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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205S9641999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20205A3101999-02-28028 February 1999 Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20151V6991998-09-11011 September 1998 Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20212B1791997-10-31031 October 1997 1 SG ARC Analyses in Support of Full Cycle Operation ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20198T4921997-03-31031 March 1997 Small Bobbin Probe (0.640) Qualification Test Rept ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power 1999-06-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20138A3661996-04-25025 April 1996 Rev 15 to Procedure FNP-O-M-011, Offsite Dose Calculation Manual ML20071P9561994-06-15015 June 1994 Rev 1 to FNP-0-ETP-4338, Svc Water Storage Pond Sounding Survey ML20071Q2831994-03-0808 March 1994 Rev 1 to FNP-0-ETP-4381, Svc Water Storage Pond Piezometer Well Readings ML20071Q3151994-03-0808 March 1994 Rev 1 to FNP-0-ETP-4389, Svc Water Storage Pond Dam Biennial Insp ML20063H7681994-01-0101 January 1994 Rev 13 to Odcm ML20071Q3551993-10-18018 October 1993 Rev 7 to FNP-0-ARP-8, Svc Water Structure ML20071Q3661993-07-13013 July 1993 Rev 26 to FNP-1-ARP-1.1, Main Control Board Annunciator Panel a ML20071Q3751993-06-24024 June 1993 Rev 8 to FNP-0-AOP-31.0, Loss of Svc Water Pond ML20071Q3341993-01-29029 January 1993 Rev 0 to FNP-0-ETP-1035, Svc Water Dam & Structure Monthly Insp ML20071Q4031993-01-0606 January 1993 Rev 8 to FNP-0-STP-125, Svc Water Bond Seepage Test ML20126A1941992-12-0808 December 1992 Rev 2 to FNP-0-M-011, Odcm ML20071Q3051992-05-12012 May 1992 Rev 0 to FNP-0-ETP-4384, Svc Water Pond Deformation Monument Readings ML20071Q3871991-03-28028 March 1991 Rev 4 to FNP-0-STP-611.1, Spillway Channel & Structure Verification ML20071Q3601991-03-28028 March 1991 Rev 4 to FNP-0-STP-611.0, Spillway Channel Insp ML20059D8331990-08-30030 August 1990 Rev 76 to EPIP FNP-0-EIP-008 ML20059J1841990-08-24024 August 1990 Rev 10 to ODCM ML20058P6261990-08-15015 August 1990 Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Classs 1,2 & 3 Components ML20058Q1541990-08-15015 August 1990 Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components ML20248H8811989-10-0404 October 1989 Rev 3 to FNP-1-M-042 Re Second 10-yr Interval Inservice Testing Program for ASME Code Class 1,2 & 3 Pumps & Valves ML19325C6751989-09-25025 September 1989 Rev 8 to FNP-0-M-011, Odcm. ML20244B4531989-04-0303 April 1989 Rev 7 to FNP-0-M-011, Odcm ML20247C7721989-03-24024 March 1989 Rev 0 to FNP-2-M-068-1, Updated Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20151U2981988-05-31031 May 1988 Suppl 1 to EQDP-ESE-68B, ATWS Mitigating Sys Actuation Circuitry in Amco Cabinet & Wall Mounted Hoffman Relay Enclosure ML20151Y7341988-04-30030 April 1988 Westinghouse MT-SME-186, Background & Technical Basis for Handbook on Flaw Evaluation for Jm Farley Nuclear Plant, Units 1 & 2 Reactor Vessel Beltline & Nozzle to Shell Welds ML20151R3301988-04-14014 April 1988 Rev 5 to General Ofc Emergency Implementing Procedure GOP-EIP-116, Emergency Operations Facility Shift Turnover ML20151S0141988-04-12012 April 1988 Rev 4 to Offsite Dose Calculation Manual ML20236T2641987-11-23023 November 1987 Draft Rev 0 to