|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test 1999-07-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17352A3821993-12-28028 December 1993 Third Ten-Yr ISI Interval IST Program for Pumps & Valves. ML17353A7621992-12-28028 December 1992 Pre-fire Plan Guidelines & Safe Shutdown Manual Actions. ML17349A7491992-12-0808 December 1992 Revised Odcm. ML17349A3711992-05-21021 May 1992 Rev 10 to Procedure PT-51-WS, Solidification Process Control Procedure. ML17349A2511992-03-27027 March 1992 Rev 0 to Pc/M 91-128, 480 Volt Undervoltage Protection Scheme Mod for Unit 3 ML17348B4121991-10-22022 October 1991 Health Physics Procedure 0-HPS-042.8, Dewatering Controls for Radwaste Liners. ML17348A2801990-05-31031 May 1990 Rev 1 to Emergency Power Sys Enhancement Project Testing Rept. ML17348A5381990-02-13013 February 1990 Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17347B4891989-12-18018 December 1989 Administrative Procedure AP 11550.92,Health Physics Procedure HP-92, Emergency Radiation Team Response - Offsite. W/891218 Ltr ML17347B3681989-10-0202 October 1989 Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves, Rev 2 ML17347B2851989-08-17017 August 1989 Change a to Rev 1 to JNS-PTN-200, Second Ten-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves. ML17347B2951989-03-21021 March 1989 Procedure 3-EOP-ECA-0.1, Turkey Point Nuclear Plant Unit 3 Loss of All AC Power. ML17348B4131988-03-10010 March 1988 Rev 8 to Procedure PT-51, Solidification Process Control Procedure. ML17342B0641987-12-30030 December 1987 Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co. ML17342A9971987-10-26026 October 1987 Procedure 0-ADM-019, Mgt on Shift. ML17342B0191987-10-24024 October 1987 Procedure 0-ADM-019, Mgt on Shift (Mos), Weekly Summary Rept for Wk Starting 871024 ML17342A8141987-07-24024 July 1987 Draft Revs to Procedures Generation Package. ML20076H2831987-05-31031 May 1987 Rev 0 to Technical Note 51187, Procedures for Repairing Prefabricated Panel & Preshaped Conduit Section Fire Barriers Installed at Plant ML17347A3081987-01-26026 January 1987 Emergency Procedure EP 20109, Criteria for & Conduct of Local Evacuations. ML17347A3071987-01-26026 January 1987 Emergency Procedure EP 20107, Fire/Explosion Emergencies. 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 ML17342A9111986-11-18018 November 1986 Off-Normal Operating Procedure 3208.1, Malfunction of RHR Sys. ML20215L8241986-09-23023 September 1986 RCS Pressure Boundary Check Valves 4-874A & B Leak Test, for Unit 4 ML20215L7031986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-3-750 &/Or MOV-3-751 Leak Test, for Unit 3 ML20215L7881986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 3 ML20215L7791986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-4-750 &/Or MOV-4-751 Leak Test, for Unit 4 ML20215L8001986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 4 ML20215L8191986-09-23023 September 1986 RCS Pressure Boundary Check Valves 3-874A & B Leak Test, for Unit 3 ML20076H4411985-11-0606 November 1985 Rev 4 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4491985-10-11011 October 1985 Rev 3 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Precedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4531985-09-20020 September 1985 Rev 2 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20199E4531985-08-23023 August 1985 Off-Normal Operating Procedure 9408.2, Energizing 4 Kv Buses Using Cranking Diesels Bus Tie Lines or Startup Transformer from Opposite Unit ML20199E4611985-08-23023 August 1985 Off-Normal Operating Procedure 7308.1, Malfunction of Auxiliary Feedwater Sys ML20199E4111985-08-22022 August 1985 Operating Procedure 7201.1, Standby Steam Generator Feedwater Sys - Operating Instructions. Related Info Encl ML20199E4321985-08-22022 August 1985 Off-Normal Operating Procedure 