Public Version of Revision 7 to Emergency Plan Administrative Procedure AD 1827.12, Protective Action Guidelines. Revision Index EnclML20052B109 |
Person / Time |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
03/24/1982 |
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From: |
TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20052B107 |
List: |
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References |
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AD-1827.12-01, AD-1827.12-1, NUDOCS 8204300035 |
Download: ML20052B109 (17) |
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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
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AD 1827.12 Davi:2-Ecsse Nuclear Power S:ation Unit No. 1 Ad=inistrative Precedure AD 12712 C Protect,;./e Action Guidelines
'E ih g i Record of Approval and Changes Prepared by C. Doyel/V. Green 2/23/76 Date 3 /11 / 7 4, Submittcd by E _ LJ _ bMtw _
Darc g.on llaad Recommended by _F) I SIG Chairman Date
,b . M ~ s J h //M M*
QA Approved -
V Na 'ger M alit / ATsurance Date Approved by _ [8 d S
~ Yatilin Superintendent Date i
1 Revision SRB QA Sta Supt.
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1 82543ooO35
. 1 1 AD 1827.12.6
- 1. PURPOSE To define a specific set of guidelines to be folicwed in determin-ing protective actions to be taken in the event of emergencies involving radio ctivity releases at the Davis-Besse Nuclear Power Station (DBNPS).
- 2. REFERENCES 2.1
- 10 CFR 20, Standards for Protection Against Radiation 2.2 10 CFR 100, Reactor Site Criteria c 2.3 USAEC TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites 2.4 AD 1808.00, Industrial Security Plan 2.5 Davis-Besse Nuclear Power Station Emergency Plan 2.6 AD 1827.10, Emergency Off-Site Dose Estimates 2.7 SAtH) 77-1725, Public Protection Strategies for Potential Nuclear Reactor Accidents - Shel tering Concepts with Existing Public and Private Structures 2.8 EPA Guidelines - September 1975, EPA-520/1-75-001 2.9 U.S. Food and Drug Administration, Federal Register, Vol.
43, No. 242, Dec. 15, 1978 2.10 Reg Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of l Evaluating Compliance with 10 CFR Part 50 Appendix I
- 3. DEFINITIONS 6 3.1 Decision Dose That value of projected thyroid dose above which evacua-tion is beneficial.
3.2 Evacuation Dose That dose that a potential evacuee would receive if he were openly exposed during the evacuation.
3.3 Evacuation Exposure Period The period during which the evacuee is exposed to tne radioactive plume.
i
3 AD 1827.12.7 The EDO shall then implement those actions for Station personnel and communicate the recommended off-site actions to the Ottawa County Sheriff's Department (or the State and County Emergency Operations Centers if they have been activated).
4.2 In order to simplify evacuation instructions for the public, evacuation " subareas" (see Figure 1) have been established by municipal and geographical boundaries.
When making evacuation decisions in an emergency situa-tion, the EDO shall consider the time available (based on plume travel speed) to evacuate the affected subarea (s),
in comparison to the estimated evacuation times as given .
in Table 1. The data sheets used in Section 6. assist in '
this process.
5 PROTECTIVE ACTION GUIDELINES 7 5.1 Recommended Protective Actions for the Plume Exposure Pathway (10 mile) Emergency Planning Zone to avoid whole body and thyroid dose from exposure to a gaseous plume:
Projected Dose (Rem) t the, Population Recommended Actions (a) Comments Whole body <1 Noplanngg) protective Previously actions. Issue an recommended Thyroid <5 advisory to seek protective shelter and await actions may further instructions. be recon-Monitor environmental sidered or radiation levels. terminated.
Whole body 1 to <S Seek shelter as a min- if con-imum. Consider evacu- straints ation. Evacuate unless exists,-
Thyroid 5 to <25 constraints make it special imp ra ctica l . Monitor considera-environmental radia- should be tion levels. Control given for access. evacuation of children and preg-nant women.
Whole body 5 and above Conduct mandatory Seeking evacuation. Monitor shelter environmental radia- would be an Thyroid 25 and above Lion levels and adjust alternative area for mandatory if evacua-evacuation based on tion were these levels. not immed:-
Control access. ately pos-sible.
