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| ATTACHMENT 2 PUBLIC COPY 8402090267 840130 PDR ADOCK 05000382 PDR F
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| ~~~--- - - - - - - - . - - _ _ _ _ _ _ _ _ _ _ _ _
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| WATERFORD 3 SE5 m !m PLANT OPERATING MANUAL
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| ).lM
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| ,= LCU131ANA m P O W E R & t.l G H T FR?Mefss!
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| POM VOLi]ME 18 EP-1-001 POM SECTION 2 REVISION 3 Emergency Plan Implementing Instruction Recognition and Classification of Emergency Condition LP&L W-3 RECORDS' UNCONTROUcED 00 NOT USE IN Ar" "AFETY-RELATED TEST COPY MAINTENANCh vH OPERATIONAL ACTIVIT PORC Meeting No. 83-52A Raviewed N/kd%
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| PORC airman Approved: u ) I!kh Plant Manager-Nuclear Approval Date Fuel Load Effective Date UNT-1-003 Revision 6 _ _ _ _
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| gggge%g g,g n gp i g
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| l
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| )
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| ~
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| WATERFORD 3 SES ,
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| PLART OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Pr:cedure No. ~ l-00) Title Rec.osulNo v wl C. lass;kk o(
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| Effective Date b M (if different from approval date)
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| ~
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| e ey e.,oc7 tw eista L n_ or c b M A. Change No. ~'Id B. Revision No. #3 C. Deletion d/d REASON FOR CHANCE. REYISIDE. OR DELETTON , , ,.
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| '75 Re.ut S E k-Nieltud 9./ lQsd rY h c 064DcnN Cdl8dlts~~
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| d& . Mse cielehed M 0. 3 '
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| wroninen sTmr196Tr Originator N W Date /2 b// 3 Tcchnical Review 2 3 OM -
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| Date >L/2> I2w ,
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| SAFETT ETALUATION Does this change, revisica, or deletion: TE3 20
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| : 1. Change the facility as deseribed in th'e FSAE7 #
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| : 2. Change the procedures as described in the FSAR7- #
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| : 3. Conduet tests / experiments rat described in the FSAR7 #
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| 4 Create a condition or conduct an operation which ex- #
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| coeda, or could result in exceeding, the limits in Technical Specifications?
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| If the answer to any of the above is yes, completo and at-tach a 10 CFR 50.59 Safety Eva tion check 1 s .
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| Satety Evaluation
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| * M 7D Date / d' S U Group /Dep't. Head Review N Med Date /U-rN3 Temporary Approval
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| * Date (NO3)
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| Temporary Approvale Date QC Review U dc~A A f ~ Date '-? ~v PORC Reviewc M M - - Date /- b V f Meeting No.
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| Plant Manager-Nuclear Approval Date -
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| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
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| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 3G
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| Emergency Plan Implementing Instruction EP-1-001 Recognition and Classification of Revision 3 Emergency Conditions TABLE OF CONTENTS 1.0 PURPOSE
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| ==2.0 REFERENCES==
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| 3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS l 7.1 Classification System (1 page) !
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| 7.1 TAB A Uncontrolled Release of Radioactivity (4 pages) 7.1 TAB B Loss of RCS Inventory (2 pages) 7.1 TAB C DNB/ Degraded Core Sequence (1 page)
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| ~
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| 7.1 TAB D Loss of Safety' Functions (3 pages) 7.1 TAB E Hazards to Station Operation (1 page) 7.1 TAB F Natural Phenomena (1 page) i 7.1 TAB G Security Compromise (1 page) 7.1 TAB H Miscellaneous (1 page) 7.2 Emergency Coordinator's Close-Out Checklist ( 1 pagd LIST OF EFFECTIVE PAGES Title Revision 3 1-20 Revision 3 21 Revision 2 1
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| Emergency Plan Implementing Instruction EP-1-001 Recognition and Classification of Revision 3 Emergency Conditions 1.0 PURPOSE 1.1 This procedure describes the immediate actions to be taken to recognize and classify the four emergency classifications: Unusual, Event, Alert, Site Area Emergency, and General Emergency.
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| : 1. 2 ' This procedure provides an Emergency Coordinator's Close-Out Checklist l (Attachment 7.2) to verify that all criteria exist to te:minate the emergency condition.
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| 4
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| ==2.0 REFERENCES==
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| 2.1 Waterford 3 SES Emergency Plan ,
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| 2.2 Title 10, Code of Federal Regulations Part 50, Appendix E 2.3 NUREG-0654/ FEMA - REP-1, Criteria for Preparation and Evaluation of Radiological Emergency. Response Plans and Preparedness in Support of Nuclear Power Plants 2.4 Waterford 3 SES Final Safety Analysis Report 2.5 EP-1-010, Unusual Event 2.6 EP-1-020, Alert 2.7 EP-1-030, Site Area Emergency 2.8 EP-1-040, General Emergency 2.9 EP-2-052, Protective Actica Guidelines 2.10 OP-903-024, Reactor Coolant System Water Inventory Balance 2.11 EP-2-150, Emergency Plan Implementing Records 2
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| i
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| Emergency Plan Implementing Instruction EP-1-001 Recognition and Classification of Revision 3 Emergency Conditions 3.0 RESPONSIBILITIES 3.1 The Shift Supervisor / Emergency Coordinator (SS/EC) shall be responsible for implementation of this procedure and declaration of the appropriate emergency classification whenever, in his judgment, the station status warrants such a declaration.
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| 3.2 The Shift Supervisor shall assume the responsibility and authority l of the Emergency Coordinator (EC) until such time that he is properly relieved of this duty by the Duty Plant Manager.
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| 3.3 If, for whatever reason, the Shift Supervisor cannot immediately l assume the duty of Emergency Coordinator, the Control Room Supervisor (CRS) shall assume the duty of Emergency Coordinator until properly relieved as described in step 3.2.
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| 4.0 INITIATING CONDITIONS 4.1 An off-normal event has occurred or is in pr' ogress.
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| 4.2 An action step in a plant operating or emergency operating procedure refers to this instruction for classification of the indicated plant conditions. >
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| CAUTION This instruction does not replace any plant operating procedure. Ensure that any inmediate actions (e.g.", use of Emergency Procedures) are taken for the proper operation of the plant.
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| During an emergency condition, continue to use the appropriate plant procedures in parallel with this instruction.
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| 3
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| Emergency Plan' Implementing Instruction EP-1-001 ,
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| Recognition and Classifi:ation of . Revision 3
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| : Emergency Conditions 5.0 PROCEDURE
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| '5.1 Verify the off-normal event to ensure chat the event la real.
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| 5.2 . Match the off-normal event with one of the following eight emergency categories:
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| 5.2.1 Uncontrolled Release of Radioactivity TAB A 5.2.2 - Loss of RCS Inventory TAB B 5.2.3 DNB/ Degraded Core Sequence TAB C 5.2.4 Loss of Safety Functions TAB D 5.2.5 Hazards to Station Operations TAB E 5.2.6 Natural Phenomena TAB F 5.2.7 Security Compromise TAB G 5.2.8 Miscellaneous TAB H NOTE The effects of combinations of initiating events that individually constitute a lower classification condition should be considered as a possibly higher emergency classification.
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| 4
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| r ,
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| Emergency Plan Implementing Instruction EP-1-001 Recognition and Classification of Revision 3
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| ; Emergency Conditions NOTE If the indicated off-normal condition does not appear to match any of the listed pre-determined emergencies, refer to TAB H, Miscellaneous. The Emergency Coordinator must use his judgement in determining if the indicated conditions meet the intent of the emergency classification scheme.
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| 5.3 Refer to Attachment-7.1, Classification System, and under the category TAB selected in step 5.2 above, match the off-normal condition with the appropriate Emergency Action Level (EAL) to determine the
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| , emergency classification.
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| 5.4 . Declare the highest emergency classification for which an EAL has been exceeded.
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| ~ 5.5 ' Perform- the emergency actions as outlined in the appropriate Emergency Plan Implementing' Instruction, one of which is provided for each classification, as follows:
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| '5.5.1 Unusual Event - EP-1-010 5.5.2 Alert - EP-1-020 5.5.3 Site Area Emergency - EP-1-030 5.5.4' General Emergency - EP-1-040 5.6 Assessment actions shall be continued, and if necessary, the emergency classification escalated (or dovngraded) as more definitive information becomes available or if the plant conditions change significantly.
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| .5.7 When the Emergency Coordinator has made the decision to terminate the emergency condition, Attachment 7.2, Emergency Coordinator's Close-Out
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| . Checklist, shall be completed to verify that all necessary criteria exist tc terminate the emergency condition.
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| 5
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| Ewergency-Plan Implementing Instruction EP-1-001 Recognition and Classification of ,
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| Revision 3 Emergency Conditions 6.0 FINAL CONDITIONS-All criteria for close-out of this instruction have been met in accordance with Attachment 7.2, and the initiating conditions which activated-this instruction have been declassified to non-emergency status.
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| 7.0 ATTACHMENTS 7.1 Classification System
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| ~
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| 7.1- TAB A Uncontrolled Release of Radioactivity 7.1 TAB B. Loss of RCS Inventory -
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| 7.1 TAB C DNB/ Degraded Core Sequence
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| '7,1 TAB D- Loss of Safety Functions 7.1 TAB E -Hazards to_ Station Operation 7.1 TAB F Natural Phenomena 7.1 TAB'G Security Compromise
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| -7.1 TAB H Miscellaneous 7.2 Emergency Coordinator's Close-Out Checklist 6
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| ~ -
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| UNCONTROLLED RELEASE OF p.DIDACTIVITY tmUSUAL EVENT ALERT SITE AREA EMERCENCY CENERAL EMERCENCT NOTE NOTE NOTE off-Site Protective Action may be Off-Site Protective Action may be Of f-Site Protective Actions ARE required - See EF-2-052 TAB "A" required - see EF-2-052. TAB "A". RBQUIRED - ees EF-2-052 TAB '5*.
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| A. Radiological ef fluent Technical A. Radiological effluente greater Any 3 of the following conditiones Any g of the following conditionet Specifientinn exceeded as indicated then 10 times Technical Specifica- .
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| by the following conditionet tiene Limits. As indicated by the 1. F1snt Stack Noble Ces Monitor, 1. Offolte Dose Assessment (CEPADAS following conditioner PRM-IRI-0110 indicates noble / Manual) projects whole body dose release rate greater than 4.085 rate at the GAB greater than or EITHER EITNER uC1/see for 0.5 hr: o_r greater equal to 1.0 ree/h,r .
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| than 4.056 uC1/see for 2 minutes, in valid IttCH alare in valid MICM alarm on CF-52.
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| OR OR 2. Offolte Dose Assessment 2. Offaite Dose Asses m nt (CEPADAS (CEFADAS/ Manual) projects whole / Manual) projects thyroid dose rate By samplint By sampling body dose rates at the EAB greater at the EA8 greater than or equal to than 50 stem /hr for 0.5 hr or 5.0 res/hr.
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| AND AND greater than 500 ares /hr for7 l minutes.
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| l Retenne path N_070 ISOLATED Release path NOT ISOLATED
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| * 3. Offeite Dose Assessment 3. Radiological monitae fng team l
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| AND (CEFADAS/ Manual) projects thyroid measures whole body does rate at the AND dese rates at the EAR greater than EAR greater than or e p al to 1.0 l 250 ares /hr for 0.5 hr or greater ree/hr.
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| In the opinion of the SS/EC that in the spinion of the SS/EC that than 2500 ares /hr for 2 minutes.
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| I exceeding of the r~nservative exceeding conservative estimate of ttie iechnical Specification provided 4. Radiological monitoring team 4. Radiological monitoring team utimate of the Technical sesoures whole body dose rates at measures thyroid done rate Specific =t bn provided fr the in tt:e parentheses "()" warrant the p2renthesen "()'' warrant t!.e declaration without calculation. the EAR greater than 50 mres/hr for (equivalent 1-131 concentrations) l 0.5 hr or greater than 500 aree/hr at the EAS greater than or equal to j dretaratios without calculation. 5.0 res/hr.
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| for ; minutes.
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| l.) Airborne effluent Monitore. l.) Airborne effluent Monitore
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| ' 5. Radiological monitoring team Crneous Weste Manegement Monitor, Caseous weste Management Monitor mesoures thyroid dose rates PRM-IRE-0648: PRM-IRE-06483 (equivalent 1-131 concentratione) at the EAR greater than 250 arem/hr (50 SCFM, 2.0 act/ml) (50 SCFM. 20.0 uCi/ml) for 0.5 bra or greater than 2500 (40 SCFM. 2.5 uC1/ml) (40 SCFM, 25.0 act/al) aree/hr for T uinutes.
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| (30 SCFM, 3.3 uCt/ml) (30 SCFM, 33.0 uC1/st)
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| (20 SCFH. 5.0 uC1/ml) (20 SCFM, 50.0 uC1/mt)
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| (10 SCFH, 20.0 uC1/ml) (10 SCFM. 200.0 uC1/ml)
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| OR OR Candenser Vacuum rump Noble Ces Condenser Vacuum Pump Noble Cas Monitor. FRM-IRE-002 Monitor. FRM-IRE-002 (5.0 E4 uct/sec.) (5.0 E5 uct/al) 7 Attachment 7.1 TAB A (I of 4)
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| EF-t-001 Revinfon 3
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| * e
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| ' UNCtNITRol, LED RELEASE OF RADIDACTITITY ALERT CtHERAL EMERCENCY
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| _ ITNUSUAl. EVDIT _ _ SITE AREA EMERGFMCY _
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| j OR OR Fuel Handling Bldg. Exhaust A Fuel Handling Rjdg. Exhaust A Honitor. APH-IRFA IDFA Honttor. ARM-IRE-Sl07A (23.625 St:FH. 1.7 F.-3 uCl/ce) (28.625 SCFM. 3.7 E-2 uCl/ml)
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| OR (ft Fuel U n.Illur Biog. Exhaust f: Fuel Handling Sidg. Exhaust R Honttor. ARM-IRE-5107R. Monitor. ARM-IRE-Sl075 i (28.625 .'.Cril. 3.7 E-3 oCl/ce) (28,625 SCFM, 3.7 E-2 utt/ml) )
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| l OR OR l l
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| Fuel Mandling Rida. Wide Range. Fuel Handling Bldg. Wide Range.
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| ARM-IRE-1937 ARM-IRE-3032 OR OR Finnt Stock Noble Cag Montent Flant Stack Roble cas Honttor. --
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| F W IRE-Ollo FRM-IRE-Ollo (Channel 4 reading 5.0 E4 uCl/ml) (Channel 4 reading 5.0 E5 uCl/ml).
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| , 2.) 1.Iquid effluent mo.eltors. 2.) 1lquid effluent monitors.
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| l l Liquid W gte Hanagement Monitor. Liquid Waste Hanagement Monitor.
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| FRM-lRE-0647 (l.O E-l uCl/ml). FRM-IRE-0647 (1.0 uCl/ml).
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| OR OR Boron H.inngement Condensate Monitor Boron Management Condensate Monitor FRM-IRE-l:627 (l.0 E-l uCl/el). FRM-IRE-0627 (1.0 oct/al).
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| l OR OR Circulating Water Discharge Monitor Circulating Wter Dischstge Honitor FRM-IRE-6716 (2.0 E-5 uCl/ml). F W IRE-1900 (2.0 E-4 uCl/ml).
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| 1 OR OR l nry Cooling Tower Sump fl Monttur Dry Cooling Tever Snap fl Honttnr Fitt!-IRE-6715 (2.0 E-5 uCl/ml). FRM-IRE-6715 (2.0 E-4 uct/ml).
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| OR OR pry Conting Tmeer Sump #2 Honitor Fry Cooling Tower Sump f2 Hanitor FRM-IRE-6776 (2.0 E-5 uCl/el). FRM-lRE-6776 (2.0 E-4 utt/ml).
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| l
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| _OR .O. R.
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| g Indust rInt s agte Sump Monitor Industrial waste Sump Honttor FRM-IRE-677R (?.0 E-4 uCl/ml). FRM-IRE-6778 (2.0 E-4 uCl/ml).
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| 9 O
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| l l O 8 AitaCment 7.1 TAR A (2 of 4) l EF-t-005 Rev i n i nr. 3 I -
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| f D
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| s
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| . . e j s . INet:tutTRoi.l.ED ret. EASE OF RABl0ACTIVITT M
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| ~
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| _ tmitSUAl. EVlWT .
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| . . . ~ . . . - - . . -
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| ALERT SITE AREA EMERCENCY _ ' CEildtA1. ENERCEBCY e
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| , B. Radiation levels on atrborne contamination which Indicate a 2 j eevera degradation in the control e -
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| of radioactive matertala an Indicated by:
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| 1.) Any Area Radiation Monitor -
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| (AAA AAS) on Proc *as Airborne Monitor (FFF. Fil PCC. FFS. FIS.
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| FCS) " trend" indication on RM-Il console shows a valid unenplained increase by a factor of 1000.
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| ~2.) Any radtalogical survey results Indiesting an unexplained increase by a f acter of 1000 in direct red-lation or strhorne contaalpation -
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| il levels within thg facility.
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| 3.) SS/EC opinion that.a fuel 6.) 55/BC opinion that a major fuel damage accident with release of damage accident with release of
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| . radioactivity to Containment or radioactietty to containment or Feel Fuel Mandling Butiding has occurred Needling Dutiding has occurred haned l based on reported fuel handling on reported fuel handling incident incident vertiled by alarma on any verified by greater than 10 times i
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| of the following radiation ssentters: N!CE alare set point indlestion on .
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| l ae.f of the following radiation l monitores Containment Mt Range Area Monitors. Contal m et NI Range Aten Monitor.
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| ARM-IRE-5400A5(BS): or ARM '.dE-5400A5(BS) og FNs Enheest A Monitor. FIIS Enhamet A Monitor.
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| ARM-Ire-SteFA or ARM-IRE-5107A3 or Fil3 Enhavet 5 Monitor. FNs Enhavet 5 Montent.
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| ARM-IRE-5107B3 og ARM-IRE-5IO75: or_
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| (
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| FWB Area Radiation Manitor. FHS Area Radiation Monitor.