FNP-1-M-043, Second 10-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20150C2271987-09-18018 September 1987 Rev 4 to FNP-0-M-011, Offsite Dose Calculation Manual ML20150C2201987-08-0505 August 1987 Rev 3 to FNP-0-M-011, Offsite Dose Calculation Manual ML20214P4381987-05-27027 May 1987 Rev 0 to FNP-1-M-042, Second 10-Yr Pump & Valve Inservice Testing Program ML20213H0721987-05-12012 May 1987 Rev 1 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures Verification ML20213H1011987-05-12012 May 1987 Rev 2 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures Verification ML20213A1771986-12-31031 December 1986 Rev 1 to Incident Investigation Manual ML20214K4911986-07-11011 July 1986 Rev 2 to Offsite Dose Calculation Manual ML20154C8681986-02-21021 February 1986 Revised Emergency Plan Implementing Procedures,Including Rev 40 to FNP-0-EIP-8, Emergency Communications & Rev 13 to FNP-0-EIP-26, Offsite Notification ML20133H1181985-10-11011 October 1985 Attachment to Procedure FNP-85-1072 Re on-call Schedules Concerning Both Plant & Nuclear Generation Personnel. Schedules Effective 851001 ML20132E9211985-07-23023 July 1985 Corrected Rev 15 to Emergency Plan Implementing Procedure FNP-0-EIP-4, Chemistry & Environ & Health Physics Support to Emergency Plan ML20133G9431985-05-21021 May 1985 Rev 1 to FNP-0-M-011, Offsite Dose Calculation Manual ML20100H4071985-02-26026 February 1985 Public Version of Revised Attachments a & B to Procedure FNP-0-EIP-8 Re on-call Schedule for Plant Personnel for 1985 & on-call Schedule for Nuclear Generation Personnel for First Quarter 1985 ML20101L5421984-12-27027 December 1984 Rev 5 to General Ofc Emergency Implementing Procedure GO-EIP-131, Emergency Operations Ctr - Flintridge Emergency Equipment & Supplies ML20101L5121984-12-27027 December 1984 Rev 9 to General Ofc Emergency Implementing Procedure GO-EIP-111, Corporate Activation & Notification Procedures ML20101E6061984-12-14014 December 1984 Rev 1 to Emergency Implementing Procedure FNP-0-EIP-30, Post-Accident Core Damage Assessment ML20198D3081984-09-24024 September 1984 Rev 3 to STD-P-05-003, Process Control Program for In-Container Solidification of 4 to 20 Weight Percent Boric Acid ML20095D4101984-08-17017 August 1984 Revised Emergency Plan Implementing Procedures,Including GO-EIP-101 Re Corporate Emergency organization,GO-EIP-135 Re Emergency Plan Review & Rev & GO-EIP-120 Re Ref Guidance for Recovery Manager ML20198D3171984-08-0606 August 1984 Rev 5 to STD-P-05-004, Progress Control Program for In-Container Solidification of Bead Resin ML20093G4051984-07-17017 July 1984 Public Version of Rev 5 to Emergency Plan Implementing Procedure GO-EIP-111, Corporate Activation & Notification Procedures. W/Jm Felton 840717 Release Memo ML20093G3561984-07-17017 July 1984 Public Version of Rev 29A to Emergency Plan Implementing Procedure FNP-0-EIP-8, Notification Roster 1998-04-19
[Table view] |
Text
.
h VOLUME 14 FNP-0-EIP-13 October 31, 1980 Revision 6 FARLE'I NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE FNP-0-EIP-13 S
A F
E T
Y FIRE EFERGENCIES R
E L
A T
PERSONAL FRIVACY INFOR'!!ATION E DE!E!33 IN ACCORDANC3 NIIH HE D FEEEDOM OJ IN705 dAIION ACT '
Approved:
U . .). Nnt ww '
PT: St Manager Date Issued: // Id Date of Implementation: 11-17-80 Diskette #EIP-1 List of Effective Pages DOCUMENT CONTROf.