1 i.
5 AD 1827.12.7 -
calculate the dose to the critical organ (s). Infants are the critical segment of the population Concentration in Milk or Water (0.5 (5 rem WB rem WB or bone: or bone: Total Intake 1.5 rem 15 rem via all Pasture thyroid) thyroid) Food & Water Grass l Preventive Emergency Pathways (Fresh Weight) 1.evel Level Preventive Emergency Preventive Emergency Nuclide* (pCi/1) (pCi/1) (pCi) (pCi) (pCi/kg) (pCi/kg) -
Cs-137 (Whole
!!ody) 0.34 3.4 7.0 70 3.5 35 Se-90 (bone) 0.007 0.08 0.2 2.0 0.7 7.0 Sr-89 (bone) 0.13 1.3 2.6 26 13 130 B. Recommended Protective Actions ,
Preventive Emergency
- 1. Removal of lactating Isolate food and water dairy cows from con- from its introduction taminated pasture and into commerce after substitution of uncon- considering:
taminated stored feed.
- 2. Substitute source of a. availability of uncontaminated water. other possible
- 3. Withhold contaminated actions; milk from market to b. importance of par-allow radioactive decay. ticular food in
- 4. Divert fluid milk to nutrition; production of dry whole c. time and effort to
! milk, butter, etc. take action;
- d. availability of other foods.
l7 5.3 Representative shielding factors from airborne radio-nuclides:
~~ '
Stryp_ Lure or 1.ocation Shielding Factor *) Representative Ranee Outside 1.0 --
Vehicles 1.0 --
Wood-frame house (b) 0.9 --
[ (no basement) i
7 AD 1827.12.7 Representative ) Representative Structure or Location Shielding Letor Range One and two-story wood- 0.4(b) 0.2-0.5 frame house (no basement)
One and two-story block 0.2( ) 0.04-0.40 and brick house (no base-ment)
House basement, one or two 0.1(D) 0.03-0.15 walls fully exposed:
One story, less than 2 0.05(b) 0.03-0.7 f t of basement, walls exposed g)
Two stories, less than 2 0.03 0.02-0.05 ft of basement, walls exposed Three- or four-story structures, 5000 to 10,000 ft2 per floor:
First and second floors: 0.05(b) 0.01-0.08 '
ilasement 0.01 0) 0.001-0.07 Miltistory structures,
>10,000 ft2 per floor:
g)
Upper floors 0.001-0.02 Basement 0.01 0.005 (b) 0.001-0.015 (a) The ratio of dose received inside the structure to the dose that would be received outside the structure.
(b) Away from doors and windows.
7 5.5 Distribution of Potassium Iodide Tablets
- 1. The EDO will direct Station personnel to take a KI tabletif,(a}5the known iodine concentration will exceed 1 x 10 pCi/cc for greater than one hour, or (b) the total known dose to an adult thyroid will exceed 10 rems.
- 2. Base the distribution of KI on actual thyroid doses, not projected closes. KT is 907. ef fective i f admin-istered within one hour af ter the uptake, and 50%
ef fective if administered within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> a f ter uptake.
- 3. Call Radiation Management Corporation if KI is administered for further directions regarding usage.
9
.- a, ,3,e..,.e I:G21?LIS C.7 ACTIONS
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.:: -rw:
._un__.N.v;n Ingestion of food Decontam: nation, and water con- condemnation, or taminated from destruction of food; LONG TIRM the soil either deep plowing, con-
?HASE3 by resuspension de= nation, o r al-or uptake teena:e use of land throuth roots Whole body expo- Relocation, access sure from deposi- control, decontam-(over 30 days)* tion =aterial or ination, fixing of -
inhalation of re- contamination, deep suspended plowing material 3
Long Term Phase - Recovery period.
4 " Typical" Post-accident time periods. .
6.4 Small Children and ?:egnant '* omen Any time the projected whole body does is expected to exnid 500 mrem or the projecte1 thyroid <inse is expce.e:I to exceed 1.5 cem, advise the Gt:awa County Sheriff's Department to conduct an evacuation in the area of exposure of families in -hich there are pregnant wcmen or small l children.