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| * ARM-IRE-0300.25: g ARM-IRE-0300.253 or '
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| l Fil8 Area Radiation Monitor. FWS Area Radiation Mnnitor.
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| ARM-IRE-0300.453 orr A156-IRE-0300.453 og 7918 Ekhemet Monitor. Wide Range. ARM-IRE-3032 or FNs Area Radiation Manitor. Filt Area Radiation Monitor.
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| ARM-IRE-0300.153 og AfM-IRE-0300.I53 g g FWB Area Radiation Monitor. FWS Area Radiation Monitor.
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| ARM-IRE-0300.3Sg g Algt-IRE-0300.3Sg g Containmene eartie iste Airborne containmene rartic late Airborne $
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| O Monitor. ARM-IRE-010053 g Monitor. AltM-IRE-0100Sg og O
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| O 9 Attachment F.I TAB A (3 of 4)
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| EF-1-001 Revialen 3
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| _-__._A__ -
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| UNCI 1NTRot.l.FD RFLEASE OF RADIOACTIVITY l
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| AI.ERT SITE ARFA EMERt:ENCY CENERAL EMERGENCY UNtISUAl. EVENT Containment Area Ra.llation Monitor. Containment Area Radiatlan Monitor.
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| ARM-IRE-3024SI o r_ ARM-IRE-1024SI or Containment Area Ra.llation Manitor. Containment Area Radiation Monitor.
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| ARM-IRE-30255; or ARM-IRE-3025SI or i Containment Area Radiatinn Monitor. Containment Area Radiation Honitor.
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| ARM-IRE-3026SI o_r ARM-IRE-3026SI _o_r y
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| Containment Area Radiation Monitor. Containment Area Radiation Monitor.
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| ARM-IRE-30275. ARM-IRE-30273 7.) Uncontrolled decrease in spent ,
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| fuel pool water level to beim level of triadiated fuel as determined by visual observation of pool levell or L2 on CP-2. FUEL. POct. l.EVFl. ID-alare. concurrent with full scale indlestion on any two of the-following radiation monitorer FHB Area Radiation Monitor.
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| ARM-IRE-0300.25 Fi!8 Area Radiation Honitor.
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| ARM-IRE-0300.45 Fits Area Radiatim. .sonttor.
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| A RM-IRE-0300. l S FHB Area Radistfon Montent.
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| ARM-IRE-0300.35 l.
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| : 8. Steam line fault concurrent.witte 4.) Steam Line fault concurrent '
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| with significant (greater than 10 SS/EC determination that grass ACS gpm) primary ta secondary leakage activity relecse from secondary as indicated by boundary as determined by:
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| Uncontrolled decreane in Steam Cen- Uncontrolled decrease in Steam Cen-erator pressure (s) to MSIS am indl- erator pressure (s) to MSIS as cated on SHA. SHR. SHt'. SHD (on indicated on SHA. SHR. SHC, SHD on CP-8) (HS-IFT-030l AS. (0301RS). CP-8 [!15-trT-030l AS. (03n185).
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| (0301AS). (0303BS)]. (0303AS) (0303RD)l.
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| AND AND Hain Steam Line Honitor. Natu Steam Line Honitor PRM-IRE-5500A. (R) exceede " Alert" PRM-IRE-5500A, (R) execeda "AP*rt" alarm set point, on CP-57. alarm set point, on CP-52.
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| I "E Equilibrium Charging Flow minus letdown finw to greater than 44 gra GD p
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| t?th RCSDE I-8 38 greater than 1.0 uCt/gm (as determined by the mnnt recent fontople nnalysin renulta). $$
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| 13 At t richment 7.1 TAR A (4 of 4)
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| FP- t -fM)I Revision 3 .
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| e e
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| .( r 3
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| . g e + . o- ,
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| ~
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| IDSS tlF RCS IIsWWITORY Al>Jti SITE AREA DIEtt.FJeCY CEIIERAL WIESCElecf
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| --IfNftSilAI. EVENT - ,
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| selrtR s00TE le9TE off-Site Protective Action may he off-Site Frotective Action may be Off-Site Protective Action ARE ~
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| required - see FP-2-n52 TAB *B". required - see Ff-2-0$2 FAB "B". REqWIRED - see EP-2-052 TAR *S".
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| Any one of the fallne=Ing conditions: Any g .of.th* following, conditions:
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| Any one of the following conditions: ,
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| u 1.) F.areceting ettber prjesty to RCS 1.eakage greater than 44 gym as. l.) RCS to Coatainment leakage' l.) Amy lose of coolant sectdent and recondary leak este technical indicated by: greater thee evallable charging Pump subsequent fatteres of Fa.ertency tracifications or primary system 'espacity (LOCA) as determined by: Core Cooling Systems such that. In Isak rate technical npecifications I.) Equillbtfue charginit flow minug ..
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| J the opisten of the $5/EC. a Core as indicated by RCS leanage greater total letdoins flow greater than 44 ifacentrolled decrease in Pressuriser Melt Sequence is in progress, or than any (eg ni the following gym. pressure and subcooling mergin with teminent, and the ultimate fatture 7tchnical Sperification Ilotto: SIAS sad NPSI flow Indicated on of Contalement is likely.
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| 2.) Rapid groes fattare of one CP-8.
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| a.) Zero pressure boundary leakage. stesa generator tube with tons of 2.) Any lose of coolant accident and' offette power as indicated by: g subsequent fattures of Containment b.) I grm untifentlfled leakage. Ilest Demoval Systems sucIs that, in
| |
| * Equilibrium charging flev minus lacreasing e ntainment radiation /. the opintos of the SS/EC, a rare c.) I gpm arS pressuie isolation total letdown flow greater than pressure / temperature / sump levels. Melt Sega. ace is in progress. or value leakage. Se gym imminent, and the ultimate fatture of Contatament is likely.
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| Main Steam I.Ine Monitor, 3
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| d.) I gem total primary to secondary ,
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| les6 age or 1/n gallons per day PRM-IRE-5500A (R) exceeds " Alert" 18o abnormal difference between Steam through any one Steam cenerator. alarm aet enint, oa CP-52 Ceners' tor pressures and levels.
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| e.) 10 ese telent if f eel leakage. g
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| . i "4 kV Bus SA Skr Trip / Trouble" alare.
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| Fi on CP-l l
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| l Alen l
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| l "4 kV Bus SR Rkr Trip / Trouble" alera.
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| l F3 on CF-l.
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| 3.) Steam line break with significant (greater than 10 ppm) primary to necondary leak rate as l Indicated by:
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| ! Equilibrium charging flow minus total letdown flow greater than 10 gym greater than known tntal ht?.
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| leskage.
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| S.
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| Ifncontrolled decrease in S/t:
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| . prennure(s) to MSIS am nienwn on SMA. SMS, Stp. SMn (CP-R
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| * IMS-trT-DM11ASl.(HWilRS). (GinlAS). #
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| O (ownRS)
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| EP-t-001 te.w l .n l on I 11 Attachment 7.1 Tab R (I of 2)
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| . . i
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| ? .
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| 8I U -
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| Ir . H9. g INWtNTIIRT AI.6 8:7 , Sl1F. AREA PMe ts;tMr.Y CFNDRAl. Fift.RCH8E3 l'fitf%81Al. t VlWF , , , _
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| 2.) PCS to ner..swaary laahage greater than avallel.le rhargint Peer rapar-Ity (SCTR) as eletermined hyr Itacentrolled decrease in Psensuriser pressiere and me.hroellet margin with S E AS and IIPSI f law Indicated on CP-S)
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| E Main Steam f.ine Monetter.
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| PhlRE-550nA. (3) exceeJs Ill-NB storm set point on CP-52.
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| 3.) RCS to nernadary leakage Rreater than SS spo concurrent with loss of offsite power as indicated by:
| |
| Equilibrium clearning flow minus total letdown flow greater than 88 SPm n
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| l
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| * Mein Steam Line Monitor.
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| P h lRE-5500A. (8) exceeds M1 alarm j set point. on CP-52.
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| O l
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| * "4 5T Bus SA Rkr Trip / Trouble" alarms Pl on CP-l.
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| .AltD, "4 kV h e %R Rhr Trip /Troulile" alarm.
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| P3 on CP-l.
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| l l
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| l
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| ?
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| . O l
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| * l 0 F.r- I -t M i t b, I s le. , y 12 At t actment 7.9 Tab R (2 of 2) l l
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| l
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| l . pHR/tet s
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| * 199 p IMRK SrapitNCE AlJ k t SITE ARIA pHtylNeV CI'NF.RAL DNDRf;tWCT It0H!illAl. t VIN 1 leOTE l .) Inc e gc r v t e.e e f:.=.11ng Synt ee t{iE " ^~ ~
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| ( ttu) init 1.st e.1 amt ellwa h.or ge in weret ag Imlinited hv: (.ff-Site Frntertive Artfon may he Of f-Site Protect ive Act ion art: l requircJ - see Ir-2 n'e2 TAR "C". RFa}UIRED - see EF-2-052 TART **.
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| V;lfJ SlA" as i nat lon and * .8 sa , __
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| 1 frjiction fl..w In.lle st ed .-
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| Cll1. ( H /pl. (0111). (01411. Any one of the Inllowing conditlanar I.) SS/EC cpintene that a "JcBraded I.) Loss of core beat sink sects tint, core with possible laas of coolant in the opinion of the SS/tr. a rare i 2.) Rapid ne. omfary depreasurlaat ton 1.) Severe less of feeel cladding geometry" cor.dttInn entsts based en Melt Sequence is in progress, or of the nenimlary side as indicated verified by Inntopic analysin Indi- consideration of the following: Imminent, and the settle.ste f ailure hys eating an increase in f eitic4 fuel of Containment is likely based en I greater than 1.0 pescent in .HI (a) Adequacy of enre conlleg, determination of either nf the Uncont glied Jerrea=c in Steam minuten or tctul f ailed inel recater followfngs '
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| i Cencr atar pr. **ure(s) t o MSIS as than 5.0 percent. (b) Reactor conlant activity sample (a) Transtent inttlated by 1.*ms of 1 indtrated an SffA. Sita. SPR: SHD on results.
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| 2.) RCS chem!ntry sample results all normal feedwater capabilit y i CP-R [HS-IFT-tfilulAS). (030lRS).
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| ! C DIAS) . (p lu lMS) l . Initcate done equivalent I 5 18 (c) Containment radioactivity followed by failure of all I greater than 300 uCl/mi a d SS/ft: levels. *mergency feedwater carahlf f t y for .
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| 1.) Ahnormal ronlant temperature opinion that nample results are not exteneled period r.nd/or pressure or ahnnemal fuel due to todine eptking phenomenon.
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| I temperatures ..ntal.le of technical M spiciffration linten an indicated 3. Reactor Contant rump shaft (b) loss of all of fette power and by: selrure leading to fuel failure ma determined by: .f at tare of both Earrgency Diesel I
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| e ) Rear t ar t i l p wi t h RFS Channe ls Cenerators and failure of steam Trip 31NRR "in" ( A- 8 2) on CF-2. Dtl8R Reactor Trip on Low Finw and I NBR driven Emergency Feedwater rump for e leng than 1.2n an inditated; or, t.ow entended period,
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| : b. ) Rear tor erIp with Pr5 Channels AN_ID 1 Tr ly local FWR Dengi t y "lll" ( A-I t) prak linear heat rat e greater than increasing selected isotope activity 21.0 kW/ft. as Indicated on CF-7 by on RPM-IRE-0202, tetdnun Proccan 8 margin meter le><n t han or equal to Radiation ftmitor on CF-4.
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| O Int DN!'R or l PD. *
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| .h""
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| l c.) RCS pressner prcater than 2750 pala. DIIBI less than 1.20 as Indicated by Cere Protection Calculators.
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| # 4.} Feiel l>amage as Indicated by:
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| AND IITDetWN As.flVITY lli alarm. DI nn 1 CP-4. and veelfled I.y factopic ( Al). ( A3) . ( AS) . ( A7) . Ulf Cr-2 rnzlysts in.f tcat ing an increase in RF.ACTDR CLC PUHF TRIP /TRonRif fcile1 fuel Recater than 0.1 percert alarm (s).
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| I la 30 m e nnten, or failed inct greater than 1.02. AND 1 Computer admin. FT. 1.D. til 3202 *
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| (13402). (t woz). (198o2). RCr tilR OVF.RCURR/ovF. RID TRlr i
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| 9 D
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| EP-t-tMt R..vigion i II A.tachment 7.I Tah C (I of I)
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| r t er:S s't SAFETY pffME3 8tt!
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| amunstA1. H' TNT AI.l F1 SITE ArtA pitt Reau.T ,_ _
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| cusERAl. FMf RCutt:T farlE skyf E Condit ion-e 3, 4 and 5 may respelse off-Site Protective Attlan ARE Of f-5Ite Prntert Ive Act Ione - 5ee RFQllIRED - See EF.2-n52. TAR''is".
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| EF-2-OS2. TAR "ti". __
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| Any one,of the in f lewing re.n li t icas t Any onie of t'ee le.Ilowing ron.f t t iong Any one of tiec following cowidttions: Any 3 of the following renditiong: 8 g
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| I I.) FC/SS cylafews that a grogn len* I l 1.) Ingn ..I ni f gls e pcwcr nr loan 1.) Iman of all af f uite ac twwer 1. Eess of all affatte ac power of onsite At: p..wcr rapalillity as concurrent witte f alleere nf liotle concurrent witle fallare af both of any two of the three finsion pen- e ind f ratret hve Faergency plee-el I;enetatara em Faergency Dienel Generatnen int duct barriers has occurred g plant determined Iy: greater than 15 minutes as deter- conditions are such that a potenttal mined by for the loss of the thtral barrier esista based on consideratinia cf the a.) FI on iT -1. "4 kV Run SA Bhr Fl on CF-l. 4 kV Ptf5 54 VOLTACF.' Fl on CF-l 4 kV RifS SA VULTACE following:
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| Trip /T o.d le" minsm. 1,05T;" Also LOSTI g FOR Tilt let BARRIER - F11F1.
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| F3 on CF-l 4 FV RL85 SR VOLTAGE F3 on CF-l, 4 kV Rtl5 SR VOLTAGE CLADDilec
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| ~ANil IDST;" LOSTg F I nn (T- l . "4 kV pun 58 R6 r Tr ip/ A.) Conditions indicat ing a potent ial Trnnhic" alare. 2.) Loss of all onsite vital de 2.) Imse of all onsite vital de loss o' feel cladding can lie deter-power as determined by: power as determined by mined by nt
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| ~
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| Ng on CF-35. BATTFRY SA TREMIBI.F; ils on CF-35, DATTIRY SA TRotisLEs I.) Violation of DelBR due to lann cf b.) loss ol operability of hath AND AND RCS flow or . loss of RCS anbraalina Fmergency filenel Ceneratorn, margin of abnormally hfgh (nel tem-N9 on CF-35. DATTERY SAR TRotf8LE M9 on CP-35. BATTERY SAS YRtN'BLE; peratures.
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| 2.) Signiffrent Inan of asnessment AND e
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| ~
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| Allo
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| ~
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| 2.) Inadequate core cooling deee en l l capability as f.:liented by: loss of core heatsink o,r core flow Mlp on CF-35. BATTERY SR 1Pintst Eg NIO on CF-35, BATTFRY SR TRtFIBLE; blockage or lACA concurrent vitie in thiden 1. ' . l.4 failure of ECCS.
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| Ingn os hat h t rain e of plant computer for r.ecater than 15 5.) Conditions indicattaa a lann eT .
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| fuel cIseding can be deterslaed 1.y l minuten.
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| 1.) Figston product activity in the tem
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| '~
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| reactor coolant. ,
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| lona of 59'16 Is* r greater than 15 minutsn.
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| 9 Iman all meteorological inst rument s f or recat er than 15 sinuten.
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| idt
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| . Technical Sperif trme lon reeguircel ninet.lewn d.sc to logg a f R M*. .
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| O El -l .p t s tuvinson 't I4 Attachment F.I inh O (I of I)
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| , e e
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| | |
| i e
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| iDSS 4] SAFETT PtlIICTroel ttNt!SIIAl. LVFJIT ALERT SITE AREA EMERcFJICT CRNERAL 190F.RCFRCT 3.) less of engineered nafety 3.) less of the ability tn achieve 3.) Imse of the ability to achieve. FOR T'IE 2nd BARRIER - RCS feature or fire protection system . or maintets Cold ShutJoine due to any or maintain Not Shutdown due to any PRR$5URE StRIIenARY function re.guiring shutdown hy of the following: of the followings ;
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| techatral nrecittrations. A.) Cenditions indicating a potential 3 (a) Inabilit:; to horate en Ph.de 5 (a) Inability to barate to Mode 4 loss of the BCS pressure boundary can Shutdows Kirgin of 2.01 k/k g or Shutdown Margin of 5.152 k/k (for be determined by:
| |
| (for greater than 15 minutes): or
| |
| ~
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| (b) toes ot - t atte Shutdown Coellag 1.) RCS overpressure transient due to tratang or (b) toss of both Steam Cenerrtorn loss of core heatsink or teactor as an effective heatsinks y power escursion or transient (c) Lnse of both essential C(N/ACCW requiring operatten of shutdown f trains. (c) Inability to maintain natural systems with failure to trip.
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| l circulation when forced flow is not
| |
| ! availableg er, R.) Conditione indicating a loan of l the BCS pressure boundary can be
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| ! (d) Insbility to make up RCS determiced by:
| |
| I volume (for greater than or equel .
| |
| to 15 minutes). l.) Decreasing RCS pressure and l increasing Containment radiation / ,
| |
| : 4. Reactor remains critical after 4 Transient requiring operation pressure / temperature / sump levels and g receipt of RPS or manual trip of shutdown systems with failure to no abnormal dif f erence between Stem .
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| signal si Indicated by trip (automaticly and manually) Cenerator pressuses (LOCA). ,
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| with no core damage immediately evident as determined by: 2.) Decreasing RCS pressure yd increasing radiation on Main Steam (a) Two or more like RPS trip (a) Two or more like RFS trip 1,ine Moeltors increasing level cr4 channels have reached or exceeded channels have reached or exceeded effected Steam Cenerator (SCTR).
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| the trip set point the trip set point.