Page Rev. CONTROLLED COPY 1, 2 , 4, 5 , 8,6, 7 6 3 5 DO NOT REPRODUCE COPY NO,. O Checklist pg.1 ,
Fig. 1 6
[1 hYl$ h) .
l FNP-0-EIP-13 VOLUME 114 i l
FIRE EMERGENCIES 1.0 Purpose This procedure establishes the initial and subsequent action to be taken by personnel on the plant site in the event of fire in the Controlled Area or fire which could affect operations in the Controlled Area.
2.0 References 2.1 Joseph M. Farley Nuclear Plant Emergency Plan.
2.2 FNP-0-EIP-1, Duties of an Individual Who Discovers an Emergency Condition.
2.3 FNP-0-EIP-2. Duties of the Shift Supervisor.
2.4 FNP-0-EIP-3, Duties of the Emergency Director.
2.5 FNP-0-EIP-7, Security Support to the Emergency Plan.
2.6 FNP-0-EIP-8, Notification Roster.
2.7 FNP-0-EIP-9, Radiation Exposure l'timation and Classification of Emergencies.
2.8 FNP-0-EIP-10, Evacuation and Personnel Accountability.
2.9 FNP-0-AP-37, Fire Brigade Organization.
2.10 FNP-0-EIP-26, Offsite Notification 2.11 FNP-0-EIP-12, Alert 2.12 FNP-0-EIP-18, Site Emergency 3.0 General 3.1 A Controlled Area evacuation will be effected by the Shift Supervisor or Emergency Director, as necessary, to protect the health and safety of personnel occupying the Controlled Area.
3.2 Any fire that occurs in a Radiation controlled Area (RCA) shall be considered to involve radio-active material and monitoring by the Radiation.
Monitoring Team shall be required.
! 3.3 Except in unusual cirewnstances, the threat to life and property from fire exceeds ' that from radiation exposure. Radiation control should be considered, but should not be permitted to interfere with the fire fighting effort unless the radiological hazard is significant.
Rev. 6 1 .
1 i
l l
I VOLUME 14 ~ FNP-0-EIP-13 l
l 3.4 If a fire involves radioactive material or has a high potential of involving radioactive materials, appropriate clothing and equipment shall be used and monitoring shall be provided by the Radiation Monitoring Team.
3.5 The assembly aress for an evacuation as a result of the Plant Eme cency Alarm shall be:
3.5.1 As defined in EIP-10, if normal assembly areas are not affected by the fire.
- 3.5.2 The plant road (Figure 1) inside the i
sourthern boundary of the Controlled Area shall be used, if the fire is in the Service Building.
3.5.3 The Switchhouse (Figure 1) shall be used in the event that the fire has rendered the entire Controlled Area untenable.
3.6 Personnel accountability as a result of a local fire evacuation in the Controlled Area or as a result of a major fire evacuation shall be performed in accordance with EIP-10.
! 3.7 Notifications which could be required during a a fire emergency are listed in EIP-26 and are l shown in Figure 2. Telephone numbers are listed
, in EIP-8.
3.8 Fi:e fighting assistance may be requested, as
)
ner.ded, from the Dothan Fire Department (DFD),
which nominally consists of:
i 3.8.1 Manpower:
, (a) Total personnel - 105 (b) Combat personnel - 91 (c) Paramedics - 15 (d) Total Companies - 5 i
(e) Companies available for assistance at
! Farley Nuclear Plant - 3
3.8.2 Resources
(a) 500 gallon pumperc - 7 (b) Minimum pumping capac;ty for 3 available companies - 2750 gym (c) Ladder / Snorkel Trucks - 1 1
Rev.' 6 i
2-
_ _ _. _ _. - _ - . _ _. _ . . _ _ _ __n.
VOLUME 14 FNP-0-EIP-13 3.8.3 Response time from the time a call is
- claced from FNP until the DFD is set up
'at the scene of the fire i.e estimated at 30 minutes.
4.0- Procedure 4.1 Initial action.