9408.3, Loss of Voltage to 'C' 4,160 Volt Bus ML20076H4611985-03-28028 March 1985 Rev 1 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4721985-03-15015 March 1985 Rev 0 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Powecorp,Turkey Point Npp ML17346A8291985-02-0404 February 1985 Procedures Generation Package. ML17346A6701984-12-31031 December 1984 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents. ML17346A5621984-09-26026 September 1984 Revised Emergency Operating Procedures,Including O-ADM-110 Re Verification Guideline for Emergency Operating procedures,O-ADM-111 Re Emergency Procedure Validation Plan & Procedures Generation package.W/841001 Ltr ML17346A5391984-09-0101 September 1984 Emergency Plan Implementing Procedure 1107, Duties of Emergency Planning Supervisor,Offsite Emergency Organization. ML17346A5401984-09-0101 September 1984 Emergency Plan Implementing Procedure 1211, Activation & Use of Emergency News Ctr (Turkey Point),Offsite Emergency Organization. 1998-08-27
[Table view] |
Text
FL IDA POWER AHD LIGHT COHPAHY TURKEY POINT UNITS 3 AND 4 EMERGENCY PROCEDURE 20107 HAY 7, 1981
1.0 Title
F IRE/EXPLOS IOH EMERGENCIES
- 2. 0 A royal and Li st of Effecti ve Pa es:
- 2. 1 ~Aroval:
Change dated 5/7/81 Reviewed by PNSC Ha 7, 1981 Approved by Plant 1~1gr-Nuc DCrW~ 5 198~
Approved by Vice President Power Resources e. 2 13+8 2.2 List of Effective Pa es:
~Pa e Date ~Pa e Date ~Pa e Date 1 5/7/81 3 3/13/81 5 4/23/81 2 3/13/81 4 5/7/81 6 4/23/81 7 3/13/81 3.0 ~Sco e:
3.1 ~Por oae:
1 This procedure provides instructions to control and extinguish fires, to minimize equipment damage from fires or explosions and to prevent personnel injuries.
3.2 Discussion
3.2. 1 The Fire Team is composed of five individuals who are qualified in accordance with Administrative Procedure 15500, Fire Protection Program. The fire team members are personnel from the Operations, Health Physics, and Nuclear Chemistry Departments.
3.2.2 Those personnel initiating and:.conducting fire drills shall: Notify the Control Room by calling 260 on the PAX phone, announce "This is a drill. This is a drill", give location and classification of simulated fire/explosion, report any simulated injuries and the extent of damage to plant components.
3.2.3 The emergency classification system (see Emergency Procedure 20103, Classification of Emergencies) includes certain fires and explosions. Hence, each fire or explosion shall be evaluated by the Nuclear Plant Supervisor/Emergency Coordinator to determine if it constitutes an unusual event, an alert, or a site area emergency.
~~81090202S9 g~P>2>~~
PDR ADQCK OS0002SO
', F ~
P)DR/
3/13/81, EMERGENCY PROCEDURE 20107, PAGE 2 FIRE/EXPLOSION EMERGENCIES Technical Specification 6.8. 1 Facility Operating Licenses DPR-31,Section III, G, and DPR-41,Section III F.
Letter from A. Schwencer of NRC to R. E. Uhrig dated 3/21/79 (NRC Safety Evaluation Report for Fire Protection) 10 CFR 50, Appendix R 10 CFR 50.48 Turkey Point Plant Emergency Plans
3.4 Definitions
The terms that must be familiar to the user in order to fully implement this procedure are as follows:
3.4.1 Class "A" Fires Class "A" fires are ordinary combustible fires in such materials as wood, paper, cloth, or rubber.
3.4.2 Class "B" Fires Class "B" fires are fires in flammable liquids, gases, and greases.
3.4.3 Class "C" Fires Class "C" fires are fires which involve "energized" electrical equipment. (Where electrical equipment is de-energized, extinguishers for Class "A" or "B" fires may be used).
3.4.4 Class "D" Fires Class "D" fires are fires in combustible metals such as magnesium, titanium, zirconium, sodium and potassium.
4.0 Precautions
- 4. 1 Water in the vicinity of high voltage electrical equipment may constitute a life hazard to personnel due to the electrical conductivity of water.