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- 11. Use informa-ica f:cm I ems 1 and 10 to ge: Es ima ed svacuation :,me . . rom .ao,ue ... nours
- 12. Exposure Time:
Item 11 - I:em 9 = hours 50ts:.
1: Item 9 is negative, . deep in mind
-s..a minus a nega .ve
. c num'er gives a positive resul . If Item 9 is larger than Item 11, enter zero hours.
- 13. Evacua-ion Exposure Period (IE?):
- Take the smaller of Exposure Time (I:em 12) or
- Release Duration (1:em 4) hours it. Evacuation Dose = IEP hours x Dose Rate = (I em 13) x (I:em 2) =
REM 1000 1000
- 13. Sliettering Cose =
Projected Cose x S :ucture Shielding Factor (f cm 5.3) =
REM
. NOTE : Since the housing in the 10 mile Emergency ?;anning 2cne is basiesity wood homes, a structure shielding fac or of
0.9 shoul
normally be used.
.v sing ?.he above information and .,o.,cwing taste,
.. o.. a.
determine the protective ac-ions o be recom= ended:
=
3 TY.=.'.i
- a. .arojected snose (Atem 0; i.ess than a. .ev4 .-- .
nu..v3 1 rem
- h. Shi itering Cose (Item 16) is grea'.e: e. SRELTER than I com but less than 5 rem
- c. Sheltering cse grea e: than 5 c. I'!ACCATE rem, and Evacuation Cose (I'.cm
- 15) less -han Shel ering Ccse
- 4. Shet'.ering Ocse greater than 5 rem d. S HE *_!ER and dvacuation-Cose tec.nce
'han v: w n.a . La :s he i'.e : 'we
13 AD 1827.12.6 TA3LE 1 Evacuation Time Estimates Land S u,1,- A rca s Populati<in* Normal Adverse Severe **
1 2,775 2 hr. 55 min.
823 4 hr. 10 min.
823 15-20 hr.
2 .2,675 3 hr. 5 min.
861 4 hr. 50 min.
861 30-40 hr.
3 10,717 3 hr. 35 min.
3,242 6 hr. 30 min.
3,242 35-45 hr.
4 608 2 hr. 50 min.
608 4 hr. 15 min.
608 10-15 hr.
5 4,940 3 hr. 30 min.
4,940 40-45 hr.
6 4,940 3 hr. 30 min.
1,506 5 hr. 10 min.
1,506 30-40 hr.
7 1,865 4 hr.
1,795 6 hr. 25 min.
1,795 50-60 hr.
TOTAL EPZ 28,484 5 hr. 15 min.
13,775 10 hr. 55 min.
13,775 75-100 hr.
Lake Sub-Areas Boaters Normal Adverse Severe 3 thru 13 Va ri es 4 he. N/A N/A Special Case ,
Pooulation No rma l Adverse Severe Port Clinton 10,128 4 hr. 45 min.
/,229 6 hr.
7.229 24-30 hr.
2L2cpulation varies due to location and transient resident variations cue to, season and unf avorable weather conditions.
- Time ranges are provided due to the uncertain nature of severe weathe:
conditions (e.g., during a severe snow fall er blizzard, the time it takes to evacuate can vary depending on the direction and speed of the wind).
15 AD 1827.12.7 DATA SHEET 2 (Continued) g THEN 7 b. Projected Thyroid Dose greater than b. EVACUATE 5 rem but less than 25 rem CHILDREN AND WOMEN OF CHILD-BEARING AGE IF POSSIBLE,
, SHELTER
- c. Projected Thyroid Dose greater than c. EVACUATE IF 25 rem, but less than the POSSIBLE OR -
- Decision Dose (Item 7) OTHERWISE SHELTER *
- d. Projected Thyroid Dose greater than d. Perform action Decision Dose, then as follows:
- 1. If EEP less than Release 1. EVACUATE Duration j
- 2. If EEP equal to Release 2. SHELTER
- SHELTER is to be with VENTILATION CONTROLLED.
l l
l END i
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