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| FOR TWR 3rd RARRIER ABID AIID - CoelfAINMEtsT (b) Reed Switch Fosition Trans- (b) Reed Switch Fosition Trans- A.) Conditions indicating a potential mitters indicate 10 nr more CEA's mitters indicate 10 ne more CF.A's loss of containment can I,e determined not full innerted not fully inserted, by:
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| : 4. ) lenn of rontainment integrity AND AIID 1.) Steam line break inside Contain-reqqlting ahntefown by Technical ment concurrent with failure of Con-Sperlitrationn. (c) No indtration of core damage (c) No indication of ente damage. tainment Neat Removal Systems.
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| 5.) Most o.- all Control Room annun- 5.) Most or all Control Room ann n- 2.) LOCA concurrest with failure of clators innt an determined by visual clators lost and,SS/EC opinion that Containment Nest Removal Systema, observation. while in Mmles I.2.3.4 transient which jeopardizes reactor safety la in progress. 1.) Foot-LOCA hydrogen generation concurrent with failure of Nydrogen 6.) Evacuation of Content Room anti- 6.) Evacuation of Cnntrol Room Removal Systems.
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| cipated or required with contral of required with rnntral of shutdown shutdown syneens estahlinhed from systeme _100T entablinhed from Incal Incal statfnna. stattens within li minutes.
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| O e EP .1.t m l R-vinson 1 I5 Attachment 7.1 Tab D (2 cf 1) t . .
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| | |
| 4 -- --
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| .m _
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| I W ', ut SADFTY FlipHTltlN .
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| \ltNI SITE AS:l A litt Rf:tNel CENFRAl. FH&Rt:lHr:Y ,
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| I'tH":tf Al IViff t R.) Conditions in.fleating a leen= of containment can be determineJ;by:
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| 8.) I.IICA or steam line break f alle**e.1 by rapidly increaging pressure in t he !
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| Shield Butiding ranalue (primar y 8:en- f tainment to Shteld Ruilding fantel. I 2.) Fressere in one Steam :eneratar continues to decrease following pi t-nation of MSIS with Contain=ent pressure not increasing (SI.R beturen Containment and H9IV).
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| 3.) MSIV position inffration alm a I
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| MSl4 not fully closed fallowlag art-wat tan of HSIS. and primary to secondary leakage Indicatel.
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| 4.) Hultiple Containment Isalattan Valee fattures creating a reles=e path from Containment to natside atmosphere.
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| 2.) Transient requiring nreratton cf shutdown systeem with failure en trip (automatically and manually) and in the opinion of the SS/EC. a Core Melt Sequence is in progress, or Imminent, as determined by:
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| Two or more like Rr5 trip channeln have reached or exceeded the telp
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| * set point. ,
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| O Reed Suttrh Fositten Trangmitters indicate 10 or more CFA's not fully inserted.
| |
| t> pinion of the SS/EC that a Core Melt Sequence is in progrenn, or faminent.
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| O 0 16 Attachment 7.1 Tah t) (1 cf 1)
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| FP- t - f wil R. v i n i. n i
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| . e i, MAZAND TO STATICII OPERATICII
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| 'Al.ERT SITE ' ARFA IMERf;P38CT CENERAL' E993CEIICT
| |
| _. IrtitMIIAl. I'VINT _ . _ _ . _ _ . . . . . . . . -
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| Any one of the following ennditions: Any one of the following conditions: Any esse of the int *nwing conditions: IIUyt t ' ' I.) ol.nervat ion of flee within the 1.) Observation of fire witlein the 1.) chservation of fire within the off-stte Protective Actions ARE plant wielrh laats langer tisan 10 plant which patentfally affects plant which compromises bath trains . 3808813E11 - See EF-2-052. TAB *E''.
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| minuses g ;etey flee within the owner nafety systems. of a safety system 3 fts feenettons.
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| * controlle.1 area which requires sffsite fire ifr.htfeeg assistance. l.) Any mejor hasard which causes messive common damage to plant sys-2.) Altrrait e asle ensite but 2.) Aircraft trank or stamile impact 2.) Aircraft crash or missile lmpact teme such that, in the opinion of outelete protecteil area. inside the protected area. or emploelen enuses major damage to the SS/EC a Core fielt Sequence is safety systems. In progress, or Imminent. and the i 1.) Trafn Jeratlmens numite. ultimate f ailure of Contatnment la linely.
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| l 4.) Near or nnsite explosinn. 3.) Known esplosion damage to the factitty which degrades the level i
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| . or safety of the plant.
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| 1
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| ( 5.) Hear or on<lte uncontrolled 4.) Uncontrolled entry into pro- 3.) tincontrolled entry of toxic or i telenne al e nric or flammahle gas, tected ares environs of toxic or flammable see into facility eivtrone l flammable gas er-% that a Protected such that it la detected within the Action le required. site boendary and protective hetinne are tenen.
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| f L
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| * I O #
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| EP-1 001 Revision 1 II Artscheent 7.1 Tab F.(I of I)
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| , e e
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| | |
| -q r
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| i e
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| NATilR3 PNf10000EIRA
| |
| , TNitS$1f t. IVf MT AllRT _
| |
| SITE ARFA EMERCESICT CEIBEiAI. E7tERCPCT
| |
| ~
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| IIUTL ofs-Site Protective Actione ABE' BEqulBED - See gP-7-OS2 TAB' P'.
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| Any y ni the following condittonst Any one of the following conditinnet Any one of the following conditionst l.) Any easthvenane felt in-plant or 1.) Earthquake recording greater than 1.) Earthquake recording greater valid receipt of I.10 (on CF-35). 0.05 g ground acceleratinn of valid than 0.1 3 ground accelerettan.
| |
| SEISMIC RE:ORITRS IN tirFRATION alarm. receipt of Melo (on CP-35). SEISMIC ETiJIT alare.
| |
| 7.) Any in-plant fin nling condition 2.) llurricane surge or other in- 2.) Ilurritane surge or other In- 1.) Any major natural phenneennn whirh. In thn opinlan af the $5/EC. plant flooding conditinn which. In plant finoding condition which which esuses massive common damage potentially degraden the level of the opinion of the SS/EC actually causes actual failure of vital- to plant systems au,h that, in t he-safety of thn plant; or river water degrades the level of safety of the equfymenti or, river water breaching opinion of the SS/EC. a Core Melt level at Intabe structure greater planti g river water level at the levee (EL. +30 ft. MSL). Sequence is in progress, or j than +14 ft. HSI.. Intake structure greater than *27 tuninent and the ultisate fatture i f t. MSI.. of Containment ter Ifftely.
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| l
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| : 3. ) Any t oe n-ido angi t e. .3.) Any tornado striking the pro- 3.) Tornado causes major damage to ,
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| tected area. vital equipment.
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| i 4.) Site enmes under a hurricane 4.) Site experiencing sustained 4.) Iturricane with wind gusts- [
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| warning. hurricane force vinde (74 aph). exceeding 200 mph. !
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| i '
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| i O #
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| 18 Attachment F.I Tab F (I of I)
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| Ep- I-tml Revision i e I e
| |
| | |
| ~
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| 1 I
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| L l e:0311Y E.lellO Nil!;t.
| |
| IUf'!;t'At. 9. VIN'S AllRI SilF art.A FMits:638t Y 4:8.litRAl. PMr let:tE7 80sfiF.
| |
| .la. .ii.t.
| |
| Of f-Site rentert ive Art Inses ARE ()ff-sjte Protective Actions ARE '
| |
| IttyltflRFD - See FT-2-4952. TART;". RRgillRRD , See FP-2-852. TAR'f".
| |
| O.) Any accus it y t hreat , at ecepted 1.) SS/Ft: n.it i f le.1 by Securit y of 1.) Busiincut Io n of phystral I.) Imse of phyntral nerarit y rent rnt i ent r y co at temptcil malwitage such an engalns nernrlty rreprenels.c in nerurity remtrol of the plant. of time plant.
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| ; that Scrurity nottfles the SS/ff of the plant. but sont to vital areas as l
| |
| init lat te n af t he Security definc.1 in the Scrur it y (:nnt innency
| |
| (:nnt ineceiry Plisn . Plan.
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| I j .
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| b 4
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| i s
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| 4
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| [
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| T J
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| I i i j i f 8 i
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| l O '
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| O '
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| EP-l-fitil Revision 1 19 Attacheent F.1 Tab 4: (I of 1) e e e
| |
| | |
| N t SCELI.AllFAMIS IfHitStiAI. ININT AI.f R1 SITE ARFA fitERCEl0CT CRIBERAt. DIERCHICT letFTE Any one of the following conditionet I.) Tr.insportat iem nf contaninated Off-Site Preteettee Actit** -ARE Injure.1 In.fividual frem site to 38Q1118E3 - See FF-2-057. TAB *ii".
| |
| offslse hospital.
| |
| : 2. ) tiel.cr pla.it renditions exist I.) tither plant conditions exist 1.) Other plant conditions estat 1.) Other plant conditlans exist that, in the opinlens of the SS/EC. that, in the opinions of the SS/EC. that, in the optalon of the SS/EC that, in the opinion of the SS/EC warrant precautionary activation of warrant activation of emergency could rescit in a Core Melt Sequence-werrant increaned awaremens on the or a rolesse of radioactivity to the part of the plant operating staff or Technical Support Center and placing centers and monitoring teams or a state or Incal authorities; or Faergency eyerationn Facility and precautionary nottiteetion to the environment sects that resultant Jose 8
| |
| require plant sluitdown under other key emessency personnel on puhl te near the site. at the site traundary could redtle or technlaal preciffration requirements; standhy. execed the EF4 Frotective Action '
| |
| Culdelines of 1.0 rem whole holy **r g f nvntve other t han nnreal $ rema to the thytold. * ,
| |
| cont rolle.I nlmedown.
| |
| t i 9 i
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| e l
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| I l
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| 1 6
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| I l
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| 9 D
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| D e
| |
| l O
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| f.p- i - tta l Revinton 1 70 Attarheent 1. 8 Tab II (I af I)
| |
| . e a
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| | |
| e EMERGENCY C00RDINATOR'S CLOSE-0UT C"ECKLIST INSTRUCTION
| |
| : 1. This checklist shall be used by the Emergency Coordinator to evaluate a decision to terminata an existing emergency condition. All criteria shall be met.
| |
| 2, . This checklist, completed and signed by the Emergency Coordinator, is a prerequisite for initiation of the Recovery Organization in accordance with EP-2-170.
| |
| CRITERIA CRITERIA MET (Initials)
| |
| : 1. The plant is in a stable configuration with ,
| |
| adequate core cooling.
| |
| : 2. In-plant radiation levels are stable or decreasing with time.
| |
| : 3. The release of radioactive material to the environment is controlled and there is no significant potential for additional uncontrolled releases.
| |
| : 4. All safety systems necessary to maintain the plant in a stable configuration are operable.
| |
| : 5. LFires are extinguished; flooding conditions and any other site damage are under control.
| |
| e 6. All vital areas requiring occupancy are habitable.
| |
| : 7. Site security control.is established.
| |
| : 8. Contaminated injured personnel have been transported to a hospital.
| |
| , 9. All implementing procedures, have been closed out or are determined to remain active with responsibility for their completion and closure assigned to an individual.
| |
| Approval to terminate emergency condition granted by:
| |
| Date: Time:
| |
| Emergency-Coordinator EP-1-001 Rev. 2 21 Attachment 7.2 (1 of 1)
| |
| | |
| WATERFORD 3 SES 7 ,
| |
| PLANT OPERATING MANGAL
| |
| .D
| |
| # LOUISIANA POWER & LIGHT M SY POM VOLUME. is EP-1-010 POM SECTION 2 REVISION 3 Emergency Plan Implementing Instruction Unusual Event LP&L W-3 RECORDS UNCONTROLLED DO NOT USE IN ANY SAFETY-RELATED TESTIN COPY .
| |
| MAINTENANCE. PORC Meeting OR OPjo.Afh0HAL ACTIVITY R ,
| |
| Reviewed 3 [ E___ _
| |
| ORC innan Approved: #
| |
| l .LUN / d /8(
| |
| Plant Manager-Nuclear Approval Date Effective Date ;
| |
| _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ A e. __t______m. _/2 4%. AO _ 4 - n
| |
| | |
| l WATERFORD 3 SE3 -
| |
| PLA37 OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Precedure No. C - / - 'J / 0 Title Mtiu a J 5%A Effective Data Mhd (if different from approval date) c-n1.e. A_ n_ ar c A. Change 50. Nb _
| |
| B. Revision No. 3 ~
| |
| C. Deletion- ^'14 neannu ran enauer. nrvTsTav on nrt_rtrow .
| |
| $l& ff sNO2 M QCoAOneded -
| |
| nrountn_ sInmitunts f{ l:TW3# N ;~"' .- , .1 ,
| |
| originator I I (. b a's Date / 2./ > M 6 ,3 Tcchnical Review h ''/ N ed d Date /7/27 #N SAFETT ETALUATION Does this change, revision, or deletion: YE3 NC
| |
| : 1. Change the facility as described in the FSAR7
| |
| : 2. Change the procedures as desoribed in the FSAR7- / ,
| |
| : 3. Conduct tests / experiments not described in the F3AR7 b 4 Create a condition or conduct an operation which ex-coeda, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Ev 1 tion opecklist.
| |
| Safety Evaluation T/bdVDate / 77 3 Group /Dep't. Head Review Y dd Date /
| |
| /f?783 Temporary-Approval
| |
| * Date (NO3)
| |
| Temporary Approvale Date QC Review AJ Jr// M - Date '-eF' PORC Review M 'N /5 ~~ Date /-d #f 'M Meeting No.
| |
| Plant Manager-Nuclear Approval Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2(e i
| |
| | |
| Emergency Plan Implementing Instruction EP-1.-010 Unusual Event Revision 3 TABLE OF CONTENTS 1.0 PURPOSE'
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS
| |
| '5.0 PROCEDURE .
| |
| .6.0 FINAL CONDITIONS
| |
| ~
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| 7.0 ATTACHMENTS .
| |
| LIST OF EFFECTIVE PAGES Title Revision 3 1 Revision 3 1
| |
| | |
| Emergency Plan Implementing Instruction EP-1-010 Unusual Event Revision 3 1.0 PURPOSE fo outline the actions to be taken for an emergency condition at the Unusual Event Level.
| |
| t NOTE The normal on-shift >:omplaint of personnel is considered sufficient to respond to an Unusual Event. Activation of other LP&L emergency organizations is optional.
| |
| l l
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| '2.1 Waterford 3 SES Emergency Plan 2.2. EP-1-001, Recognition and Classification of Emergency Conditions 2.3 Emergency Management Resources Book i
| |
| .2.4 EP-1-020, Alert 2.5 EP-1-030, Site Area Emergency 2.6 EP-1-040, General Emergency 2.7 EP-2-010, Notifications and Communications 2.8 EP-2-031, In-Plant Radiological Controls and Surveys During Emergencies 2.9 EP-2-100, Technical Support Center (TSC) Activation, Operation, and
| |
| ' Deactivation 2.10 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation
| |
| ; -2.11 EP-2-150, Emergency Plan Implementing Records 2.12 FP-1-003, Fire Emergency / Reports 3.0 RESPONSIBILITIES The Emergency Coordinator is responsible for ensuring that the actions as outlined in this procedure are carried out. The Shift Supervisor is 2
| |
| | |
| Emergency Plan Implementing Instruction EP-1-010 Unusual Event Revision 3 the Emergency Coordinator and responsiele for implementation of this l'
| |
| procedure.
| |
| 4.0 INITIAT[NG_ CONDITIONS This procedure is to be initiated upon reaching the following conditions:
| |
| 4.1 -Whenever an Unusual Event is recognized and classified per EP-1-001. -
| |
| 4.2 At the direction of the Emergency Coordinator.
| |
| 5.0 PROCEDURE 5.1 Sound the station alarm as necessary. l 5.2 Make the following announcement (s):
| |
| .5.2.1 " Attention all-personnel; attention all personnel: An Unusual Event has been declared. All members of the On-Shift Emergency Organization report to your stations. All other personnel should continue with their normal duties unless further instruction is given. The maintenance radio frequency is now dedicated for emergency use only."
| |
| 5.2.2 If there is a localized emergency announce its type and location end instruct personnel to stand clear of-this area (Refer to FP-1-003).
| |
| 5.2.3 Repeat the-announcement (s).
| |
| 5.3 Make initial contact with the Duty Plant Manager (Refer to the Emergency Management Resources Book).
| |
| 5.3.1 If the Ducy Plant Manager cannot be' reached, contact any of the alternate Duty Plant Managers (Refer to the Emergency Managerment Resources Book).
| |
| 3
| |
| | |
| . Emergency Plan Lnplementing Instruction EP-1-010 Unusual Event Revision 3 5.3.2 Upon contact with the Duty Plant Manager, discuss the following:
| |
| 5.3.2.1 Nature of situation 5.3.2.2 Classification 5.3.2.3 Action taken or to be taken 5.3.2.4 Need to call in additional support personnel 5'.3.2.5 Advise that the Duty EOF Director be contacted by the Duty Plant i Manager.
| |
| 5.3.2.6 -Advise that Emergency News Director be contacted by the Duty Plant Manager. (Refer to the Emergency Management Resources Book).
| |
| S '. 4 If-necessary, activate the on-site Emergenc Response Organization by directing the Emergency Communicator to activate the Emergency Pager System in accordance with EP-2-010, Attachment 7.2.
| |
| ESTE ,
| |
| If conditions. exist that could be hazardous to those. personnel reporting to the site, provide instructions for appropriate protective actions including use of alternate routes, activiation of backup facilities, etc. as necessary.
| |
| 5.5 Complete Attachment 7.5 of EP-2-010, Initial Notification Form, and prcvide the form and the agencies to be notifed to the Emergency Communicator. Direct the Emergency Communicator to commence initial off-site notifications of the appropriate organizations
| |
| ' listed below in accordance with EP-2-010:
| |
| 5.5.1 St. Charles Parish Emergency Operations Center (EOC) - Notify within 15 minutes of classification.
| |
| 5.5.2, St. John the Baptist Parish EOC '- Notify within 15 minutes of classification.
| |
| 4
| |
| | |
| Emergency Plan Implementing Instruction EP-1-010 Unusual Event Reyision 3 5.5.3 Louisiana Nuclear Energy Division (LNED) - Notify within 15
| |
| ~
| |
| 4 minuteslof classifiention.