Water hoses should be operated with a fog pattern only and at a distance of 10 feet or more from any energized electrical equipment.
4.2 Portable multipurpose dry chemical extinguishers may be used on the following class fires:
- 1. Class "A"
- 2. Class "8"
- 3. Class "C" 4.3 Portable carbon dioxide fire extinguishers may be used on the following class fires:
- 1. Class "B"
- 2. Class "C"
3/13/81 E AGENCY PROCEDURE 20107, PAGE 3 FIRE/EXPLOSION EMERGENCIES 4.4 AFFF foam shall be used only on Class "8" fires, where energized electrical equipment is not present.
4 5 The installed Halon 1301 gas system in Document Control is safe as installed. However, the discharge of Halon 1301 may create hazards to personnel such as dizziness, impaired coordination, reduced visibility and exposure to toxic decomposition products. For this reason personnel should leave the area immediately. Self-contained breathing apparatus is required to re-enter the area until the building is ventilated.
5.0 Res onsibilities:
- 5. 1 It shall be the responsibility of the Fire Team Leader (normally the Nuclear Match Engineer) to:
- 5. 1. 1 At the beginning of the shift verify the on-site availability of four qualified Fire Team Members in addition to himself. Normally, the four members will be the Nuclear Operator, the Nuclear Turbine Operator, a Radiation Protection Man, and a Lab Technician.
- 5. 1.2 Direct all phases of the fire fighting activities.
- 5. 1.3 Communicate the status of the fire and fire fighting activity to the Emergency Coordinator.
- 5. 1.4 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 The Plant Manager-Nuclear shall designate in writing an individual(s) to verify through regular inspections that all fire fighting equipment and supplies are in good condition and operable.
5.4 For 'a fire, it shall be the responsibility of the Nuclear Plant Supervisor or designee to complete the attached fire drill evaluation sheet.
5.5 For a fire drill, the person conducting the drill (normally'rom the Training Department) is responsible for completing the fire drill evaluation sheet.
5.6 The Nuclear Plant Supervisor/Emergency Coordinator is responsible for classifying fires and explosions as unusual events, alerts, or site area emergencies in accordance with Emergency Procedure 20103, Classification of Emergencies.
0 EMERGENCY PROCEDURE 20107,
~
PAGE 4 5/7./81 F IRE/EXPLOSION EMERGENCIES 6.0
References:
- 6. 1 Turkey Point Plant Emergency Plans 6.2 Final Safety Analysis Report (FSAR) 6.3 10 CFR 50, Appendix R 6.4 10 CFR 50.48
7.0 Records
- 7. 1 Log entries in Nuclear Plant Supervisor's Log Book 7.2 Completed fire/drill evaluation sheets constitute guality Assurance Records and, therefore, shall be retained in accordance Procedure 0190.14, Document Control and equality Assurance with'dministrative Records.
8.0 Instructi ons
- 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 llucl ear Plant Supervisor Jor the appropriate control ~roon .
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 for the appropriate control room over the PA system or by dialing 260 on any PAX ~tele hone . The following information should be given:
8.2. 1 Location of the fire or explosion.
8.2.2 Type of fire or explosion, if known.
8.2.3 Whether or not there are any injured personnel.
8.2.4 Extent of damage to plant components.
t<OTE: Speed in notification is much more important than the completeness of the initial report.
8.3 The Nuclear Plant Supervisor for the control room operator contacted shall instruct the individual to take any immediate action he is qualified to perform to extinguish the fire.
JHOTE: In the case of the control room receiving the notification, the individual receiving the call shall notify the Nuclear Plant Su ervisor .
8.4 The Iiuclear Plant Supervisor Jor his desiqenee shal I cross-connect tile PA system, sound the fire alarm, wait for the fire alarm to stop, then immediately announce the fire/explosion in the following manner:
For Fires: "This is not a drill. This is not a drill," and give the location and classification of the fire/explosion. Then announce, "All personnel in the fire area withdraw to a safe location."
4/23/81
~ ~
GENCY PROCEDURE 20107, PAGE 5 F IRE/EXPLOS ION EMERGENC IES For Fire Drills: "This is a" drill. This is a drill," and give the location and classification of the simulated fire/explosion. Then announce, "All personnel in the fire area withdraw to a safe location."
