|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20078A3771994-05-12012 May 1994 Vols 1 & 2 of Vogtle Electric Generating Plant Unit 1 Readiness Review Module 4 Mechanical Equipment & Piping Program ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20035F5601993-04-0505 April 1993 Rev 5 to Inservice Insp Plan (ISI-P-014) for Vogtle Electric Generating Plant,Unit 2 ML20035F0721993-03-22022 March 1993 Rev 7 to Inservice Test Program (ISI-P-008) for Vogtle Electric Generating Plant,Unit 1 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program ML20092G7441992-02-20020 February 1992 Undated Draft Site Safety Manual. Supporting Documentation Encl ML20094K1721991-12-31031 December 1991 Draft, ODCM for Vogtle Electric Generating Plant ML20086Q7231991-12-0404 December 1991 Rev 7 to Procedure 91202-C, Activation & Operation of Operations Support Ctr ML20129J2961991-09-13013 September 1991 Rev 3 to Procedure 23985-1, RCS Temporary Water Level Sys ML20091L7891991-07-0303 July 1991 Rev 5 to Procedure 29537-C, Outage Scheduling ML20079G4971991-06-10010 June 1991 Rev 5 to ISI-P-006, Inservice Insp Program for Vogtle Unit 1 ML20079G5071991-06-10010 June 1991 Rev 4 to ISI-P-014, Inservice Insp Program for Vogtle Unit 2 ML20091L7991991-04-22022 April 1991 Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to Ts ML20091L7771991-04-17017 April 1991 Rev 21 to Procedure 10000-C, Conduct of Operations ML20129H6151991-03-20020 March 1991 Rev 7 to Procedure 10004-C, Shift Relief. Supporting Documentation Encl ML20129J0311990-09-18018 September 1990 Rev 4 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program ML20043B6321990-05-22022 May 1990 Rev 5 to ISI-P-008, Inservice Testing Program ML20043B6381990-05-22022 May 1990 Rev 2 to ISI-P-016, Inservice Testing Program ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events ML20113G6141990-05-15015 May 1990 Rev 0 to VEGP-22981-C, Calcon Pneumatic Temp Sensor Calibr 1TSH-19110-1TSH-19119,1TSH-19146,1TSH-19153,2TSH-19110- 2TSH-19119,2TSH-19146 & 2TSH-19153. Supporting Documentation Encl ML20034C1061990-04-26026 April 1990 Rev 4 to Inservice Insp Program First 10-Yr Interval ML20129H9081990-04-16016 April 1990 Rev 3 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20113G3421990-04-0404 April 1990 Procedure T-ENG-90-016, DG1A J.W. Temp Monitoring & Recording ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20092F9691990-03-28028 March 1990 Rev 0 to T-ENG-90-15, Unit One Train a DCP 88-V1N0070 Sequencer Functional Test. Supporting Documentation Encl ML20092F8621990-03-28028 March 1990 Rev 1 to Procedure T-ENG-90-11, A-Train Undervoltage Test ML20092F7521990-03-27027 March 1990 Rev 20 to 13145-1, Diesel Generators ML20092F8741990-03-26026 March 1990 Rev 3 to Procedure VEGP 00053-C, B-Train Undervoltage Test ML20092F8481990-03-25025 March 1990 Rev 2 to Generator & Engine Control Panel Functional Test Procedure 27563-C, Power & Signal Removal/Replacement Data Sheet ML20092H0391990-03-23023 March 1990 Rev 16 to VEGP-10000-C, Conduct of Operations ML20092F5271990-03-21021 March 1990 Data Sheet 1 to Rev 12 to VEGP-10006-C, Reactor Trip Rept. Supporting Documentation Encl ML20092F7341990-03-19019 March 1990 Rev 16 to Procedure 25717-C, Torquing Electrical Type Connections ML20092G9111990-03-16016 March 1990 Abnormal Operating Procedure to Rev 7 to VEGP-18028-C, Loss of Instrument Air ML20092F6901990-03-16016 March 1990 Rev 7 to Procedure 18019-C, Abnormal Operating Procedure, Loss of Rhr ML20092F6361990-03-12012 March 1990 Temporary Change Notice to Rev 14 to Procedure 12007-C, Refueling Entry 1998-05-25
[Table view] |
Text
~~~~
App,,,a ero w u s No.