| |
| 5.5. 4~ Louisiana.0ffice of Emergency Preparedness L0EP) - Notify within -
| |
| 15 minutes of classification. j 5.5.5 Waterford l'and 2 - Notify within 15 minutes of classification. ,
| |
| 5.5.6 Nuclear Regulatory Commission (NRC) - Within one hour of classification. !
| |
| 5.5.7 U. S. Coast Guard - As necessary.
| |
| 5.5.8 Missouri Pacific Railroad - As necessary. ;
| |
| 5.5.9 American Nuclear Insurers (ANI) - As necessary. I 1
| |
| 5.6 1As additional information becomes available, update the Emergency Communicator .by completing Attachment 7.7 of EP-2-010, Follow-up Notification. Direct the Emergency Communicato'r to conduct additional updates to off-site agencies in accordance with EP-2-010.
| |
| 5.7 Direct a Health Physics Technician to initiate in-plant radiological controls in accordance with EP-2-031 if a real or potential radiological hazard exists.
| |
| 5.8 Initiate any additional response measures in accordance with applicable emergency procedures listed on Attachment 7.1.
| |
| 5.9 As-conditions change, periodically check EP-1-001 to. determine whether reclassification is necessary.
| |
| . 5 . 9.1' If reclassification is necessary, then reclassify the emergency in accordance with EP-1-001 and implement appropriate Implementing Instruction EP-1-020, EP-1-03'0, or EP-1-040.
| |
| 5.9.2 If closeout is appropriate, then close out the emergency with a verbal summary to all agencies / personnel as indicated on Attachment 7.13 of EP-2-010 and refer to EP-2-170 to initiate any appropriate recovery activities. j i
| |
| l l
| |
| 5 l l
| |
| 1
| |
| | |
| J.
| |
| . Emergency Plan Implementing Instruction EP-1-010 ,
| |
| Unusual Event' Revision 3 6.0 FINAL CONDITIONS
| |
| :6.1 The. Unusual Event has'been closed out with normal station administration resumed and appropriate recovery activities underway.
| |
| 7.0 -ATTAC10ENTS
| |
| ~
| |
| 7.1 Procedure Reference for-Additional Response Guidelines ,
| |
| s
| |
| +
| |
| 9 Y
| |
| O
| |
| ?
| |
| 6
| |
| | |
| PROCEDURE-REFERENCE FOR ADDITIONAL RESPONSE GUIDELINES Topic Reference Personnel EP-2-020, Contaminated Injured /Ill Per.onnel EP-2-030, Emergency Radiation Exposure Guidelines and Controls EP-2-032, Monitoring cr.d ":::atamination EP-2-081, Search and Rescue
| |
| ~
| |
| FP-1-003, Fire Emergency / Reports UNT-7-018, First Aid and Medical Care Radiation Releases EP-2-060, Radiological Field Monitoring Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentry EP-2-170, Reccvery Emergency Management Resources Book l
| |
| 5 EP-1-010' Revision 3 7 Attachment 7.1 (1 of 1)
| |
| | |
| l WATERFORD 3 SES 7 c: PLANT OPERATING MANDAL
| |
| # LOUISIANA POWER & LIGHT b SYS POM VOLUME 18 EP-1-020 POM SECTION 2 REVISION ,
| |
| Emergency Plan Implementing Instruction Alert
| |
| ^
| |
| LP&L W-3 RECORDS UNCON1RO1 LED COPY _.
| |
| DO NOT USE IN ANY SAFETY-RELATED TESTING, MAINTENANCE, OR OPERATIONAL ACTIVITY PORC Meeting No. 83-52A Reviewed: , M(([C2 d_,%
| |
| PORC Qiairman Approved: J, i i t. -
| |
| Il!8%
| |
| Plant Manager-Nuclear Approval Date
| |
| - Fuel Load Effective Date
| |
| .. _ _n_- ____--_______a
| |
| | |
| /- .
| |
| '4ATERFORD 3 SE3 -
| |
| PLANT OPERATING MANUAL CHANGE /RE7ISION/ DELETION REQUEST Precedure No. O ' I - O E Title b6 Effective Date M M (if different from approval date)
| |
| < - ni.ta 1. B. er c A. Change No. _
| |
| 3; Revision No. 3 '
| |
| C. Deletion MM swanne yon enauer_ nrvTsron. on artrtrow
| |
| /lbtL- C$Cbf.$1lS (AA'M . (x09st ,
| |
| A
| |
| ' ,M# M0~
| |
| REQUIRED SICMATURES originator *S~~5~ leu)I'r _
| |
| h- Date /.2/c9/,92 Tcohnical Review p/<e#%Ad Date ' 7 /' 1/P 3 SAFETT ETALUATION Doesthischange, revision,ordeletioni YES NO
| |
| : 1. Change the. facility as described in the FSAR7 #
| |
| : 2. Change the procedures as described in the FSAR7- _
| |
| J,,
| |
| : 3. Conduct tests / experiments not described in the FSAR7 ._._
| |
| : 4. Create a condition or conduct an operation which ex- _d coeda, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety valuatt Satety Evaluation b ; y checklist.~ v E e A M Date / 2d Mg 3 Group /Dep't. Head Review N M e [ A d M Dete / ML //fl Temporary Approval * .,,,,,,,, Da te (NO3)
| |
| Temporary Approvale Date QC Review A'd M/dw Date ot +-<
| |
| PORC Review [Mdd-e~-
| |
| , Date / d -P'/ Meeting No.
| |
| Plant Manager-Nuclear Approval Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2(s 4
| |
| | |
| u Emergency Plan Implementing Instruction EP-1-020 Alert' Revision 3 TABLE OF CONTENTS 1.0 PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| 3.0 RESPONSIBILITIES ~
| |
| 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Procedure Reference for Additional Response Guidelines (1 page)
| |
| LIST OF EFFECTIVE PAGES Title - Revision 3 1-8 Revision 3 i
| |
| r 1
| |
| | |
| Emergency Plan Implementing Instruction EP-1-020 Alert Revision 3 1.0 PURPOSE To outline the actions to be taken for an emergency condition at the Alert Level.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 Waterford 3 SES Emergency Plan 2.2 EP-1-001, Recognition and Claasification of Emergency Conditions ,
| |
| 2.3 EP-1-010, Unusual Event 2.4 EP-1-030, Site Area Emergency -
| |
| 2.5 -EP-1-040, General Emergency 2.6 EP-2-010, Notifications and. Communications 2.7 EP-2-031, In-Plant Radiological Controls and Surveys During Emergencies 2.8 EP-2-050, Offsite Dose Assessment (Manual) 2.9 EP-2-051,.0ffsite Dose Assessment (Computerized) 2.10 EP-2-052, Protective Action Guidelines 2.11 EP-2-060, Radiological Field Monitoring 2.12 EP-2-100, Technical Support Center'(TSC) Activation, Operation, and Deactivation 2.13 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation 2.14 EP-2-150, Emergency Plan Implementing Records
| |
| '2.15 Emergency Management-Resources Book l
| |
| 2.16 EP-2-034, Onsite Surveys During. Emergencies 2.17 FP-1-003, Fire Emergency / Records
| |
| -~ . .
| |
| 2
| |
| ''I l
| |
| | |
| Emergency Plan Implementing Instruction EP-1-020 Alert Revision 3
| |
| '2.18 UNT-7-018, First Aid and Medical Care 2.19 EP-2-071, Site Protective Measures 2.20 EP-2-130, Emergency Team Assignments 3.0 RESPONSIBILITIES i The Emergency Coordinator is responsible for ensuring that the actions outlined in this procedure are carried out. The Shift Supervisor .
| |
| is the Emergency Coordinator and responsible for implementation of this procedure until relieved by the Duty Plant Manager. !
| |
| 4.0 INITIATING CONDITIONS This procedure is to be. initiated upon reaching the following conditions:
| |
| 4.1 Whenever an Alert is recognized and classified in accordance with EP-1-001. .
| |
| '4.2 At the direction of the Emergency Coordinator.
| |
| 5.0 PROCEDURE 5.1 Sound the station alarm as necessary: l 5.2 Make the following announcement (s):
| |
| 5 . 2.' 1 " Attention all personnel; attention all>perscanel: An Alert has been declared. All members of the on-Site Emergency Response Organization report to your stations. All other personnel report to your work stations. (If the emergency is radiation oriented, add: "There will be no smoking, eating or drinking until further notice.") "The Maintenance radio frequency is now dedicated for emergency use only."
| |
| 5.2.2 If there is a localized emergency announce its type and instruct personnel to stand clear of this area (refer to FP-1-003). l 3
| |
| | |
| Emergency Plan Implementing Instruction EP-1-020 Alert Revision 3 5.2.3 Repeat the announcement (s).
| |
| 5.2.4 Consider site protective measures in accordance with EP-2-071.
| |
| 5.3 Make initial contact with the Duty Plant Manager (Refer to the Emergency Management Resources Book).
| |
| 5.3.1 If the Duty Plant Manager cannot be reached, contact any of the alternate Duty Plant Managers (Refer to the Emergency Management Resources Book).
| |
| ~
| |
| 5.3.2 Upon contact with the Duty Plant Manager, discuss the following:
| |
| 5.3.2.1 Nature of the situation 5.3.2.2 Classification 5.3.2.3 Action taken or to be taken 5.3.2.4 Need to activate emergency response facilities 5.3.2.5 Advise that the Duty Emergency Operations Facility Director be contacted by the Duty Plant Manager.
| |
| 5.3.2.6 Advise that the Emergency News Director be contacted by the Duty
| |
| . Plant Manager.
| |
| 5.4 Direct the Emergency Communicator to activate the Emergency Pager System in accordance with Attachment 7.2 of EP-2-010.
| |
| NOTE If conditions exist that could be hazardous to those personnel reporting to the site, provide instructions for appropriate protective actions including use of alternate routes, activation of backup facilities, etc. as recessary.
| |
| 5.5 Complete Attachment 7.5, Initial Notification Form, or Attachment 7.7, Followup Notification Form as appropriate of EP-2-010 and provide the form and agencies to be notified to the Emergency Communicator Direct the E.argency Communicator to commence initial off-site notifications of the appropriate organizations listed below in accordance with EP-2-010.
| |
| 4 l
| |
| | |
| Emergency Plan Implementing Instruction EP-1-020 Alert Revision 3 5.5.1 St. Charles Parish Emergency Operations Center (EOC) - Notify within 15 minutes of classification. .
| |
| 5.5.2 St. John the Baptist Parish EOC - Notify within 15 minutes of classification.
| |
| 5.5.3 Louisiana Nuclear Energy Division (LNED) - Notify within 15 minutes of classification. f 5.5.4 Louisiana Office of Emergency Preparedness L0EP) - Notify within 15 ,
| |
| minutes of classification.
| |
| 5.5.5 Waterford 1 and 2 - Notify within 15 minutes of classification but .
| |
| * I only after above notifications. .
| |
| 5.5.6 Nuclear Regulatory Commission (NRC) - Notify within one hour of '
| |
| classification.
| |
| 5.5.7 Middle South Utilities - As soon as possible.
| |
| 5.5.8 Institute of Nuclear Power Operations (INPO) - As soon as possible. l 5.5.9 U.S. Coast Guard - As necessary 5.5.-10 Missouri Pacific Railroad - As-necessary.. !,
| |
| 5.5.11 American Nuclear Insureres (ANI) - As necessary l 5.6 As additional information becomes available, update the Emergency Communicator by completing Attachment 7.7, Follow-up Notification, of EP-2-010. Direct the Emergency Communicatcr to conduct additional updates to offsite agencies in accordance with EP-2-010.
| |
| 5.7 Initiate off-site dose assessment in accordance with EP-2-050 for manual assessment or EP-2-051 for computerized assessment.
| |
| Determine the need for protective action recommendations in accordance with EP-2-052, Protective Action Guidelines.
| |
| 5.8 If radiological releases are occurring, instruct the Health Physics Coordinator to activate Radiole3 i cal Field Monitoring Teams in accordance with EP-2-130 and EP-2-060.
| |
| 5.9 Initiate activation of the Technical Support Center in accordance
| |
| ^
| |
| with EP-2-100.
| |
| 5.10 Initiate activation of the Operational Support Center in accordance with EP-2-101, 5
| |
| | |
| I Emergency Plan Implementing Instruct.ica EE-!-020 Alert Revision ;
| |
| 5.11 Direct the Health Physics Coordinator and/or the Radiological Controls to initiate in plant radiological controls in accordance with EP-2-031 if a potential radiological hazard exists and to perfrom on-site surveys as necessary in accordance with EP-2-034.
| |
| 5.12 Ensure that emergency logs / records are kept in accordance with EP-2-150.
| |
| 5.13 Initiate any additional response measures in accordance with the applicable emergency procedures listed on Attachment 7.1.
| |
| 5.14 As conditions change, periodically check EP-1-001 to determine whether i reclassification is necessary.
| |
| 5.14.1
| |
| * If reclassification is necessary, then reclassify emergency in I accordance with EP-1-001 and implement the appropriate Emergency Plan Implementing Instruction: EP-1-010, EP-1-030 or EP-1-040.
| |
| 5.14.2 If closeout is appropriate, then close out the emergency with a verbal summary to all agencies / personnel as indicated on Attachment 7.13 of EP-2-010 and implement EP-2-170 to initiate recovery activities. ,
| |
| 6
| |
| | |
| e Emergency Plan' Implementing Instruction EP-1-020 Alert Revision 3
| |
| - 6. 0' FINAL CONDITIONS
| |
| ' 6.1. The Alert has been closed out with normal station administration resumed and recovery activities initiated in'accordance with EP-2-170
| |
| 'or the emergency is reclassified.
| |
| . 7.0 ATTACHMENTS
| |
| ~
| |
| 7.1 Procedure Reference for Additional Response Guidelines
| |
| \
| |
| w C
| |
| 7 r " ''--- - ' -
| |
| | |
| PROCEDURE REFERENCE FOR ADDITIONAL RESPONSE GUIDELINES Topic Reference Personnel EP-2-020, Contaiminated Injured /Ill Personnel EP-2-030, Emergency Radiation Exposure Guidelines and Controls EP-2-032, Monitoring and Decontamination EP-2-081, Search and Rescue EP-1-003, Fire Emergency / Records UNT-7-018, First Aid and Medical Care Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentry EP-2-170, Recovery Emergency Management Resources Book l EP-1-020 Revision 3 8 Attachment 7.1 (1 of 1)
| |
| | |
| WATERFORD 3 SES 7 m. PLANT OPERATING MANDAL LOUISIANA POWER & LIGHT US.a#sE POM VOLUME 18 EP-1-030 REVISION 3 POM SECTION _ L Emergency Plan Implementing Instruction Site Area Emergency LP&L W-3 RECORDS UNCONTROLLED COPY DO NOT 03j IN ANY SAFETY-RELATED TESTING, fv.AINTENANCE, OR Ot-ERATIONAL ACTIVITY PORC Meeting No. 83-52A Reviewed: M 8_d((p_a~
| |
| PORC Chairman Approved: i 2 C_ _ .
| |
| ll!hY Plant Itnager-Nuclear Approval Date Fuel Load '
| |
| Effective Date
| |
| | |
| i WATERFORD 3 SE3 -
| |
| PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. -/-030 Title . *N ddCt b4 cam .c<,
| |
| Effective'Date U b d (if different from approval 5te) '
| |
| t'am ni ata 1. R. are C A. Change No. #!'l U
| |
| B. Revision No. ~
| |
| C. Deletion ^> N araman ren'enauer: navTsTen on nrtman Afsu_ di k >'lecl.- Loen o i 09 >flot i
| |
| EEot! IRED SIGNATURES % Y# #
| |
| Originator 3'~ X L p_lb lh g,g, jft ')/83
| |
| -Tcchnical Review j' d ' W Date Eh 74 %
| |
| SAFETT ITALUATION Does this change, revision, or deletion: YE3 NO
| |
| : 1. -Change the facility as described in the FSAR7- V a
| |
| : 2. Change the procedures as described in the FSAR7- _
| |
| : 3. Conduet tests / experiments not described in the FSAR7 #
| |
| 4 Create a condition or conduct an operation which ex- #
| |
| coeds, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Eval t on checklist.
| |
| Safety Evaluation M4 aIQste /6 2M6 3 Group /Dep't. Head Review _M M Da te /E[17[83 Temporary Approval' Date (NO3)
| |
| Temporary Approvale Date QC Review 4.4 W'/ k - /- - Date /- /- F''
| |
| PORC Review A /2 d /0 -
| |
| , Date /-6 "f V Meeting No.
| |
| Plant Manager-Nuclear Approval Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UMT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G i
| |
| | |
| c
| |
| -: ' Emergency Plan Implementing Instruction EP-1-030 m
| |
| . Site' Area'Emerg acy Revision 3 TABLE OF CONTENTS l.0 PURPOSE' 2;0. REFERENCES 3.0 RESPONSIBILITIES .
| |
| 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS ,
| |
| 7.1 Procedure References for Additional Response Guidelines
| |
| . (1 page)
| |
| LIST OF EFFECTIVE PAGES
| |
| \
| |
| Title, Revision 3 1-7 Revision 3 L
| |
| 1
| |
| | |
| Emergency Plan Implementing Instruction EF-1-030 Site Area Emergency Rerision 3 1.0 PURPOSE To outline the actions to be taken for an emergency condition at the Site Area Emergency level. ~
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 Waterford 3 SES Emergency Plan 2.2 EP-1-001, Recognition and Classification of Emergency Conditions
| |
| ' ~
| |
| 2.3 Emergency Management Resources Book 2.4 EP-1-010, Unusual Event .
