozzles shall be used on combustible liquid fires, electrical fires or on fires which might involve energized conductors and/or equipment.
8l09020026 810827,'DR ADOCK 05000335'P.DR, 1 1 0 t Page 2 of 4 E-PLAN IMPLEMENTING PROCEDURE 3100025E FIRE EMERGENCIES REVISION 6 4.0 Precautions (continued) 4.2 Foam type fire extinguishing materials shall not be used on electrical fires.4.3 When fighting fires in the Radiation Controlled Area that may involve radioactive materials, the members of the Fire Team shall use additional protective equipment specified by the Radiation Team Leader and shall follow any instructions he issues regarding precautions to observe while fighting the fire.5.0 Responsibilities:
5.1 The Nuclear Watch Engineer is the Fire Team Leader.If he is not available, the Nuclear Turbine Operator acts as his alternate..
It shall be the responsibility of the Fire Team Leader to: 5.1.1 Direct all phases of the fire fighting activities.
5.1.2 Coordinate
the activities of any outside fire fighting organization called in to assist with the emergency.
5.2 It shall be the responsibility of each Fire Team member to be thoroughly familiar with the contents of this procedure and the location of fire fighting equipment in the plant.5.3 All personnel shall be familiar with the location of, and be familiar with operation of fire equipment in their designated work stations.5.4 On the basis of observations, the Nuclear, Plant Supervisor is responsible for classification of the emergency.
He is also responsible for making notifications and taking other actions appropriate to the emergency class.6.0
References:
6.1 St.Lucie Plant Emergency Plan.6.2 E-Plan Implementing Procedure EP3100023E
, On-Site Emergency Organization/and Roster.6.3 St.Lucie Plant Administrative Procedure No.1800022 Fire Protection Plan".6.4 St.Lucie Plant Administrative Procedure No.0010431"Preventive Maintenance Program".7.0 Records: Any actions taken shall be recorded in the Nuclear Plant Supervisor's Log Book.
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0 E-PLAN IMPLEMENTING PROCEDURE 3100025E FIRE EMERGENCIES REVISION 6 Page 3 of 4 8.0 Instructions:
8.1 When an individual discovers a fire which can be safely extinguished using fire fighting equipment at hand, he shall do so and then promptly notify the Nuclear Plant Supervisor.
8.2 When an individual discovers a fire or.explosion resulting in a fire which cannot be extinguished using fire fighting equipment at hand,he shall notify the Nuclear Plant Supervisor over the PA system or the control room by dialing 333 on any PAX telephone.
The following information shall be given: 8.2.1 Location of the fire.8.2.2 Type of fire, if known.8.2.3 Whether or not there are any injured personnel.
8.2.4 Extent of damage to plant components.
NOTE: Speed in notification is much more important than the completeness of the initial report.8.3 The Nuclear Plant Supervisor shall instruct the individual to take any immediate action he is qualified to perform to extinguish the fire.8.4 The Nuclear Plant Supervisor shall cross-connect the PA system, declare a Fire Emergency, announce the location of the fire, and sound the fire alarm..If sufficient information is available, he shall classify the-emergency and implement the Emergency Plan.(1)The Nuclear Watch Engineer will direct, by use of the page.system, which members will meet him at the fire site, and which members will go to the fire house.(2)If the fire is found to be in the Radiation Controlled Area, the Radiation Team shall be activated by the Emergency Coordinator (Nuclear Plant Supervisor).
(3)If the fire or explosion is in the Radiation Controlled Area, they shall wear appropriate protective clothing and respiratory equipment and personnel monitoring devices, attempt to stay upwind of the fire, and coordinate their actions with the Radiation Team.(4)Other'lant personnel except the operators on watch shall report to the maintenance shop and be ready to assist in the.fire or explosion fighting operations when called upon.
0 E-PLAN IMPLEMENTING PROCEDURE 3100025E FIRE EMERGENCIES REVISION 6 Page 4 of 4 8.4 (continued)
(5)During normal working hours additional personnel are available from the maintenance department to support fire fighting efforts until outside assistance is obtained.(6)The Emergency Coordinator (Nuclear Plant Supervisor) shall designate additional available on-site personnel to assist in extinguishing the fire, as required by the situation.
8.4.1 Requesting
Outside Fire Assistance:
(1)If the fire is too large to be controlled by available plant forces, the St.Lucie County-Ft.
Pierce Fire District shall be called by the Emergency Coordinator.
(2)The main guard station shall be notified of the location of-the fire and the expected arrival of the off-site fire fighting equipment.
(3)Working commuinications shall be established between the Emergency Coordinator, the person in charge of the off-site fire fighting organization, the Radiation Team Leader, if the fire is in the Radiation Controlled Area, and the Fire Team Leader.St.Lucie County-Ft.
Pierce OR St.Lucie County Emergency Center 461-1547 464-1122 911 (4)In the case of an uncontrolled fire, not involving a safety system, but requiring off-site support, the Nuclear Plant Supervisor shall declare an UNUSUAL EVENT.(5)In the case of an uncontrolled fire, potentially affecting safety systems and requiring off-site support, the Nuclear Plant.Supervisor shall declare an ALERT.(6)In the case of a fire resulting in degradation of safety systems, the Nuclear Plant Supervisor shall declare a SITE AREA EMERGENCY.
NOTE: See E-Plan Implementing Procedure 3100023E, Emergency Roster, for specific information regarding means of communication and telephone numbers.
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