4.1.1 The individual d:scovering the fire
- shall
4.1.1.1 Contact the control room and report the location, type and size of the fire.
4.1.1.2 Attempt to extinguish or isolate the fire to the best of his ability and judgement.
4.1.2 The plant operator shall:
4.1.2.1 Immediately notify the Shift Supervisor of the location, type and size of the fire.
4.1.2.2 In case of a significant fire, sound the Plant Emergency Alarm as necessary to ensure personnel evacuation, and to alert the fire brigade; announce the location of the fire, evacuation orders and assembly area (s) on the public address system.
4.1.2.3 Place the unit in a safe
! condition.
4.1.3 The Shift Supervisor shall (refer to EIP-13A, Fire Emergency Checklist):
4.1.3.1 Enaure the affected unit is in a s. fe condition and assess the scope of the fire.
4.1.3.2 Direct the Fire Brigade Chief in fighting the fire.
4.1.3.3 Direct the plant operator to ensure the affected unit is maintained in a safe condition.
Rev. 5 3
VOLUME 14- FNP-0-EIP-13
- 4.1.3.4 Implement EIP-12 if the fire may potentially affect ECCS.
4.1.3.5 Implement EIP-19 if the fire affects ECCS.
4.1.3.6 Perform the notifications listed in EIP-26.
4.1.3.7 If. time and personnel permit, dispatch a Radiation Monitoring Team to meet the outside agency at the CSC Building.
4.1.3.8 Continue to reassess the situation for evacuation requirements and notify personnel accordingly.
4.1.3.9 Account for all personnel if the Emergency Director is not present.
4.1.4 The Emergency Director shall (refer to EIP-13A, Fire Emergency Checklist):
4.1.4.1 Activate only that portion of i the emergency organization necessary to respond to the incident.
4.1.4.2 Ensure that personnel account-ability has been effected.
4.1.4.3 Implement EIP-12 if the fire may potentially affect ECCS.
4.1.4.4 Implement EIP-18 if the fire affects ECCS.
1 4.1.4.5 Perform notifications per EIP-26.
4.1.5 The Fire Brigade Chief shall:
. 4.1.5.1 Proceed to the fire. Don L appropriate protective clothing and respiratory protection.
equipment, if necessary.
4.1.5.2 Direct the fire brigade in
- fire fighting operations.
Rev. 6 1
1 4
i
, - , , -. . . . - - . . . , - ~ , - - , . - -
~*
VOLUME 14 FNP-0-EIP-13 4.1.6 'The Fire Brigade shall:
4.1.6.1 Report to the locker rocm
' adjacent to the control room when the Plant Emergency Alarm sounds unless otherwise instructed by the control room.
4.1.6.2 Don, protective clothing and respiratory equipment, if necessary.
4.1.6.3 Proceed to the location of the fire with all necessary fire fighting equipment.
4.1.6.4 Follow the instructions of the Fire Brigade Chief in extinguishing the fire.
4.1.7 The Radiation Monitoring Team shall:
4.1.7.1 Report to the Health Physics office adjacent to the control room when the Plant Emergency Alarm sounds unless otherwise instructed by the control room.
4.1.7.2 Don protective clothing and respiratory protection equipment, if necessary.
4.1.7.3 Acccmpany members of the Fire Brigade to the fire.
4.1.7.4 Survey the area of the fire to determine radiological hazards and supervise the use of protective clothing and equipment.
4.1.7.5 If the fire is in the RCA and, time and personnel permit, meet outside agencies at the CSC Building. Equip them with personnel' dosimetry devices and other required items of protective equipment. Remain with the agency personnel for the duration of their stay inside the Controlled Area.
I Rev. 6 j i
5
l FNP-0-EIP-13 VOLUME 14 !
l l
4.1.8 The Emergency Repair Party personnel i
shall:
4.1.8.1 Proceed to their asaembly area (maintenance shop or plant road.outside of the south boundary) whenever the Plant Eme.rgency Alarm sounds.