| |
| 2.5 EP-1-020, Alert 2.6 EP-1-040, General Emergency 2.7 EP-2-010, Notifications and Communica'tions 2.8 EP-2-031, In-Plant Radiologia1 Controls and Surveys During Emergencies 2.9 EP-2-050, Offsite Dose Assessment (Manual) 2.10 EP-2-051, Offsite Dose Assessment (Computerized) 2.11 EP-2-060, Radiological Field Monitoring 2.12 EP-2-071, Site Protective Measutes 2.13 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.14 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation 2.15 EP-2-102, Emergency Operations Facility (EOF) Activation, Operation, and Deactivation 2.16 EP-2-150, Emergency Plan Implementing Records 2.17 EP-2-052, Protective Action Guidelines 2
| |
| | |
| Emergency Plan Implementing Inst uction IP *-020 Site Area Emergency Revision 3 2.18 EP-2-130, Emergency Team Assignments 2.19 EP-2-034, Onsite Surveys During Emergencies ,
| |
| 2.20 FP-1-003, Fita Emergency / Reports 2.21 UNT-7-018, First Aid and Medical Care 3.0 RESPONSIBILITIES The Emergency Coordinator is responsible for ensuring that the actions as outlined in t' tis procedure are carried out. The Shift Supervisor is the Emergency Coordinator and is responsible for implementation of this procedure until relieved by the Plant Manager.
| |
| 4.0 INITIATING CONDITIONS This procedure is to be initiated upon reaching the following conditions 4.1 Whenever a Site Area Emergency is recognized and classified in accordance with EP-1-001.
| |
| 4.2 At the direction of the Emergency Coordinator.
| |
| 5.0 PROCEDURE 5.1 SITE EVACUATION l 5.1.1 Select the off-site assembly area to be used: Monsanto Park, Luling or St. John the Baptist Catholic Church, Edgard.
| |
| 5.1.2 Notify the Security Shift Supervisor to prepare for evacuation of the site.
| |
| 5.1.3 Dispatch the Off-site Assembly Area Supervisor.
| |
| 5.1.4 Ensure that a Health Physics technician is dispatched to the off-site assembly area.
| |
| 5.1.5 Sound the station alarm. l 5.1.L Make.the following announcement:
| |
| " ATTENTION ALL PERSONNEL! ATTENTION ALL PERSONNEL: A SITE AREA EMERGENCY HAS BEEN DECLARED. ALL MEMBERS OF THE EMERGENCY ORGANIZATION REPORT TO YOUR STATIONS, DUE TO PLANT CONDITIONS, ALL NONESSENTIAL PERSONNEL MUST PROCEED IMMEDIATELY TO THE (state 3
| |
| | |
| Emergency Plan Implementing instruction F.P '. -TN Site Area Emergency Revision 3 one of the locations: ST. JORN THE BAPTIST CATHOLIC CHURCH OR MONSANTO PARK AREA). UPON ARRIVAL, ALL PERSONNEL LOG IN WITH THE ASSEMBLY AREA SUPERVISION. PERSONNEL IN RADIATION-CONTROLLED AREAS PROCEED TO THE HEALTH PHYSICS CONTROL POINT. THERE WILL BE NO SM0 KING, EATING, OR DRINKING UNTIL FURTHER NOTICE. THE MAINTENANCE RADIO FREQUENCY IS NOW DEDICATED FOR EMERGENCY USE ONLY."
| |
| 5.1.6.1 Repeat the aanouncement.
| |
| 5.1.7 Go to step 5.2 !
| |
| 5.2 Make initial contact with the Duty Plant Manager.
| |
| NOTE l i
| |
| See Emergency Management Resources Book for names and phone numbers.
| |
| I 5.2.1 If the Duty Plant Manager cannot be reached, contact any of the alternate Duty Plant Managers.
| |
| 5.2.2 Upon contact with the Duty Plant Manager, discuss the following:
| |
| 5.2.2.1 Nature of situation 5.2.2.2 Classification 5.2.2.3 Action taken or to be taken 5.2.2.4 Need to activate emergency response facilities 5.2.2.5 Advise that the Duty E0F Director be contacted.
| |
| l NOTE If conditions exist that could be hazardous to those personnel reporting to the site, provide instructions for appropriate protective actions including use of alternative routes, activation of backup facilities, etc. , as necessary.
| |
| 5.3 Direct the Emergency Communicator to activate the Emergency Pager System in accordance with EP-2-010.
| |
| 4
| |
| | |
| I
| |
| }
| |
| t l
| |
| l P Emergency Plan Implementing Instruction EP-1-030
| |
| . Site Area Emergency Revision 3 5.4 Complete Attachment 7.5, Initial Notification Form, or Attachment 7.7, Followup notification form as appropriate of EP-2-010, and provide the form and the-ageacies to be notified to the Emergency Communicator.
| |
| >-- Direct that the Emergency Communicator commences initial off-site notifications of the appropriate organizations listed below in accordance with EP-2-010:
| |
| 5.4.1 St. Charles Parish Emergency Operations Center (E0C)-notify within l '
| |
| 15 minutes of calssification.
| |
| 5.4.2 St. John the Baptist Parish E0C-notify within 15 minutes of classification -
| |
| 5.4.3 Louisiana Nuclear Energy Division (L!TED)-notify within 15 minutes i of classification 5.4.4 Louisiana Office of Emergency Preparedness (LOEP)-notify within '
| |
| 15 minutes of classification 5.4.5 Waterford 1 and 2-notify within 15 minutes of classification, but after above notifications _
| |
| 5.4.6 Nuclear Regulatory Commission (NRC)-notify within one hour of classification f
| |
| 5.4.7 Middle South Utilities - as soon as possible ;
| |
| i 5.4.8 Institute of Nuclear Power Operations (INPO) - as soon as possible -
| |
| ~5.4.9 - U. S. Coast Guard - as necessary 5.4.10 Missouri Pacific Railroad - as necessary 5.4.11 American Nuclear Insurers (ANI) - as necessary 5.5 As additional ~information becomes available, update the Emergency.
| |
| ' Communicator by completing Attachment 7.7, Follow-Up Notification, of EP-2-010. Direct the Emergency Communicator to conduct additional updates to off-site agencies per EP-2-010, 5.6 Initiate off-site dose assessment in accordance with EP-2-050 for manual assessment or EP-2-051 for computerized assessment. Determine the need for protective action recommendations per EP-2-052, Protective Action Guidelines.
| |
| 5
| |
| | |
| --Emergency Plan Implementing Instruction EP-1-630 Site' Area. Emergency -
| |
| Revision 3 1 5.7. If radioactive releases are occurring or anticipated, 14struct the Health Physics Coordinator to activate Radiological Field tionitoring Teams in accordance with EP-2-130 and EP-2-060.
| |
| 5.8 Initiate activation of the Technical Support Center in accordance with !
| |
| to EP-2-100,E if ' nct previously ' activated.
| |
| ~
| |
| i 5.9 . Initiate activation of the Emergency Operations Facility in accordance j with EP-2-102. _
| |
| f.10 Ensure that emergencyflogs/ records are kept in accordance with
| |
| 'EP-2-150.
| |
| ' 5.11 Direct the 1:aalth Physics Coordinator and/or the Radiological Controls
| |
| ~
| |
| Coordinator to. initiate in plant radiological controls in accordance with
| |
| ' EP-2-031 if a real or potential radiological hazard exists and to perform cn-site. surveys as necessary in accordance with EP-2-034.
| |
| 5.12 Initiate any additional response measures in-accordance with the applicable emergency procedures-listed-in Attachment 7.1.
| |
| 5.13 As conditions. change, periodically check EP-1-001 to determine whether
| |
| . reclassification is necessary.
| |
| 5.13.1 .If reclassification'is necessary,'then reclassify emergency according to.EP-1-001 and. implement appropriate Implementing Instruction EP-1-010, EP-1-020 or EP-1-040.
| |
| '5.13.2 If closeout is appropriate, then.close out emergency with a verbal summary to'all' agencies / personnel as indicated on Attachment 7.13 of EP-2-010 and implement EP-2-170 to initiate recovery activities.
| |
| ' 6.0 -- FINAL CONDITIONS 6.1 The Site Area Emergency'has'been closed out with normal station administration' resumed and. recovery activities initiated in accordance with~EP-2-170 or the emergency reclassified.
| |
| l7.0 ATTACHMENTS 7.1 Procedure Rererences for'Additonal Response Guidelines 6
| |
| ~ - . . . . -
| |
| | |
| vT-".
| |
| PROCEDi:RE REFERE!!CES FOR ADDITIONAL RES LIbTS
| |
| . Topic References Personnel EP-2-020, Contaminated Injured /Ill Personnel EP-2-030, Emergency Radiation Exposure Guidelines and Controls EP-2-032, Monitoring and Decontamination EP-2-033, Administration of Icdine-Blockir- . gents-EP-2-052, Protective Action Guidelines ,
| |
| EP-2-071, Site Protective Measures EP-2-081, Search and Rescue Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentrv EP-2-170, Recovery Emergency Management Resources Book l f
| |
| EP-1-030 7 Attachment 7.1 (1 of 1)
| |
| Revision 3-
| |
| | |
| j .
| |
| 1 WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA POWER & LIGHT NN b POM VOLUME 18 EP-i-040 POM SECTION 2 REVISION 3 Emergency Plan Implementing Instruation
| |
| )
| |
| General Emergency LP&L W-3 RECORDS UNCONTROLLED DO NOT US5 IN ANY SAFETY-RELATED TESTING, COPY fWAINTENANCE, OR OPERATIONAL ACTIVITY PORC Meeting No. 83-52A Reviewad: , Md67.2/p___ _
| |
| PORC Chairman Approved: 'tt L I ' /
| |
| Plant Manager-Nuclear Approval Date Fuel Load Effective Date
| |
| _ _ _ _ _ _ _ _ _ ____________._hm_-_A-_---M-_A-_ AA- -- ^ -^^-
| |
| | |
| t WATERFORD 3 SE3 PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Pr:cedure No. @- /- O Vo Title Sheaaf hs -m gffective Date U l ^^ d --. (if different from approval date) '
| |
| t'am ni ate 1. B_ er C A.- Change No.
| |
| N. Revision Ec. 3 '
| |
| C. Deletion' ^2A nemnnu ran ennuar_ nrvTsinn on nrtrtion ihs. dblail oa t.acoaam Ecl !
| |
| r - , c; -
| |
| . nrournrn n naatunes g Originator I I M [1 m/ N ~~Date /3 !8J Tcchnical Review [ # N/NA' ^d Date r 4 />D SAFETT ETALUATION '
| |
| Does this change, revision, or deletion: '
| |
| TE3 NO
| |
| : 1. - Change the facility as described in the FSAR7 [#
| |
| : 2. Change the procedures as described in the FSAR7-
| |
| : 3. Conduct testa / experiments not described in the FSAR7 __, _
| |
| : 4. Create a condition or conduct an operation which ex- _
| |
| coeda, or could result in exceeding, the limits in Technical Spec:1fications?
| |
| If'the answer to any of the above is yea, complete and at-tach a 10 CFR 50.59 Safety pr ti checklist.
| |
| Safety Evaluation Y < " 8hbato # 3 Grcup/Dep't. Head Review Me IN E4tw 'eh r F2
| |
| ' Temporary Approval' Date (NO3)
| |
| Temporary Approvals Date QC Review A 4 '/N 'b- 6 Date /- (- ' < "
| |
| PORC Revi Md'~ Date /"6 "P[ Meeting No.
| |
| Plant Manager-Nuclear Approval Date -
| |
| ' Temporary appre711 acat 'e followed by Plant Manager-Nuclear approval within 14' days.
| |
| UNT-1-003 Revision 6' Attachment 6.9 ( 1 cf 1) 2G
| |
| | |
| Emergency Plan Implementing Instruction EP-1-040 General Emergency Revision 3 TABLE OF CONTENTS 1.0 PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0- ATTACHMENTS 7.1 Procedure References for Additional Response Guidelines (1 page)
| |
| LIST OF EFFECTIVE PAGES Title Revision 3 1-8 Revision 3 1
| |
| | |
| s Emergency Plan Implementing Instruction EP-1-040 l General Emergency- Revision 3
| |
| , 1.0 ' PURPOSE y
| |
| To outline the actions to be taken for an emergency -condition at the General Emergency level.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 _Waterford 3 SES Emergency Plan
| |
| '2.2 EP-1-001, Recognition and Classification of Emergency Conditions 2.3 Emergency Management Resources Book l 2.~ 4 EP-1-010, Unusual Event 2.5 .EP-1-020, Alert 2.6 EP-1-030, Site Area Emergency 2.7 EP-2-010, Notifications and Communications
| |
| -2.8 EP-2-031, In-Plant Radiologica'l Controls and Surveys During Emergencies
| |
| '2.9_ EP-2-050, Offsite Dose Assessment (Manual) 2.10 EP-2-051, Offsite Dose Assessment (Computerized) 2.11 EP-2-052, Protective Action Guidelines 2.17~EP-2-060,. Radiological Field Monitoring 2.13 EP-2-071, Site Protective Measures
| |
| .2.14'EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.15 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation 2.16 EP-2-102, Emergency Operations Facility (EOF) Activation, Operation, and Deactivation 2
| |
| | |
| Emergency Plan Implementing' Instruction EP-1-040 General Emergency -
| |
| Revision 3 2.17 EP-2-150, Emergency Plan Implementing Records 2.18 EP-2-034, Onsite Surveys During Emergencies 2.19 FP-1-003, Fire Emergency / Reports 2.20'UNT-7-018, First Aid and Medical Care 3.0 RESPONSIBILITIES <-
| |
| The Emergency Coordinator is responsible for ensuring that the actions as outlined in this procedure are carried out. The Shift Supervisor is the Emergency Coordinator and responsible for implementation of this procedure until relieved by the Duty Plant Manager
| |
| . 4.0 ~ INITIATIATING CONDITIONS This procedure is to be initiated upon reaching the following conditions: -
| |
| 4.1. Whene,ver a General Emergency is recognized and classified per EP-1-001. -
| |
| 4.2 At the direction of the Emergency Coordinator.
| |
| -5.0 PROCEDURE ~
| |
| 5.1 initiate a Site Evacuation, if not previously initiated:
| |
| 5.1.1 Select the Off-site Assembly Area to be used: Monsanto Park, Luling or St. John the Baptist Catholic Church, Edgard. ,
| |
| 5.12 . Notify the Security Shift Supervisor to prepare for the evacuation of the site.
| |
| 5 .1. 3 - Dispatch the Off-site Assembly area Supervisor.
| |
| 5.1.4 Ensure that-a Health Physics technician is dispatched to the Off-site Assembly. Area.
| |
| 5.1.5 Sound the station alarm as necessary. l 5.2 Make the following announcement (s):
| |
| 3
| |
| | |
| 7 Emergency Plan Implementing Instruction EP-1-010 General Emergency Revision 3 5.2.1 " ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: A GENERAL EMERGENCY HAS BEEN DECLARED. ALL MEMBERS OF THE EMERGENCY ORGANIZATION REPORT TO YOUR STATIONS. DUE TO PLANT CONDITIONS
| |
| -ALL NONESSFNTIAL PERSONNEL MUST PROCEED IMMEDIATELY TO THE (state one'of the locations: St. John the-Baptist Catholic Church or Monsanto Park area.) UPON ARRIVAL, ALL PERSONNEL LOG
| |
| :IN WITH THE ASSEMBLY AREA SUPERVISOR. PERSONNEL IN RADIATION CONTROLLED AREAS PROCEED TO THE HEALTH PHYSICS CONTROL POINT.
| |
| THERE WILL BE NO SM0 KING, EATING OR DRINKING UNTIL FURTHER NOTICE. THE MAINTENANCE RADIO FREQUENCY IS NOW DEDICATED FOR EMERGENCY USE ONLY."
| |
| 5.2.2 If there is a localized emergency (e.g., fire), announce its type and location and instruct personnel to stand clear of this area (refer to FP-1-003). !
| |
| 5.2.3 Repeat the announcement (s).
| |
| 5.3 Make initial contact with the Duty Plant Manager.
| |
| NOTE See Emergency Management Resources Book for names and phone numbers.
| |
| 5.3.1 If the Duty Plant Manager cannot be reached, contact any of the alternate Duty Plant Managers.
| |
| 5;3.2' Upon contact with the Duty Plant Manager, discuss the following:
| |
| 5.3.2.1 Nature:of the situation 5.3.2.2 Classification
| |
| .5.3.2.3 Action taken or to be taken 5.3.2.4 Need to activate emergency response facilities 5.3.2.5 Advise the Emergency Operations Facility Director be contacted by the Duty Plant Manager.
| |
| 4
| |
| | |
| l' Emergency Plan Implementing Instruction EP-1-050
| |
| ' General Emergency - Revision 3 NOTE i
| |
| If conditions exist that could be hazardous i to those personnel reporting to the site, provide instructions for appropriate protective actions including use of alternative _ routes, i activation of backup facilities, etc. as necessary 5.4 Direct-the Emergency Communicator to activate the Emergency Pager System in accordance with EP-2-010.
| |
| 5.5 Complete Attachment 7.5, Initial Notification Form, or Att:chment 7.7, Followup Notification Form as appropriate. of EP-2-010, and provide the form and the agencies to be notified to the Emergency Communicator. Direct that the Emergency Communicator commence initial off-site. notifications of_the appropriate organizations listed below in accordance with EP-2-010:
| |
| '5.5.1 . St. Charles Parish Emergency Operations Center (E0C) - Notify within 15 minutes of classification.
| |
| 5.5.2- St. John the Baptist Parish EOC - Notify within 15 minutes of ;
| |
| classification.
| |
| [
| |
| 5.5.3 Louisiana Nuclear Energy Division (LNED) - Notify within 15 minutes j i
| |
| of classification.
| |
| I 5.5.4 Louisiana Office of Emergency Preparedness (LOEP) - Notify within 15
| |
| ~
| |
| minutes of classification.
| |
| _5.5.5 Waterford I and 2 - Notify within 15 minutes of classification, but
| |
| -after above notifications. j 15.5.6 Nuclear Regulatory Commission (NRC) - within one hour of classification..
| |
| 5.5.7 Middle South Utilities - as soon as possible i
| |
| -5.5.8 Institute of Nuclear Power Operations (INPO) - as soon as possible.
| |
| 5 j
| |
| | |
| t k ,
| |
| Emergency- Plan Implementing Instruction - EP-1-040 General Emergency Revision 3 5.5.9. U.S. Coast Guard - as necessary l 5.5.10 Missouri Pacific Railroad - as necessary
| |
| : 5 '. 5 ~.11' American Nuclear Insurers (ANI) - as necessary
| |
| -5.6 As' additional information becomes available, update the Emergency Communicator by completing Attachment 7.7,- Follow-Up Notification, of.EP-2-010. Direct the Emergency Communicator to conduct additional _
| |
| updates to off-site agencies in accordance with EP-2-010.