$e Vogt;e Electric Generating Plant 91403-C 7
/
NUCLEAR OPERATIONS
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FOR INFORMATION ON
- 1'h SITE EVACUATION 1.0 PURPOSE The purpose of this procedure is to provide instructions for the early dismissal or evacuation of non-essential personnel including visitors at VEGP in l
the event of an emergency.
q 2.0 RESPONSIBILITIES 2.1 The Emergency-Director shall be responsible for determining the need for early dismissal or evacuation and selecting evacuation routes.
2.2 The Security Coordinator shall be responsible for conducting the evacuation and directing the Security
.~
Force to assist in various stages of the evacuation.
2.3
-The HP Supervisor or Dose Assessment Manager will provide HP support for monitoring and decontamination at the selected offsite relocation center..
l 3.0 PREREQUISITES The Emergenc Director has determined that conditions warrant-earl dismissal or evacuation of-all non-essentia personnel.
4.0 PRECAUTIONS The evacuation should be conducted in an orderly fashion so as to prevent personnel injury.
5.0 PROCEDURE 5.1 EMERGENCY DIRECTOR 5.1.1 The Emergency Director shall order evacuation of non-essential personnel (if feasible) whenever a. Site Area or General Emergency is declared.
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91403-0 4
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5.1.2 The Emergency Director may also order a specified area dhh{
nyacuation under the following conditions:
5.1.2.1 It is determined by actual observation or by calculation that personnel will receive 100 Mrem, or a dose rate of 2.5 Mem/hr in a normally non-radiologically controlled building.
5.1.2.2 It is determined that there is a threat to the health I
and safety to onsite personnel exists.
5.1.2.3 There is no reason to retain these personnel in the area.
5,1.3 The Emergency Director has the option to (1) send personnel. home from work early before there is a danger of radiation exposure or, (2) evacuate personnel to an offsite relocacion center for monitoring, if a release has occurred and contamination is detected or suspected.
5.1.4 Early releases from work shall be initiated and conducted per Subsection 5.7 of this procedure.
5.1.5 The Emergency Director shall confer with the HP r')
Supervisor (or Dose Assessment Manager if EOF is (y
activated) on wind direction and other factors which will influence the choice of whether to evacuate to the crimary or alternate offsite relocation center.
The Imergency Director shall then decide which relocation center shall be utilized.
5.1.6 The Emergency Director shall notify the Security Coordinator (or Supervisor Nuclear Security - SNS if l
EOF is not activated) and inform him of the impending evacuation.
This will allow Security time to prepare and initiate its evacuation activities.
NOTE If this is a drill, the message should be preceded and followed by the statement:
"THIS IS A DRILL "
5.1.7 The Emergency Director shall make the following announcement over the plant PA system:
" ATTENTION ALL PERSONNEL ATTENTION ALL PERSONNEL
- NON-ESSENTIAL PERSONNEL ARE ORDERED TO EVACUATE.
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FOLLOW THE DIRECTIONS OF SECURITY TO ENTER YOUR
(_/
CAR OR DESIGNATED BUS.
REPORT TO THE RELOCATION CENTER AT (relocation center).
REMAIN THERE UNTIL CLEARED TO LEAVE."
$344k
" ~ ' * *
- PRoCEDUAE No nEyestoy p,gg g 91403-C 4
3 of 9 j
i 5.1.8 The Emergency Director shall direct Security (SNS) to e
O activate the site siren, and make an announcement on 4
the site siren PA system in accordance with EPIP 91704-C, " Actions For Security During A Radiological Emergency".
5.1.9 The Emergency Director shall notify the Security Coordinator (or SNS if EOF not activated) so that notification of personnel outside the Protected Area may be performed in accordance with "rocedure 91704-C,
" Actions for Security during a Radiological Emergency".
4 5.1.10 The Emergency Director shall receive periodic reports from the Security Coordinator (or SNS) on the progress i
of the evacuation.
5.2 SECURITY COORDINATOR (OR SUPERVISOR NUCLEAR SECURITY
- (SNS) IF EOF IS NOT ACTIVATED) 1 5.2.1 Upon declaration of an Alert, designate one of the Security Officers to be Evacuation Leader (Subsection 5.4) and dis?atch him to the relocation center along with Health ?hysics support.
This will allow setup prior to evacuees arriving.
5.2.2 Upon notification of the impending evacuation from the O
Emergency Director, the Security Coordinator shall perform the following actions:
5.2.1.1 Designate one of the Security Officers to be Evacuation Leader (Suboection 5.4) and dispatch him to the relocation center if not already performed at an Alert.