8.4. 1 When word of the Fire/Explosion is passed over the page:
- 1. The Fire Team Leader shall respond immediately to the fire before dressing out. He will take a radio with nim, communicate with the Emergency Coordinator, and take steps to limit the spread of the fire.
- 2. The Nuclear Turbine Operator and Health Physics fire team members will report to the fire locker, dress out as fast as possible, carry their self-contained breathing apparatus and an extra turnout coat, helmet, pair of gloves and boots (to be used by the Fire Team Leader) to the fire.
8.4. 2 The Nuclear Operator and Lab Technician fire team members will report to the fire house, dress out as fast as possible, carry their self-contained breathing apparatus and an extra one (for use by the Fire Team Leader) to the i re location.
NOTE: A list of the locations of fire protection equipment is included in Maintenance Procedure 15537.2, Periodic Surveillance of Fire Protection Equipment.
- 8. 4.3 Upon arrival of the Fire Team Members, the Fire Team Leader shall give instructions to them for fighting the fire. While the Fire Team Members begin extinguishing the fire, the Fire Team Leader can put on his protective equipment and join them.
8.4.4 In the event of a fire in a radiation area, the protection of life and property may require more immediate attention than the radiological hazard itself. Only when it has been determined or suspected that the fire is in an unusually high radiation area or in a high airborne activity environment should the radiological effort be permitted to interfere with extinguishing the fire.
8.4.5 J If a fire is classified as an ALERT or SITE AREA EMERGENCY pursuant to Emergency Procedure 20103, Classification of Emergencies, notify the Nuclear Regulatory Comission within one hour in accordance with Administrative Procedure 0103. 12, Notification of Significant Events to ~NRC .
8.4.6 Requesting Outside Fire Fighting Assistance
- 1. If the fire, or explosion resulting in a fire, is considered by the Nuclear Pl ant Super vi sor/Emergency Coordinator based on reports from the fire team leader as probably beyond the capability of the fire teams to contain, the Dade County Fire Department shall be called. Whereupon, at the option of the Nuclear Plant Supervisor/Emergency Coordinator, if the fire cannot be controlled by the additional forces, then the Homestead Air Force Base Fire Department shall be called.
4/23/8j EMERGENCY PROCEDURE 20107, PAG 6 FIRE/EXPLOSION EMERGENCIES
- 2. If the fire, or explosion resulting in a fire, is too large to be controlled by available plant forces and is in the Radiation Controlled Area, the Homestead Air Force Base Fire Department shall also be called.
- 3. The Main Entrance Station Guard shall be notified of the "
location of the fire and the expected arrival of the off-site fire fighting equipment.
Working communications 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.
NOTE: See Emergency Procedure 20104, Emergency Roster, for specific information regarding means of communication and telephone numbers.
8.5 Fire/Drill Evaluation:
8.5. 1 The Nuclear Plant Supervisor/Emergency Coordinator or the person conducting the fire drill shall complete and forward the Fire/Drill Evaluation Sheet to the Fire Protection/Safety Coordinator and a copy to the Fire Team Training Supervisor and a copy to Document Control for retention.
I 3/13/81
~ to EM uENCY PROCEDURE 20107, PAGE 7 F IRE/EXPLOSION EMERGENCIES APPENDIX A F IRE/DRILL EVALUATION SHEET Date:
- 1. Fire/Fire Drill ( Including location and class of fire)
- 2. Time for fire alarm to sound after fire/drill is initiated:
- 3. Time until fire/drill and location are announced on page:
- 4. Time for first man to arrive at scene:
- 5. Time when all Brigade Members are at scene:
- 6. Evaluation of team leader performance:
- 8. Training given at fire/drill scene:
- 9. Individuals on fire team at scene:
5.
- 2. 6. 10.
- 3. 7.
- 8. 12.
- 10. Critique on fire/drill:
for drill t
- 11. Recommendations program, procedure, changes:
Drill given by:
(Use Reverse Side if Necessary)
a ~
~ s; s
~ I