| |
| 5.7 Initiate off-site dose assessment in accordance with EP-2-050 for
| |
| -manual assessment or EP-2-051 for computerized assessment.
| |
| Determine protective action recommendations in accordance' with EP-2-052', Prctective Action-Guidelines.
| |
| 5.8 If. radiological' releases are occurring or anticipated instruct the 3 Health Phy' sics Coordinator to activate Radiological Field Monitoring Teams in accordance with EP-2-130 and EP-2-060.
| |
| 5.9 Initiate activation of-the Technical Support Center in accordance with l EP-2-100, if not previously activated.
| |
| 5.10 Initiate activation of_the Operational Support Center in accordance with l EP-2-101,if not previously activated.
| |
| 5.11 Initiate activation of the Emergency Operations Facility in accordance l with EP-2-102, if not.previously activated.
| |
| '5=.12 Ensure-that emergency logs / records are kept in accordance with EP-2-150.
| |
| 6
| |
| | |
| b .
| |
| b s
| |
| q ~
| |
| Emergency'P1an' Implementing Instruction EP-1-040 General Emergency Revision 3 5.13 Direct the Health Physics Coordinator and/or the Radiological Controls Coordinator to initiate in-plant radiological controls in accordance with-EP-2-031 if a real or potential radiological hazard exists-and to perform on-site surveys as necessary in accordance with EP-2-034.
| |
| 5.14 Initiate any additional' response measures.in accordance with emergency procedures listed in' Attachment 7.1.
| |
| 5.15 As-conditions' change, periodically check EP-1-001 to determine whether reclassification is necessary.
| |
| 5.15'.1 If reclassification is necessary, then reclassify the emergency in accordance with EP-1-001 and implement appropriate Implementing Instruction EP-1-010, EP-1-020., or EP-1-030.
| |
| 15 . 1 5 . 2. If closecut is appropriate, then close out the emergency with a verbal summary to all agencies / personnel as indicated on Attachment 7.13 of EP-2-010 and implement EP-2-170 to initiate recovery activities.
| |
| 6.0 FINAL CONDITIONS ,-
| |
| 6.1 ~The General Emergency has been closed out with' normal station administration resumed and recovery activities initiated in accordance with EP-2-170 or the emergency reclassified.
| |
| 7.0 ATTACHMENTS 7.1 Procedure References'for' Additional Response Guidelines.
| |
| 7
| |
| - . _ - - - _ - . - _ . _ _ _ _ - _ _ - - - . - . _ - _ _ - _ - - - - - _ _ - - . - - - - _ _ - - - - - - - _ - . ~ - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - - -
| |
| | |
| L PROCEDURE REFERENCES FOR ADDIT.IONAL RESPONSE GUIDELISES Topic References Personnel EP-2-020, Contaminated Injured /lll Personnel EP-2-030, Emergency Radiation Exposure Guidelines and Controls EP-2-032, Monitoring and Decontamination _
| |
| EP-2-033, Administration of Iodine Blocking Agents EP-2-071, Site Protective Measures EP-2-081, Search and Rescue Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentry EP-2-170, Recovery Emergency Management Resources Book l I:
| |
| . =~ ,
| |
| ' EP-1-040 Revision 3 8 Attachment 7.1 (1 of 1)
| |
| | |
| WATERFORD 3 SES N PLANT OPERATING MANUAL "M LQUISIANA POWER & LIGHT b
| |
| POM VOLUME 3o EP-2-010 POM.SECTION 7 REVISION q Emergency Plan I=plementing Procedures Notification and Communication LP&L W-3 RECORDS -
| |
| UNCONTROLLED DO i4or USE IN ANY SAFETY-RELATED TESTING, COPY MAINTENANCE, OR OPERATIONAL ACTIVITY P0RC Meeting No. 83-52A Reviewed: M/I M//w PORC Qhairman Approved: L L /
| |
| Plant Manager-Nuclear Approval Date Fuel Load Effective Date
| |
| | |
| ~
| |
| WATERFORD 3 SE3 PLA3T OPF. RATING MANUAL ,
| |
| CHANGE /RE7ISICN/DCLETION REQUE3T .
| |
| Procedure No. 5Y l**
| |
| * Titie n' J d V- .- A D '-- ~ < ...
| |
| Effective Date E U- L~* (if different from approval date) t h at at.m A. R. er C A. Change No. N B. Revision No. T
| |
| * C. Deletion. *N anSDE FOR CHAEGE. RETISIDE. OR DE1. M ON I T, w. . o. k. C. . ~ , . . n. -. - I . M . .~.. d--A
| |
| [^ 7 U ^ h anunrn sram1 Tutus .
| |
| Originator b* *- Date / 2/ 1'75 Tcchnical' Review M8 EMU Date M?r83 SAFETT ETALBATION Does this change, revision,'or deletion: '
| |
| TES NO
| |
| ~1. Change the faeility as described it the F3AR7
| |
| : 2. Change the procedores as desoribed in the F3AR7- '
| |
| : 3. Conduet testa / experiments not described in the FSAR7 _
| |
| .4 Create.a condition or conduct an operation which ex- i'
| |
| , seeds, or could result in exceeding, the limits in Technical Specificationa?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
| |
| Safety' Evaluation M# hMe~/ Date / 7O Group /Dep't. Need Reviewc Y d Date /Y23M Temporary Approval
| |
| * Date (NO3)
| |
| Temporary Approvals Date QC Review A4 +8M- Date ':
| |
| - S' -
| |
| PORC Review # / M280 -- =
| |
| Plant Manager-Nuclear Approval Date /- 8 -P[ Meeting No.
| |
| Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UMT-1-003 Revision 6' Attachment 6.9 (1 of 1)
| |
| : 7. G
| |
| | |
| p.
| |
| p _ .
| |
| Emergency Plan implementing Procedure EP-2-010 Notifications and Communications Revision 5 TABLE ^F CONTENTS 1.0 PURPOSE 2.0 REFERL .CES 3.0 RESPONSIBILITIES 6.0 INITIATING CONDITIONS 5.0 PROCEDURE -
| |
| 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Operation'of the Answering Machines 12 pages) 7.2 Activaticn of the Emergency Response Organization (2 pages) 7.3 ~ Answering Machine Message (1 page) 7.4.. Initial Notification Procedure (5 pages)
| |
| .7.5 Part I'- Initial Notification for State, Parish and Secondary Agencies; Part II - NRC Operations Center. Event Notification Form (3 pages) 7.6 Follow-Up Notification Procedure (5 pages) 7.7 Part.I - Follow-Up Notification for State, Parish and Secondary Agencies; Part II - NRC Supplementary Event Notification Information (5 pages) 7 '. 8 Request for Offsite Assistance (4 pages) 7.9 Control Room Checklist for Transferring Communications
| |
| , Responsibilities to the TSC (1 page) 7.10 TSC Checklist for Accepting- Responsibility for Communications Systems from the Control Room (1 page) 7.11 TSC-(EOF) Checklist for Transferring Communications Responsibilities to the EOF (TSC) (1 page) 7.12' EOF Checklist for. Accepting Communications Responsibilities from
| |
| -the TSC-(1 page) 7.~13 Notification Checklist (1 page)
| |
| -7.14 Emergency Response Verification (1 page) 1
| |
| | |
| Emergency Plan Implementing Procedure EP-2-010 Notifications and Communications Revision 5 LIST OF EFFECTIVE PAGES Title Revision 5 1-6, 9, 10, 12-16, 20-24 Revision 5 30-34, 36, 39, 40 Revision'S ;
| |
| 7, 8, 11, 17-19, 25-29, Revision 4 35, 37, 38 Revision 4 LIST OF PAGES CONTAINING PROPRIETARY OR PRIVATE INFORMATION 7
| |
| 13 14 15 18 21 23 24 27 30 31 32 33 2
| |
| | |
| l
| |
| . Emergency' Plan Implementing Procedure EP-2-010 Notifications and Communications Revision 5 1.0 PURPOSE This procedure provides guidance for making notifications duri.'g an emergency and outlines the methods for activating the LP&L Emergency 9
| |
| Response Organization.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 Waterford 3 SES Emergency Plan 2.2 State of Iauisiana Peacetime Radiological Response Plan 23 EP-2-iOO, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.4 EP-2-150, Emergency Plan Implementing Records 2.5 Emergency Management Resources Book l 2.6 EP-3-060, Emergency Communications Guidelines 2.7 EP-3-070, Er.ergency Communications Systems Routine Testing 3.0 RESPONSIBILITIES The Emergency Communicator, TSC Lead Communicator aad/or the EOF Communications Coordinator is responsible for carrying out the actions outlined in this procedure.
| |
| 4.0 INITIATING CONDITIONG This procedure is to be initiated upon any of the following conditions:
| |
| 4.1 .At the direction of the Emergency Coordinator 4.2 Declaration of any of the following emergency conditions:
| |
| .4.2.1 Unusual Event 4.2.2 Alert _,
| |
| 4.2.3 Site Area Emergency 3
| |
| | |
| $ +$ b+
| |
| i k IMAGE EVALUATION
| |
| ////pNT g)y s$%f/
| |
| TEST TARGET (MT-3) g?g[+9 4
| |
| 6+f %,g,sy, 1.0 l#NaI!at
| |
| [ll Na i,i !5: lillu l.8 l.25 I.4 1.6 4 150mm >
| |
| < 6" >
| |
| 4 *' e+
| |
| *Stf 4/// Nt3%'b[
| |
| v
| |
| | |
| ~
| |
| 4# v@
| |
| k@ / IMAGE EVALUATION ///jg/f I 0f *#
| |
| g ,377s; c/ +4, r TEST TARGET (MT-3) Ts
| |
| %'U
| |
| + + %4 %
| |
| l.0 lgm an 1
| |
| y ll EE l.1 k.*
| |
| p8 1.25 1.4 1.6
| |
| < 150mm *
| |
| < 6" #
| |
| g,,
| |
| ~
| |
| / 4%
| |
| *%y>p/////
| |
| o
| |
| 'Q<%
| |
| s-
| |
| | |
| /
| |
| E;nergency Plan I:nplementing Procedure EP-2-010 .
| |
| Notifications and Connunications Refrision 5 4.2.4 General Emergency 5.0 PROCEDURE 5.1 INITIAL NOTIFICATIONS BY THE ON-SITE ORGANIZAITON 5.1.1 Activation and Notification of the Emergency Response Organization.
| |
| NOTE If conditions exist that could be hazard-ous to those personnel reporting to the
| |
| , site, provide instructions for personnel
| |
| . protection (alternate routes, etc.).
| |
| 5.1.1.1 Place the answering machines in operation in accordance with Attachment 7.1; 5.1.1.2 Activate and notify the Emergency Response Organization (for Alert, Site Area Emergency or General Emergency) in accordance with Attachment 7.2, Section 1.0.
| |
| NOTE
| |
| : 1. Activation of additional personnel to support the Operational Support Center (OSC) or engineering support activities will be directed ,
| |
| by the OSC Supervisor, if required.
| |
| 4 e , , - - e g - r +
| |
| -, -,,-. ., ,,, - . - - ----,n-.,..,g. . , , , , , , - ,,,,ee, e,,w n-,,r-,,.n.m, e----,e .,,w - - - . -
| |
| | |
| Emergency Plan Implementing Procedure EP-2-010 Notificacions and Communications Revision 5
| |
| : 2. Activation o t Emergency Operations Facility (EOF) personnel will be accomplished by the EOF Director.
| |
| : 3. Activation of Corporate Command Center personnel will be accomplished by the -
| |
| Emergency Director.
| |
| 5.1.2 Conduct initial off-site notifications in accordance with Attachment 7.4 and update Attachment 7.13, Notification Checklist.
| |
| 5.1.3 Upon completion of the initial off-site notifications, verify the Emergency Response Organizaiton activation accordin3 to
| |
| -Attachment 7.2, sections 2.0,.3.0 and 4.0.
| |
| t 5.1.4 Continue to update off-site agencies / personnel in accordance with Attachment 7.6, Follow-Up Notification Procedure, and update Attachment 7.13, Notification Checklist.
| |
| 5.1.5 When directei, make requests for off-sit; assistance according to Attachmant 7.8, Request for Offsite Assistance.
| |
| 5.2 The Control Room Emergency Coordinator shall transfer communications l to the TS'C Lead Communicator in accordance with Attachment 7.9.
| |
| I 5.3 The TSC Lead Communicator shall accept responsibility for ccmmunications in accordance with Attachment 7.10.
| |
| 5.4 The- TSC Lead Communicator and/or EOF Communications Coordinator shall transfer communications responsibility in accordance with Attachment 7.11.
| |
| l 5.5 The EOF Communications Coordinator shall accept responsibility for communications in accordance with Attachment 7.12.
| |
| 5
| |
| | |
| . . . ~
| |
| Emergency Plan Implementing Procedure EP-2-010
| |
| ' Notifications and Communications ReNision5 5.6 Maintain communications records in accordance with EP-2-150.
| |
| 6.0 -FINAL CONDITIONS Use of this procedure shall be terminated at the time of TSC deactivation or when directed by the Emergency Coordinator. ;
| |
| 7.0 ATTAClDIENTS 7.1 Operation of the Answering Machines 7.2 Activaiton of the Emergency Response Organization 7.3 Answering Machine Message 7.4 Initial Notification Procedure 7.5 ' Part I - Initial Notificaiton -for State, Parish and Secondary Agencies; Part II--- NRC Operations-Center Event Notification Form 7.6 Follow-Up Notification Procedure 7.7 Part I - Follow-Up Notification for State, Parish and Secondary Agencies; Part II - NRC Supplementary Event Notification Information 7.8 -Request'for Offsite Assistance 7.9 Control Room Checklist for Transferring Communications Responsibilities to the TSC 7.10 TSC Checklist for Accepting Responsibility for Communications Systems from the Control Room 7.11 TSC (EOF) Checklist for Transferring Communications Responsibilities to the EOF (TSC)'
| |
| 7.12 EOF Checklist for Accepting Communications Responsibilities from the TSC 7.13 Notification Checklist 7.14 Emergency Response Verification 6
| |
| | |
| OPERATION OF THE ANSWERING MACHINES
| |
| : 1) The answering machines are normally in the " Announcement only" mode.
| |
| To change functions: .
| |
| Press MODE Press STOP
| |
| : 2) To install or remove outgoing or Incoming Cassettes:
| |
| Full down the EJECT lever
| |
| : 3) To deliver a message and record incoming calls: -2 Install the appropriate cassette ,
| |
| Press STOP k Press ANSWER
| |
| : 4) To verify correct information:
| |
| Call C ] and listen for the correct message and tone
| |
| : 5) To play'back incoming messages: =,
| |
| l Press STOP Press REWIND l Press PLATBACK
| |
| : 6) To record new messages:
| |
| l Install the appropriate cassette Press STOP Press RECORD (a tone will sound)
| |
| Speak into the microphone Press STOP (the message will automatically replay) l l
| |
| THE MATERIAL CONTAINED WITHIN THE SYMBOLS ( } IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| e i
| |
| EP-2-010 Revision 4 7 Attachment 7 1 ( 1of 2)
| |
| | |
| OPERATION OF THE ANSWERING MACHINES NOTE Refer to EP-3-070, Emergency Communications Systems Routine Testing, Attachment 7 4, for
| |
| ~
| |
| details not covered by this attachment.
| |
| l I
| |
| l l
| |
| l 1
| |
| EP-2-010 Revision 4 a . Attachment 71 ( 2 of 2)
| |
| | |
| ACTIVATION OF THE EMERGENCY RESPONSE ORGANIZAITON 1.0 ACTIVATING THE EMERGENCY PAGER SYSTEM Activate the Emergency Response Organization in accordance with the Emergency Management Resources Book. l 2.0 VERIFYING RESPONSE 2.1 To verify response to the pager system:
| |
| 2.1.1 Press PLAYBACK and machines will automatically rewind and play back called-in messages. ,
| |
| NOTE Any calls received while in the PLAYBACK mode must be answered and logged manually.
| |
| -2.1.2 When-the machine starts playing back the message, the display will show for each message the following:
| |
| Message number Date of call Time of call 2.1.3 Record the responders on Attachment 7.14.
| |
| l 2.1.4 The answering machine will automatically stop after the last message has been played.
| |
| 2.1.5 Press ANSWER to start receiving calls after listening to the last message.
| |
| 2.1.6 To erase all messages previously received, press REWIND ERASE and l ,
| |
| i then press REWIND.
| |
| EP-2-010 Revision 5 9 Attachment 7.2 (1 of 2)
| |
| | |
| ACTIVATION OF T'4E ?.NERGENCY RESPONSE ORGANIZATION 3.0 BACKUP METHOD FOR ACTIVATING THE EMERGENCY RESPONSE ORGANIZATION 3.1 ~Using the Emergency Management Resources Book, attempt to contact the individals in the Emergency Response Organization via telephone.
| |
| Upon reaching them, announce:
| |
| WE HAVE DECLARED AN/A EMERGENCY AI WATERFORD 3.
| |
| (Alert, Site Area, General)
| |
| YOUR Il9fEDIATE RESPONSE TO THE SITE IS REQUIRED. WHAT IS YOUR ANTICIPATED ARRIVAL TIME?
| |
| Do not engage in a discussion of the situation with the iddividual.
| |
| If questions'arise, inform the individual he/she will be briefed upon arrival en site, 4.0 UPDATING THE EMERGENCY COORDINATOR 4.1 Provide' Attachment 7.14, Emergency Response Verification, to the Emergency Coordinator.
| |
| 5 4.2 Request the names of personnel to substitute for those not contacted.
| |
| 4 Once names have been provided, contact personnel via telephone and repeat the message in step 3.1 above.
| |
| EP-2-010 Revision 5 10 Attachment '.2 (2 of 2)
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| | |
| ANSWERING MACHINE MESSAGE
| |
| : 1. Completa the following message and provide to the Emergency Com-municator: .
| |
| AN (Unusual Event, Alert, Site Area cr General) EMERGENCY HAS SEEN DECLARED A".
