Public Version of Administrative Memo 42-18 Consisting of Temporary Mod Request T-6833 to Emergency Plan Procedure AD 1827.11 Assembly Accountability & Subsequent EvacuationML20069L146 |
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Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
10/19/1982 |
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From: |
Murray T TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20069L126 |
List: |
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References |
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PROC-821019-01, NUDOCS 8211170037 |
Download: ML20069L146 (9) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
Text
(;. ,
THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN SUPPORTING PROCEDURES REVISION INDEX I J I PAGE i
REVISION 5
PROCEDURES HP 1602.01 REVISION 10 TEMPORARY MODIFICATIONS T-6393
! AD 1827.'01 3 I~3 AD 1827.02 8 AD 1827.03 1 AD 1827.04 2
- AD 1827.05 2 AD 1827.06 2 i
AD 1827.07 2 T-6605 AD 1827.08 1 AD 1827.09 1
, AD 1827.10 12 T-6491 AD 1827.11 3 IJ AD 1827.12 8 AD 1827.13 5 AD 1827.14 1
- AD 1827.15 3 AD 1827.16 1 AD 1827.17 1
[ AD 1850.04 4
'~ AD 1850.05 5
- 3 i ADMINISTRATIVZ MEMORANDUMS REVISION r-lE l 35 '
No. 37 - ECS Pager and Telephone Numbers No. 38 - First Aid Team 28 11 No. 39 - Fire Brigade 13
! No. 41 - Emergency Duty Officer (EDO) 25
. No. 42 - Radiation Monitoring Teams (RMT) 18 -
t Revision 153 g- October, 1982 8211170037 821108 PDR ADOCA 05000346 F PDH
oATE I inh'* 'M$MPANY MEMORANDUM s o c2wa Rev. 17 - August 31, 1982 TJ Rev. 18 - October 16. 1982 l All Davis-Besse Station Fersonnel l PaOM l suuscT Terry D. Murray 3 O W-- --
~
U Radiation Monitoring Teams ADMINISTRATIVE MEMORANDUM NO. 42-18 In accordance with the Davis-Besse Emergency-Plan, the following named people are qualified to be Radiation Monitoring Team Members. AD 1850.05, Radiation Monitoring Team Surveys, provides instructions for collecting samples.
Bill Armstrong Bob Finneran John Tapley Mike Beier Randy Saum Tim Thompson Larry Bonker Jim Kalmback Tony Wakulenko Rick Edwards Greg McKarnd Wayne Wiedenhef Dave Eshelman Joan Niese Mark Rcwland Jack Ferguson Chuck P.ider John Blankemeyer Bill Frazer Reggie Rogers Bilal Sarsour Dennis Honnen Ed Rohrer Pete Senuik Rusa Hofer John Sanlovich Mike Parker
,3 Dave Jazwiecki Phil Strahm Ted Lang d Ford Kabkar Jim Sytowski Ron Wolfe i Linda Makatura Sy Syslo Jennifer Scott-Wasilk
' l 18, Lynn Harde.r Kevin Melstad Gary Downing g Terry Tata Jeff Lieczow
- I
!l TDM/DWB/fas
!I I
.I -
F I
THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN SUPPORTING PROCEDURES REVISION INDEX PACP, REVISION PROCEDURES REVISION TEMPORARY MODIFICATIONS 1 5 HP 1602.01 10 T-6393 HP 1604.01 2 AD 1827.01 3 AD 1827.02 8 AD 1827.03 1 AD 1827.04 2 AD 1827.05 2 AD 1827.06 2 AD 1827.07 2 T-6605 AD 1827.08 1 AD 1827.09 1 AD 1827.10 12 T-6491
- AD 1827.11 3 T-6833 AD 1827.12 8 Ab 1827.13 5 AD 1827.14 1 AD 1827.15 3 AD 1827.16 1 AD 1827.17 1 I,C Q AD 1850.04 AD 1850.05 4
3 I
ADMINISTRATIVE MEMORANDUMS REVISION No. 'l/ - F.CS Pager and Telephone Numbers 28 No. '1H - First Aid Team 11 No. 39 - Fire Brigade 13 No. 41 - Emergency Duty Of ficer (EDO) 25 No. 42 - Itadiation Monitoring Teams (l(MT) 18 Revision 154 October, 1982 0
, ys D15 ISUTION Original, Responsible Sectlan Head Action
- File Copy. Master File e -
- COPES TO BE MODIFIED FOR IMMEDI ATE IMP.5 MENTATION DAVIS BESSE NUCLEAR POWER STATION UNIT 1 TEMPORARY MODIFICATION REQUEST
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SECTION 1 PROCEDURE TITLE AND NUM8ER ,
/i M> J l l A,.itn?t . f< s ,,i. M ,l 2 ad 4 4 <s n / 6. a , , 5 s RE ASON POR CHANGE /' /
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SS PROCEDURE REVISION REQUIRED PREPARED BY p'N ,
DATE #
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APPROVED SY DATE //
h "s * (. C /0*/)*Y1 APPROVED BY CATE g .j - fh'l ' .
l l SUBMITTE
/nin D BY (Sec[ [w]..:.e/J ~J /. , any DATE
, /, ,/;= " I nis2-I j DATE /
1 RECOMMENDED SY (SRB Chairmen
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l QA APPROVED BY ( ~
we e AssureAYe) DATE
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Nl APPROVED OY (Station S.,perinddent) DATE 7
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2 AD 1827.11.3 -
3.3 E Descriptions of the types of emergencies that can require assembly or station evacuation are described in the DBNPS Emergency Plan.