4.1.8.2 Provide mainteaance support to the Emergency Director, as required.
4.1.9 The AFCo Production Security Force
, shall:
)
4.1.9.1 Meet outside agencies at the CSC Building.
4.1.9.2 If a Radiation Monitoring Team is not present:
4.1.9.2.1 Issue appropriate personnel-dosimetry devices and protective equipment to outside agency personnel.
^
4.1.9.2.2 Lead agency personnel to the emergency.
4.1.9.3 Provide personnel accountability information to plant supervisors or the control room.
4.1.10 The Dothan Fire Department shall:
i 4.1.10.1 Proceed to the CSC Suilding.
4.1.10.2 Obtain personnel dosimetry
. devices and protective equipment at the CSC Building as directed by the Radiation Monitoring Team or security guard.
4.1.10.3 Proceed as directed by the Radiation Monitoring Team or security guard to the location
- of the fire.
. 4.1.10.4 Follow instructions of the
< Fire Brigade Chief and of the Radiation Monitoring Team.
1 Rev. 6 r- 6
,a ,. ,, - - , , , - . - - . - ,n-- -
VOLUME 14 FNP-0-EIP-13 4.2 Subsequent' action.
- 4.2.1 The Dothan Fire Department shall:
4.2.1.1 Be monitored (both personnel and equipment) and be decontam-inated, if necessary, by the Radiation Monitoring Team upon leavinc the RCA. Vehicles shall be monitored prior to release from Protected Area.
4.2.1.2 Return personnel dosimetry devices and any APCo aquipment which was issued, prior to ,
being released from the Protected Area.
4.2.1.3 Provide to the Radiation Monitoring Team the names and social security numbers of all personnel who entered the Protected Area.
- 4.2.2 The Radiation Monitoring Team shall:
4.2.2.1 Continue monitoring area and personnel, if necessary.
4.2.2.2 Decontaminate all personnel and equipment upon leaving the RCA, as necessary.
4.2.2.3 survey all off-site personnel, equipment and vehicles prior to releasing them from the Protected Area.
4.2.2.4 Ensure the return of all AFCo equipment issued to outside agencies (protective clothing, dosimeters, etc.).
4.2.2.5 Obtain the name and social security number of each off-site individual who entered the Protected Area and correlate the information with the appropriate personnel dosimetry device.
Rev. 6 i
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' VOLUME 14 FNP-0-EIP-13 4.2.3 The 3 c-;o Fire Marshal shall:
4.2.3.1 Investigate the cause of the fire and the extent of damage.
. 4.2.3.2 Report findings to the Emergency Director.
4.2.3.3 Supervise recharging or replacing of all firefighting equipment and supplies.
4.2.4 The Emergency Director shall:
Be guided by the following procedures:
FNP-0-EIP-3, Duties of the Emergency Director
- FNP-0-EIP-8, Notification Roster i
! FNP-0-EIP-9, Radiation Exposure Estimation and Classification of Emergencies i FNP-0-EIP-12, Alert (if applicable) i FNP-0-EIP-18, Site Emergency (if applicable)
FNP-0-EIP-26, Offsite Notification
- Implemented if the fire involves a radiation hazard.
Rev. 6 9
~ ~'
FNP-0-EXP-13A
\
FIRE EMERGENCY CHECKLIST Initials I. Shift Supervisor A. Ensure affected unit is in safe condition and assess fire.
B. Direct Fire Brigade Chief in fighting the fire.
C. Ensure affected unit is maintained in a safe condition.
D. Implement EIP-12, if applicable E. Implement EIP-18, if applicable
. F. Perform the notification listed in EIP-26 G. Alert CSC if assistance from outside agencies is required.
- H. Dispatch Radiation Monitoring Team, s if available, to meet outside agency. -
I. Reassess situation for evacuation requirements.
J. Initiate personnel accountability (EIP-10). '-
II. . Emergency Director A. Activate necessary elements of emergency organization to respond
- to incident.
B. Ensure personnel accountability
- (EIP-10).
i C. Implement EIP-12, if applicable D. Implement EIP-18, if applicable E. Perform notifications per EIP-26 i
- Implemented if fire involves a radiation hazard.
i f
Rev. 6 s
- *o FNP-0-EIP-13
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