| |
| WATERFORD 3 DUE TO ,
| |
| _d YOUR IMMEDIATE RESPONSE TO THE SITE IS REQUIRED. AFTER THE SOUND 0. THE-FOLLOWING TONE, LEAVE YOUR NAME, ANTICIPATED ARRIV AL TIME AND TITLE OF 1-EMERGENCY POSITION AT THE END OF THIS MESSAGE.
| |
| l l
| |
| I?-2-010 Revision 4 11 Attacr.mant 7,3 (1 of i; .
| |
| | |
| INITIAL NOTIFICATION PROCEDURE 1.0 Receive from the Emergency Coordinator a completed Attachment 7.5, Part I - Initial Notification for State, Parish and Secondary Agencies.
| |
| 2.0 Perform initial notifications to St. Charles Parish EOC, St. John the Baptist Parish EOC, Louisiana Nuclear Energy Division (LNED) and Louisiana Office of Emergency Preparedness (L0EP) via the Operational Hotline.
| |
| 2.1 Lift the Operational Hotline receiver and push the ring button.
| |
| 2.2 'As each agency representative identifies himself, resp,ond'*with WATERFORD 3 STEAM ELECTRIC STATION - STAND BY and note the title of the agency responding.
| |
| 2.3 After all agencies have identified themselves or two minutes have elapsed, make the following statement:
| |
| THIS IS AT THE WATERFORD 3 STEAM ELECTRIC STATION.
| |
| (name/ title)
| |
| THE FOLLOWING IS A NOTIFICATION OF AN EMERGENCY. OBTAIN A COPY OF THE PART I - INITIAL NOTIFICATION FOR STATE, PARISH AND SECONDARY AGENCIES FORM AND STAND BY TO RECORD INFORMATION.
| |
| ; Allow a few moments for the agencies' representatives to obtain the i
| |
| I form.
| |
| l 2.4 Read information on the initial notification form one line at a time and allow agency representatives time to fill in their forms.
| |
| NOTE
| |
| ',, Do not supply any information not listed on the form. Inform agency representatives that more information will be forthcoming.
| |
| EP-2-010 Revision 5 12 Attachment 7.4 (1 of 5)
| |
| | |
| INITIAL NOTIFICATION PROCEDLTE 2.5 After the agencies on the Operational Hotline have recorded the information on the initial notification form, contact any of the agencies listed that did not respond when the hotline was activated.
| |
| 2.5.1 Dial the phone numer of the appropriate agency and perform steps 2.3 and 2.4 above.
| |
| 2.5.1.1 St. Charles Parish EOC 2.5.1.2 St. John the Baptist Parish EOC 2.5.1.3 Louisiana Nuclear Energy Division (LUED) - Caergency Preparedness -
| |
| 2.5.1.4 Louisiana Office of Emergency Preparedness (LOEP) -
| |
| Communications Office 2.5.2 If contact cannot be made by dialing the appropriate agency's phone number, then activate the State Civil Defense radio transmitter and repeat steps 2.3 and 2.4 above.
| |
| NOTE LNED does-not have the State Civil Defense radio.
| |
| Request LOEP to contact LNED if the' State Civil Defense radio is used.
| |
| ( 2.5.3 Ensure that the TSC Lead Communicator / Communications Coordinator receives verification of transmittal.
| |
| 2.5.4 TSC Lead Communicator / Communications Coordinator notifies the l
| |
| Emergency Coordinator / EOF Director or verification of transmittal.
| |
| 2.6 Update Attachment 7.13, Notification Checklist.
| |
| 2.7 Waterford 1 and 2 SES will be notified using one of the following l
| |
| methods:
| |
| LP&L Emergency Telephone, dial l PABX or 1
| |
| 2.7.1 When Waterford 1 and 2 come on the line, repreat the information on the initial notification form. _ , _
| |
| THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE
| |
| 'INFORMAITON.
| |
| EP-2-010 Revision 5 13 Attachment 7.4 (2 of 5)
| |
| | |
| INITIAL NOTIFICATION PROCEDURE 3.0 NOTIFICATION VIA THE NRC EMERGENCY NOTIFICATION SYSTEM NOTE Communications with the NRC cay be con-tinuously maintained.
| |
| 3.1 Lift the receiver for the NRC Emergency Notification System phone.
| |
| Once a response is obtained, make the following statement: _-
| |
| THIS IS AT THE LP&L WATERFORD 3 STEAM ELECTRIC STATION. (Name/ Title)
| |
| THE FOLLOWING IS A NOTIF.ICATION OF AN EMERGENCY. ,
| |
| 3.2' Provide the NRC representative with the information written on the initial notification form, Part II - NRC Operations Center Event Notification Form. ,
| |
| NOTE Do not supply any information not listed on the form or answer any other questions which may be posed to you. Should the representative need additional information, contact the Emergency Coordinator and have him discuss the situation with the representative.
| |
| : 3. 2.1 -' If.the NRC Emergency Notification System (ENS) is not operational, contact the NRC by the following method:
| |
| i
| |
| : 1. Commercial telephone
| |
| : l. 2. Health Physics network l
| |
| l-3.3 Update Attachment 7.13, Notification Checklist.
| |
| .THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| EP-2-010 Revision 5 14 Attachment 7.4 (3 of 5)*
| |
| _ _ _ , ,_~
| |
| | |
| INITIAL NOTIFICATION PROCEDURE 3.4 .If relieved by an NRC Representative, continue with conununications
| |
| -duties.
| |
| 4.0 SECONDARY NOTIFICATION 4.1 The fallowing notifications will be performed after the initial notifications:
| |
| 4.1.1 Middle South Utilities, Refer to the Emergency llanagement Resources Book 4.1.2 Institute of Nuclear Power Operations (INPO), Atlanta, GA, or l 4.2 Secondary notifications will be made at the direction of the Emergency Coordinator or the Emergency Operations Facility Director.
| |
| 4.2.1 U. S., Coast Guard -
| |
| 4.2.2 Missouri Pacific Railroad, between 0700-2300, hours, If no answer, call 4.2.3 American Nuclear Insurers (ANI), Farmington, CT -
| |
| 5.0 VERIFICATION CALL l
| |
| NOTE If St. Charles Parish EOC, St. John the Baptist Parish EOC, the LNED or LOEP is j notified via any method other than the Opera-I tional Hotline, then a verification call is i
| |
| required. Record required information below.
| |
| I i
| |
| THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| EP-2-010 Revision 5 15 Attachment 7.4 (4 of 5)
| |
| | |
| INITIAL NOTIFICAIION PROCEDURE 5.1 Record agencies making verification calls.
| |
| 5.1.1 St. Charles Parish EOC (time /name) 5.1.2 St. John the Baptist Parish EOC (time /name) -
| |
| 5.1.3 Louisiana Nuclear Energy Division (time /name) 5.1.4 ' Louisiana Office.of Emergency Preparedness
| |
| ! (time /name) i .
| |
| l l
| |
| l .
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| 4 i
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| l l
| |
| I l .
| |
| l' l EP-2-010 Revision 5 16 Attachment 7.4 (5 of 5)
| |
| L . . ._ _ _ . _ _ _ _ , _ .
| |
| | |
| ( .
| |
| ? m I: nTIT.91 >UJIFIC u!CT K 2 Sr L , ? B ISH AND SICorARY .'-ca C IS kw mr 1 mis is with Massage No. , at hrs.,
| |
| (Name) (Time)
| |
| '2 cn with Telephone No. t l (Data) (site) i
| |
| !3 Events are such that a/an: N ='*1 Event Sits Area Bergency ,
| |
| 4 Alert Gecaral margerry .
| |
| ,5- *e declared at hrs. .,
| |
| l 6, Brief' Mptica of event (s): '
| |
| 7 8
| |
| l "3E FCILCHIM DH!t1HL.ECN APPLI5:
| |
| 9_ Release ,
| |
| m 10- E S - Liquid; Gacecus; Cther .
| |
| ~
| |
| 11 Wini Speed :rph 12 WLad Direction frcm in'w Secter(s) .
| |
| : l. (%w) (A-R) l 13 Pacennerzi Protective Ac. ices: 1c ne l14 ,
| |
| Shalter -
| |
| l15 other .
| |
| i l6 "
| |
| l l A c:mprehensive assessaant of conditions is in progress at this time.
| |
| Addi*h information will be providad to ycu as the situation develepa.
| |
| N CCCRDINA M / N l -
| |
| ECM & N .EN AS *.M MCN IS m. ,
| |
| T.NID St. Charles ECC 1 l
| |
| ; I4EP St. Jchn ICC [
| |
| t l
| |
| CE E4ANSd.IN VERIZICACCN - CO 012IICA3'S SIG A72 2P-2-010 F.avisien 4 g Attachcanc 7.5 (1 cf 3)
| |
| | |
| FR_".BRY kWCCCN 7GEC S M ARY IL'*D'IC C OI 2CD C St. Charles ECC _
| |
| A carford 1&2 St. Jcho Z:"O CS Coast Cwd
| |
| ~
| |
| Ia. Ex: lear Energy Missouri Pacific BR __
| |
| Ia. Offica anarce::c't Middle Scuth Utilities -
| |
| Preparedness ANI -
| |
| INPO -
| |
| ; ~
| |
| s l
| |
| l I
| |
| l i
| |
| l l
| |
| l UE MAT!! RIAL CC#'4INED WI'5IN HE SZMBOLS ( } IS PRCERIED2Y CR
| |
| [ PRr/ ATE INFCRMAECN. ',,
| |
| EP-2-010 Feiisien 4 18 Attac=mnt 7.3 (2 cf 3) -
| |
| l .
| |
| | |
| PART II - }EC CPERACCNS CIS E7DE WlC:?ICASCN ?CFM
| |
| ,"ME CF lunra..ATION L'DE EME MD IONE: ERC REGION: CACE: / /
| |
| 1T CAT.L S;CK 2CSER: M D Y
| |
| #CILIrf CR CPGWIZATICN: CAT.J.JP.'S 22 Et1DE C:AS: uric'ICN:
| |
| t J.. 50.72 (NDE BERGDCC) ,,
| |
| : 2. CNPIARGED RELEASE -
| |
| : 3. ICTIFICATIC3i G GESUAL E7DE ,
| |
| : 4. ALERT ,
| |
| : 5. SITE ARER DEEGDCf
| |
| : 6. GDERAL DEEGECf - -
| |
| : 7. 1RANSiGEATICN EniNT .,
| |
| s
| |
| : 8. PHYSICAL SICCRITY/SAF33CARCS
| |
| : 9. OMER ;
| |
| OGIR RDCICR EZfm':
| |
| Ch'dR PRICR TO Stair? PCWER AT TI24E G REPCR'" RESIDENT DECSMED RIP 7 __
| |
| INITIATDG SIGE7 EFETY DUECTICN CR ICCS7 INITIAUN3 SIGAL7 -
| |
| BF SCICATION?
| |
| ID #CTICN STP EDENr?
| |
| I R E Cr L & dCN/C:ESE:
| |
| 1 1
| |
| RADIOiCSJE IGi2JiASES? (CtAVIITT): _
| |
| 7IEIR NCR PRCSIJMS7 t _
| |
| PIMWm K'f'TCNS/ ppm R]iI.:iASES?
| |
| .A.rm vE N CR F:.RSCREL DUTIFI:iD 3Y LICalSEE: STATE (S) LCCE ,
| |
| M ,
| |
| ~
| |
| 1
| |
| %TY CN -
| |
| / :
| |
| EMEISDC CCCPIDATCR'S SIGa?2S/E:E ,
| |
| /
| |
| C4E ':3ANS.T.N VE.RIFIED/D!ERGEC COMM.2ECA".C4'S SIQTC3E t
| |
| l l
| |
| EP-2-012 Retisicn 4 19 At ac::::en- 7.3 (3 Of 2:
| |
| . - - . - - , . . _ , . -. . , - . . . . , , , , , _ . , _ , _ , _ _ . _ _ , _ , , _ _ _ _ , _ , , _ _ , , _ , , , , , . _ _ _ , . , . , , _ _ . ,,_ , _ _ , _ _ .____,_,__.____,_y __ _, _ . . _ _ , . , ,
| |
| | |
| FOLLOW-UP NOTIFICATION PROCEDURE i .
| |
| : 1.0 Receive from the Emergency Coordinator a completed Attachment 7.7, Follow-Up Notification for State, Parish and Secondary Agencies.
| |
| NOTE Notify only the appropriate personnel / agencies of conditions that change.
| |
| 2.0 Renotify St. Charles Parish EOC, St. John the Baptist Parish E'0C, Louisiana Nuclear Energy Division (LNED) and Louisiana Office of Emergency Preparedness (LOEP) via the Operational Hotline.
| |
| 2.1 lift the Operational Hotline receiver and push the ring button.
| |
| 2.2 As each agency representative identifies himself, respond with WATERFORD 3 STEAM ELECTRIC STATION: STAND BY and note the title of the agency responding.
| |
| 2.3 After all agencies have identified themselves, or two minutes have elapsed, make the following statement:
| |
| [ THIS IS AT THE WATERFORD 3 NUCLEAR POWER STATION.
| |
| l (name/ title)
| |
| THE FOLLOWING IS A SUBSEQUENT NOFTIFICATION OF AN EMERGENCY AT WATERFORD 3. OBTAIN A COPY OF THE FOLLOW-UP NOTIFICATION (TAB 3 TO ATTACHMENT 1 0F THE STATE OF LOUISIANA PEACETIME RADIOLOGICAL RESPONSE PLAN) AND STAND BY TO RECORD INFORMATION.
| |
| L Allow a few moments for the agencies' representatives to obtain the checklist.
| |
| l l 2.4 Read information on the Follow-Up Notification one line at a time and allow agency representatives time to fill in their forms.
| |
| 2.5 After agencies have recorded the information on the Follow-Up Notification, contact any of the agencies listed that did not respond when the hotline was activated.
| |
| l EP-2-010 Revision 5 20 Attachment 7.6 (1 of 5)
| |
| L
| |
| | |
| FOLLOW-UP NOTIFICATION PROCEDURE 2.5.1 Dial the appropriate agency's phone number ~and perform steps 2.3 and 2.4 above.
| |
| ~2.5.1.1 St. Charles Parish EOC 2.5.1.2 St. John the Baptist Parish EOC. ___
| |
| 2.5.1.3 Louisiana Nuclear Energy Division (LNED) - Emergency Preparedness 2.5.1.4 Louisiana Office of Emergency Preparedness (L0EP) -
| |
| Constnications Office .
| |
| 2.5.2 If contact cannot be made by dialing the appropriate agency's phone number, then activate the State Civil Defense radio transmitter and repeat steps 2.3 and 2.4 above.
| |
| NOTE LNED does not have the State Civil Defense Radio.
| |
| Request LOEP to contact LNED if.the State Civil l' Defense Radio is used.
| |
| 2.5.3 Ensure that the TSC Lead Communicator / Communications Coordinator receives verification of trnasmittal.
| |
| 2.5.4 TSC Lead Communicator / Communications Coordinator notifies the Emergency Coordinator / EOF Director of verification of transmittal.
| |
| 2.6 Update Attachment 7.13, Notification Checklist.
| |
| 2.7 Waterford 1 and 2 SES will.be notified using one of the following methods:
| |
| LP&L Emergency Telephone, dial PABX THE MATERIAL CONTAINED WITHIN THE SYMBOLS ( ) IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| EP-2-010 Revision 5 21 Attachment 7.6 (2 of 5)
| |
| | |
| FOLLOW-UP NOTIFICATION PROCEDURE 2.7.1 When Waterford 1 and 2 come on the line, deliver the following message:
| |
| THIS IS AT THE WATERFORD 3 STEAM ELECTRIC (name/ title)
| |
| ! STATION. WE HAVE DECLARED A(N) AT (emergency classification)
| |
| HOURS. WE HAD A RADIOACTIVE RELEASE.
| |
| (time) -(have/have not) _
| |
| (Provide a brief description of the event) -
| |
| WATERFORD 3 SES REQUESTS THAT (Protective actions, assistance, etc.)
| |
| 3.0 NUCTEAR REGULATORY C0t91ISSIO'N (NRC) VIA NRC EMERGENCY NOTIFICATION SYSTEM (ENS)
| |
| NOTE Communications with the NRC may be continuously maintained.
| |
| 3.1 -Lift the receiver for the NRC Emergency Notification System phone.
| |
| Once a response is obtained, make the following statement:
| |
| l THIS IS AT THE LP&L WATERFORD 3 STEAM ELECTRIC (name/ title)
| |
| STATION. THE FOLLOWING IS AN UPDATE OF INFORMATION REGARDING OUR l DECLARED EMERGENCY.
| |
| 3.2 Provide the NRC representative with the information written on the NRC
| |
| ( Supplementary Event Notification Information Form.
| |
| l-I l
| |
| I EP-2-010 Revision 5 22 Attachment 7.6 (3 of 5)
| |
| | |
| FOLLOW-UP NOTIFICATION PROCEDURE NOTE Do not supply any information not listed on the form or answer any other quesitons which may be posed to you. Should the representrtive need additional information, contact the Emergency Coordinator and have him discuss the situation with the representative. .
| |
| 3.2.1 If the NRC Emergency Notification System (ENS) is not operational, contact the NRC by the following method:
| |
| : 1) Commercial telephone,
| |
| : 2) Health' Physics Network
| |
| ~
| |
| 3.3 Ensure that the Emergency Coordinator receives. verification of transmittal.
| |
| 3.4 Update Attachment 7.13, Notification Checklist.
| |
| 3.5 If relieved by an NRC Representative, continue with communications duties. r THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| EP-2-010 Revision 5 23 Attachment 7.6 (4 of 5)
| |
| | |
| 4 FOLLOW-UP NOTIFICAT, ION PROCEDURE 4.0 SECONDARY NOTIFICATIONS
| |
| - 4.1 The- following notifications will be performed after the followup notification:
| |
| These notifications are only required at an emergency classification or change of classification or at the direction of the Emergency Coordinator / EOF Director.
| |
| 4.1.1 Middle South Utilities,.(Refer to the Emergency Management Resources Book).
| |
| 4.1.2 Institute of Nuclear Power Operations (INPO), Atlanta, Ga.
| |
| 4.2-' Secondary followup notifications will be made at the direction of
| |
| 'the Emergency Coordinator or the 50F' Director.