- 4. ASSEMBLY AREAS Definition Those areas designated by this procedure or other procedures to !
garner personnel resources or to serve as a collection point f~or performing personnel accountability.
J' I Personnel with Emergency Response Functions shall respond as directed by the Emergency Implementing Procedure, EI 1300 series.
Personnel not assigned Emergency Response Functions shall proceed g I to the following assembly areas (refer to Enclosure 1 & 2).
4.1 Protected Area g
I Six areas have been designated as assembly areas within the protected area. 4 g
4.1.1 4th floor Turbine Building B J
- a. Two areas in the Turbine Building have been designated assembly areas (see Enclosure 3).
Fu J
- b. The area directly adjacent to the Operations Support Center (Lunchroom) is desi.gnated for I on-shift IEir, net 4&GMFAT' .. .ud 7th"i .=' : .eOcr U=6n'h m r,woaw
- c. Office personnel and staff (clerical, TED avis o -.1 (fer's ra.edc 7 6enr 2 ),
J'
), 7+%
management, and QC) should assembly on the (ex:ivdin) cj dj east side of the turbine by the train bay. me mbus)
- d. Only FBT leaders, FAT leaders, and RMT leaders '
I should assemble in the OSC along with the OSC manager and his support personnel.
4.1.2 !!calth Physics Monitor Room (603' level) "
- a. All C&HP personnel not assigned specific emergency duties should assemble'in the Health Physics Monitor Room. __
4.1.3 I&C Lab (623' level)
- a. All I&C personnel not assigned specific emergency duties should assemble in the I&C j' Lab. "
E e
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. l
- 6 AD 1827.11.3 .
i
- E
' b. The Nuclear Construction Superintendent or his alternate should be contacted for informa-I :l tion receipt and dissemination or for performing accountability within the COB.
3 B
5.5.4 I
DBAB j
- a. If required, personnel should assemble in th'e \
lunchroom located on the second floor.
f C o h 9 0 ,Ts e m N M u f
. )SMOL 0'
- b. If the ocated on the first floor are activated, personnel located in these areas need not assemble in the lunchroom. l 3! U
+
- c. The DBAB Facilities Services Manager or the DBAB Office Services Supervisor should be g contacted for information receipt and g dissemination or for performing accountability within the DBAB.
I 5.5.5 Results of accountability checks outside the protected area will be' forwarded to the EDO.
(*
L NOTE: Number for personnel to be contacted can be found in Section X of Admin. Memo 37. -
[" 6. EVACUATION PROCEDURES u 6.1 Limited Evacuation Procedures I
J 6.1.1 Localized emergencies do NOT normally require a general evacuation, however, conditions such as explosion, fire, toxic gas release, or radioactive J material spills or leakage may require that personnel leave a specific building or area.
Instructions or directions will be either announced over the PA system (Gai-tronics) or disseminated in the assembly area.
6.2 A limited evacuation will require personnel involved with I the emergency to leave the area or building by the near-est safe exit and assemble as directed by the Shift Supervisor. -
6.3 In case of a limited evacuation, evacuees will NOT icave the protected area unless released by their supervisor and y shall maintain a safe distance away from the emergency scene and roadway to allow for safe passage and access by emergency equipment.
I a I
ede
4=
e 7 AD 1827.11.3 3 6.4 In th'e event of limited evacuation of site buildings or areas, evacuees will NOT leave the Owner Controlled Area
~
unless released by their supervisor and shall maintain a safe distance away from the emergency scene and roadway to allow for safe passage and access by emergency equipment.
7.
GENERAL EVACUATION PROCEDURE 7.1 If the announcement for a station evacuation is made, visitors and station personnel NOT assigt.ed Emergency I_ Response Functions will proceed out of buildings follow-ing the evacuation plan (Enclosure 1) to the PPF for evacuation from the station unless otherwise directed. In the case of non-radiation emergencies or exercises, security badges and TLD's shall be collected by security as personnel pass out the gate. Vnen personnel may have been exposed to radiation, they will keep assigned monitoring devices 3
until they have been checked by C&HP personnel at the DBAB Radiological Testing Laboratory, or other designated locations. Evacuated station personnel and visitors will 4, -
I-- be directed to leave by the main access road via their (*
private automobiles to their home or designated assembly point to await instructions from the EDO. The hard surface roads, State Houte 2, Duff Washa, and State Route I_. 19 may be used for evacuation away from the site proper, if a General Emergency is declared (see Enclosure A .
V. m j 7.2. g
' Station personnel who are required to remain in the station to perform emergency duties shall remain in their designated areas, for direction, subsequent evacuation or I to assume emergency duties. If directed to evacuate, station personnel will proceed to depart the building (s) following the nearest safe evacuation route unless other-wise notified (see Enclosure 1 and 2).
7.2.3 Nuclear Security Force
~' 3 7.2.3.a The Security shall be responsible
- for directing' personnel leaving the protected Area during the I m general evacuation. In an emergency, the security officers may bypass normal procedures '
I for the exit of employees and visitors, except that personnel should be monitored for con-tamination. PPF Security I -
Officers shall remain on post and maintain communications with the Shift Supervisor in O
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