5.2.1.2 Dispatch Security Officers to plant gates and traffic control points for traffic control.
5.2.1.3 Contact the HP Supervisor or Dose Assessment Manager to ensure that sufficient Health Physica sup3 ort (at least two individuals) has been dispatched to ele relocation center to conduct radiation monitoring and decontamination.
5.2.1.4 Contact the relocation center and inform them of the impending evacuation.
5.2.1.5 Perform protected area accountability"per Procedure 91401-C, " Assembly and Accountability if not already completed.
5.2.1.6 Check with the HP Supervisor or Dose Assessment Manager concerning radiological conditions prior to dispatching Security Officers to check owner controlled areas to O
assure that all non-essential personnel have been evacuated.
?
7c3 45
._ ~_
PRoCEDUAE No.
REVISloN PAQi'No 91403-C 4
4 of 9 5.3 HEALTH PHYSICS 5.3.1 Designated Health Physics staff shall be dispatched to the relocation center at an Alert to allow setup of the center prior to evacuees arriving.
5.3.2 After informing the Evacuation Leader of their arrival at the offsite relocation center, the Health Physics staff shall establish a monitoring point and if necessary, a decontamination point in accordance with Procedure 91306-C, " Contamination Monitoring and Decontamination".
5.4 EVACUATION LEADER U)on his appointment by the SNS, the Evacuation Leader I
siall report to the relocation center and implement the Evacuation Leader Checklist.
5.5 EVACUATING PERSONNEL Upon activation of the evacuation notiiication, personnel shall proceed to the offsite relocation center, taking directions from Security Officers.
5.6 0FFSITE RELOCATION CENTER AND EVACUATION ROUTES 5.6.1 The Emergency Director shall order evacuation to the VEGP Recreation Area, the primary offsite relocation center, if radiological conditions allow its use.
The evacuation route shall be the main plant access road, see Figure 3.
5.6.2 The alternate offsite relocation center is located at Plant Wilson.
The evacuation route shall be the visitors center access road, see Figure 3.
5.7 EARLY DISMISSAL 5.7.1 The Emergency Director may determine that it is desirable to send persons home before there is a danger of radiation exposure.
5.7.2 The Emergency Director shall direct an early dismissal in accordancu with 91102-C, " Duties Of The Emergency Director".
4 5.8
-POST-EVACUATION CONDITIONS 5.8.1 The Security Coordinator shall assure that all personnel have been evacuated, as appropriate, and shall brief the Emergency Director.
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REVIStoN PAGE No 91403-C 4
5 of 9
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5.8.2 The Security' Coordinator shall collect all accountability forms, relocation center monitoring data and other evacuation records.
5.8.3 The Security coordinator shall ensure that access l
control to the protected area is provided by the Security Department during emergency conditions.
Access will be granted to Emergency Response Personnel and NRC Personnel.
6.0 REFERENCES
6.1 VEGP Emergency Plan 6.2 PROCEDURES 6.2.1 91102-C,
" Duties of The Emergency Director" l
6.2.2 91306-C,
" Contamination Monitoring And i
Decontamination" t
6.2.3 91401-C.
" Assembly And Accountability" 6.2.4 91704-C,
" Actions For Security During A Radiological Emergency"
()
6.3 NUREG-0654, FEMA-REP-1, Rev. 1. " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" i
END OF PROCEDURE TEXT O
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-s PROCEDU,.c No.
GEVI5 ION PAGE NO-91403-C 4
6 of 9 GROUP LOCATION MAP FOR
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i Sheet 1 of 1 EVACUATION LEADER CHECKLIST POSITION FILLED BY: On shift Security Officer RESPONSIBILITY:
Supervise activities at the offsite
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relocation center including monitoring and decontamination of evacuees.
INITIAL ACTIONS:
1.
Upon direction from the SNS, re, ort to the designated I
relocation center along with a Liealth Physics Technician, 2.
Assist the Health Physics Technician to establish a i
decontamination area as necessary.
SUBSEQUENT ACTIONS:
l.*
Provide periodic updates to the SNS (Security coordinator, I
EOF activated) via radio or telephone.
2.*
Direct arriving groups to specific locations (See Figures 1 & 2).
3.*
Supervise the monitoring and decontamination of evacuees.
4.
Request assistance from the SNS (Security Coordinator, EOF i
activated) if required.
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