| |
| 4.2.1 U. S. Coast Guard -
| |
| ! 4.2.2 Missouri Pacific Railroad - between 0700-2300 hours -
| |
| i j If no answer call -
| |
| 4.2.3 American Nuclear Insurers (ANI), Farmington, CT -
| |
| l i
| |
| l I
| |
| EP-2-010 Revision 5 24 Attachment 7.6 (5 of 5)
| |
| | |
| 6 ,
| |
| FMc I: Fr**%3P k'n.:iCCN FCR STA"", P.3F" M MEN an.
| |
| 3 seer .
| |
| 1 1 bis is _ with Massace No. , at hrs., -
| |
| (Name) (Time) -
| |
| t 2 cm with Telephone No. 464-(Data) (Si*J) .
| |
| 3 ,
| |
| monts are such that a/an: Causual ment sita A:ea marrgenef .
| |
| 4 Alert Gereral I=argeccf T.
| |
| 5 *as d!aclarsi at
| |
| . hrs.
| |
| This classification is (Escalatai, co-escalatad, Ucena:ged, T*t:sinacsi) f rc:n e.e '
| |
| last p .
| |
| 5 Raasen for :=-12==4 *ication:
| |
| * i 7
| |
| , 8 EE ECLI4NEG DECR%TICN APPfl25:
| |
| 9 -- , " a As Radiolcnical' Release Infcrmatica N/A l10 This information is: A) New Infoczatica B) Ce*W 11 (1) Type of ?=34al @ 1 Release: Liquid, e.a - a: Cther 12 (2) Ttna of Reactor Shutdcwn: hrs.
| |
| i 13 (3) Initial Time of Release hrs.
| |
| ' 14 (4) Release Tarninted: 20; Y25 II.T TUL 6 T!D hrs.
| |
| 15 (5) Duration of Release: EDN cr TCTIAL PRw-r_m (bcurs) (hcurs) -
| |
| 16 (6) Release Rate: Nchle Gas Ci/sec M:nitored; e=1mtated 17 Iciina C1/sa: M::nitored; Calcalated 13 Particulate Ci/sec Mcni" h ; e=1 m1= cad 19 (7) Release 21evation: Grcund Level: Elevated 20 (8) L=*4 =** cf Surface F**ation In-Plant, Cnsita, er Cffsite:
| |
| 21 22 e rH 3: Meterelcav N/A 23 This informat2.cn is: A) New infct:Datien B) Uncm g ed 2 24 (1) Wind: Speed mph 25 Dirac-den '. ::m into Secter(s) -
| |
| (cegrees) (A-R) ~
| |
| 25 (2) Stabilief Cisss: A B C D E F G 27 (3) Precipitaticn: Tc.e; Fain; <iaat; Sncw; Eail IP-2-010- F.eiisic 4 25 At- m 7. d 5)
| |
| . . . . . _ ~ . , . _ , _ . . , , , , . , , , . , _ , _ . . _ , . . , . - - , . , _ ,
| |
| | |
| i l
| |
| l i
| |
| I "s
| |
| . l u::tur ECrl.C.H.1? 2CT.IFICATICN - Page 2 1
| |
| 1 1 SECTIci C: CSsits P2diclcde:2.1 Ocsa censecuences N/A 2 Cis is: A) Not II:fcrzstien B) Unchanged _
| |
| Projec*d
| |
| , (1) ?rciected Mv31e Bcht Dese At: Dese Rate Duratien ?rciccted Ccse f 1
| |
| ~
| |
| 3 A) Sita M-Mm 7 mR/hr mRent 4 31 2 Miles :nR/hr =Ran '
| |
| '5 C) 5 Miles mR/hr = Pan
| |
| ~'
| |
| i5 D) 10 M4 % mR/hr * =Ses ,
| |
| (2) Prcid Orrreid Dese F mitrant At: P;ciected Ccse -
| |
| l 7 A) Sita W rv'a 7 mPan 3 B) 2 Miles mRe:1 9 C) 5 Miles =Ran 10 0) 10 Miles =Ran 11 (3) Affected Sect =rs, 12 erH D Elmereact-r W** Ccnsideratiens N/A 13 21s is A) New Infcr: nation B) Crw-h2W (1) F r-- ---- M Prctactiv*. .k:: ices:
| |
| 14 Ncce; Cther (Descr!.he) 15 15 ~
| |
| 17 (2) IJ.censee it:iii.mgency Acticns Urx:ermy: Ncce; Ctner (Cescr:2e) _
| |
| 13 ~
| |
| 13
| |
| ,20 (3) P.eq.:sts: fcr Cffsita Sq;: pert: Ncce; C*-** (Cescrl:e.'
| |
| as .
| |
| I22 ..
| |
| '23 (4) Prognosis for 9ersacing cr Terminacica ci Eve.= 3ased en Plant Inic:::ation:
| |
| 24 Ncne; Cther (D
| |
| * M) 25
| |
| ,26 l27 (5) Ott:ar Ccan: ants: Ncca; Ctber (Desc $ )
| |
| !23 -
| |
| 19 30 IMEPG2:I? CCCRDDMI2'S/IEF DLLM - TEF.,
| |
| , as EP-2-010 Rerisic: 4 26 At ma.: 7.7 ( 2 cf 5)
| |
| , e
| |
| * P Plasse acic.cwlsiga :ntesipt cf this ::assage as yc::: sutics is -='isd:
| |
| I2GlD g _
| |
| t St. r%rtaa EC: '
| |
| e
| |
| ~
| |
| St. Jchn III: ,
| |
| M M N _2D: ~
| |
| , CCEEICMD. SIGA7JRE /TI.E -
| |
| i FRDERY PuwwCCN ;GEEII:S SIC:2EARY SummCCN A.uRw Z St. Charles KC Waterford 142 i St.- Jd2n EDC US Ccast G.:ard
| |
| * I Ia. Nuclear Energy __ Misacuri Pacidic RR Ia. Cffica ant w. Middle Scuth Utilities l pg .
| |
| i l
| |
| l -.
| |
| l l
| |
| i -
| |
| I SE !RT! RIAL CO7rLDIID 'M "SE SreCLS ( ] IS 7ECPRIN .
| |
| CR PRIVRIE DE:RMICICN.
| |
| e w
| |
| 1
| |
| _.3-2-0.10 ?.erisien 4 27 At ".ch:aar: 7.7 (3 cf 5i l
| |
| 9 9
| |
| | |
| PAKr II - E SUPPLI:EC2RY IJEC SETD'ICATICN DEUE"'ICN e IS I.CC*C',2fA PCWER E f'r'*r CCs!P.25? - W3 SIS WI""E A SUPPLDfETI".4RY TIEC
| |
| %; R s C CN : W E AT D S, CN .
| |
| (cate)
| |
| D2:*,.her Licsa.See ActicCS
| |
| ' hcan PL*rread E m fc Cacege -
| |
| Radicactivit7 Released (cr Increased Release)?
| |
| Liquid / Gas? Iccatica/So:rce cf P=1=== Elevation _'
| |
| Release Rate Curation Stepped ,
| |
| Balasse Mcni* h ? ,Aucunt cf Release T m ai Radiatica tavels in Plant: Em*i m(s) ~
| |
| ~
| |
| Paitauen Lavsl(s) Areas Evacuatec btxi=unt Offsite Ccse Ratas !
| |
| I=tegrated ocse ,
| |
| MatercDxv Win:1 Directica Fr:2n -
| |
| Wini S;: eel (.%ter/sec cr miles /hr) l Calta T (CC cr C)
| |
| ? Sig:n E: eta Tercerature (CC cr CF) l Stability Class A B C D E F Ral s g (Yes / Nc)
| |
| Projected Deses: I Dese Rates Integrated Dese 1
| |
| 2d 5 :ni 10 mi Sectors C:r?'d .atics (Surface): Implant te Cffsite ,
| |
| React =r Cceratiens:
| |
| Reacter Svstem Stat =s Pcwer Iavel Pressure Tere. Ficw ( M s on)
| |
| CT1f7 M:de ICCS Cperan.w/cpazahia -
| |
| C:n*= 4 r- = t. Stat s ,.
| |
| c**= 4 -e Isclated? Centainment Tec:c. .
| |
| Ce4 ='* Pressure Centairmant Radiatica RA.r -
| |
| Shrr*hy Gas he Sys (3hR) anac-ivt w cent cis i Centrcl . h Insertsi Status cf r..ar. Ecration Systsn IP-2-010 Revisien 4 28 At-m m t 7.7 (4 cf 5)
| |
| | |
| .?MC II - 2C SCPPTZMECME E7EE T'ETICASCN DIFCFh0CICN Stamm Plant Stat:s S/G Imels F4tip. Failure FascWater So:rcs/Flcw S/G !sclaced?
| |
| .6's (SWR) cia ==d Electrical Dist. Stacas: Nczmal Offsite Pcter A1milable? ,
| |
| cMjor Bussas/tcads Lost k Safeguarda Busses PcWar Scurca e Q/G W a=? 7 Security /Saf--- -d5:
| |
| acan 123 rent: Sanzch Ccaductad?
| |
| Search Results Site Evace.atad? J .
| |
| Extortica: Sazrca (Phens, lettar, etc)?
| |
| IcceT.2n of Lattar * !
| |
| Intrusica: N id=*? Cutsidar?
| |
| Furthest Pcint of Intrusion Fire azzs relatad? . Stolen / Mini ex; Material?
| |
| Rx Ccar. h uoticn: Sima of Grcup Danarxis via1=aa=? Fire arms r='=*=d?
| |
| 4t *-_ __ -- __/ymnes a mi I am, Mn1 en [7 Arsct1 I::UQld .
| |
| , Stolen /P'saia" mearial?
| |
| l l M- --_2 sticn:
| |
| - Moda (Rcad/ Rail / Air /etc.) Carrier Exact Iccation ~
| |
| Tfge of Matarial (HE7/Spani Fcal/ Cat III/Ctnar)
| |
| Description of Shi;aant Iabals: (Cn m tarial Ps::xaga) (Cn Vamela) h 9 4119 Surveys -
| |
| , Physical damage to ccceminar? -
| |
| l- Eire /9tcita Misas.ng star::al?
| |
| l Ntari.als and Fuel Facilities:
| |
| Kind of Licensen ( p are, radiwtm, :mdical, etc.)
| |
| I-@ invol'ad , ,
| |
| l SclidA n''n ?4 =d? T'antvl/tecsa?
| |
| ~
| |
| /
| |
| l Boargency Cecrtiteator/E:P 01:ac:ce Signac.:re/':'1:na W.smittal verifisi /
| |
| c=micacer Sig::a==e/ nae IP-2-010 ?siisien 4 29 At-,r+.t 7.7 ( 5 ef 5) .
| |
| e t e
| |
| - - - - _ _ - - . , _ . . . _ _ _ _ - , _ . . _ _ _ . __m,..m.,_,., ,,,_,_.._..,g,_ , _ , . _ _ . _ . _ _ , , . _ _ _ , . , _ , _ , , . , . , _ , , _ _ _ , . , _ _ _ _ _ _,, , __ _ , _ _ . ,_,,,_,___
| |
| | |
| REQUEST FOR OFFSITE ASSISTANCE 1.0 The Emergency Coordinator or the Emergency Operations Facility Director will forward requests for offsite assistance to the Lead Communicator at the applicable facility for transmission to the
| |
| -desired agency. This request could be made using the Follow-Up Notification, Attachment 7.7, of this procedure, or the Communications Log Form, Attachment 7.1, of EP-2-150.
| |
| NOTE .
| |
| ~
| |
| Notify or request assistance only from the appropriate personnel / agencies as directed by the Emergency Coordinator or the Emergency Operations Facility Director.
| |
| 2.0 REQUESTS FOR OFFSITE ASSISTANCE see EP-2-020, Contaminated Injured /Ill Personnel
| |
| ~
| |
| | |
| ===2.1 Hospitals===
| |
| ~
| |
| 2.1.1 Reqdests for medical assistance will be made directly to the appropriate hospital using PABX telephone.
| |
| 2.1.1.1 West Jefferson General Hospital -
| |
| 2.1.1.2 Ochsner Foundation Hospital -
| |
| 2.1.1.3 St. Charles Hospital -
| |
| NOTE
| |
| ^ Do not contact St. Charles Hospital for Medical Problems that are complicated by Contamination or Radiation.
| |
| 2.2 AMBULANCE SERVICES EP-2-010 Revision 5 30 Attachment 7.8 (1 of 5)
| |
| _ .--,__ _ __.~. _ _ . ___ _. . _ _ _ , . _ _ _ . _ - . _ . . _ . _ . _ _ . _ . , _ .
| |
| | |
| 2.2.1 Requests for Ambulance Services will be made directly to the i appropriate facility for West Jefferson Hospidal and to tne St.
| |
| Charles Sheriff for St. - Charles Hospital.
| |
| 2.2.2 St. Charles Hospital Ambulance Industrial Hotline or Operational Hotlina.
| |
| 2.2.3 West Jefferson General Hospital (Air Care, Helicopter Services)
| |
| THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE
| |
| -INFORMATION.
| |
| EP-2-010 Revision 5 31 Attachment 7.8 (2 of 5)
| |
| | |
| REQUEST FOR OFFSITE ASSISTANCE NOTE When requesting off-site ambulance assistance, ensure that EP-2-020, Contaminated Injured /Ill Personnel, Attachment 7.3, Security Notification
| |
| . Checklist, is utilized to alert Security of arrival of ambulance on site.
| |
| 2.3 RIVER / RAILROAD OR VEHICULAR CONTROLS 2.3.1 United States. Coast Guari,
| |
| 'or via EOC Operational Hot?ine. ,
| |
| 2.3.2 Missouri Pacific Railroad Company, 2.3.3 Louisiana State Police, or Operational Hotline.
| |
| 2.3.4 St'. Charles Parish Sheriff's Department, St. Charles Industrial Hotline or Operational Hotline or 2.3.5 St. John Parish Sheriff's Department, -
| |
| ~
| |
| 2.4 FIRE FIGHTING ASSISTANCE -
| |
| 2.4.1 Hahnville Volunteer Fire Department, St. Charles Industrial Hotline.
| |
| 2.5 ENGINEERING ASSISTANCE
| |
| (
| |
| I 2.5.1 Combustion Engineering, Inc., _
| |
| 2.5.2 EBASCO Services, Inc. - (NY, NY), . .
| |
| I 2.5.3 EBASCO Services, Inc. - (On Site) {R. Milhiser) 2.5.4. Middle South Uti11 ties - [S. Fisher],
| |
| I l
| |
| l 2.6 TECHNICAL / ENGINEERING ASSISTANCE 2.6.1 ' Institute of Nuclear Power Operations (INPO) -
| |
| THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE I
| |
| INFORMATION. -
| |
| 1 l
| |
| l i
| |
| EP-2-010 Revision 4 32 Attachment 7.8 (3 of 5)
| |
| | |
| REQUEST FO:" OFFSITE ASSISTANCE 2.7 DEPARTMENT OF ENERGY 2.7.1 Radiation Faergency Assistance Center -
| |
| 2 7.2 Radiological Assistance for Region II -
| |
| 2.7.3 Dept. of Energy EOC, Washington, DC, 2.8 NUCLEAR REGULATORY COMMISSIC" 2.8.1 Use dedicated NRC ENS or
| |
| ~
| |
| 2.8.2- Region IV, Arlington, Tx, 2.9 OTHER LP&L FACILITIES 2.9.1 Waterford'I and 2 SES, LP&L Emergency Dial ; PABX 2.9.2 Luling District Office 2.10 OTHER FEDERAL GOVERNMENT AGENCIES 2.10.1 Federal Aviation Administration, 2.10.2 U.S. Army Corps of Engineers, 2.10.3 National Weather Services,Moisant Field, 2.11 MUTUAL ASSISTANCE ORGANIZATIONS PHONE AFTER HOURS PHONE 2.11.1 Arkansas Power & Light Company Primary: [ John Griffin]
| |
| Alternate: [ Donald Ruter]
| |
| Alternate: [ William Cavanaugh) l THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE l INFORMATION.
| |
| EP-2-010 Revision 5 33 Attachment 7.8 (4 of 5)
| |
| | |
| REQUEST FOR OFFSITE ASSISTANCE 2.11.2 Gulf States Utilities Company Primary: [ William J. Cahill,Jr.] [504-388-0691] [504-635-4390]
| |
| Alternate:[Ellery L. Hammond] [504-635-6844] [504-635-3618]
| |
| 2.11.3 Mississippi Power & Light Company Primary: [ James P. McGaughy,Jr.] [601-969-2399] [601-956-3240]
| |
| Alternate: '[ Larry F. Dale] [601-969-2448] [601-373-3465]
| |
| 2.11.4 Seiraic Verification St. Louis University,St. Louis, Missouri [1-314-658-2222] ;
| |
| Spring Hill College, Spring Hill, Alabama [1-205-460-2011]
| |
| Tennessee Earthquake Information Center [1-901-454-2007]
| |
| Memphrs, Tennessee University of Texas, Galveston, Texas [1-713-765-1011]
| |
| 3.0 MESSAGE FORMAT TO:
| |
| . THIS IS .AT THE WATERFORD 3 STEAM ELECTRIC STATION.
| |
| WE HAVE DECLARED AN AT HOURS,,
| |
| . WE HAD A RADIOACTIVE RELEASE.
| |
| WE REQUIRED ASSISTANCE AS FOLLOWS:
| |
| i l _.
| |
| l Emergency Coordinator or (Time /Date)
| |
| EOF Director Signature
| |
| -THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| l EP-2-010 Revision 5 34 Attachment 7.8 (5 of 5)
| |
| | |
| CONTROL ROOM CHECKLIST FOR TRANSFERRING CCMMUNICATIONS RESPONSIBILITIES TO THE TSC i
| |
| : 1. When the TSC is activated and is ready to accept the responsibilities for all off-site and on-site ccamunications, the Control Room Emergency Communicator will establish communications with the TSC Lead Communicator and provide the following informa-tion:-
| |
| A. Communications lines on which the Control Room is currently com-municating _-
| |
| B. Individual / agency at the other end of the lines C. Latast infernation transmitted over the lines D. - Latest information received over the lines
| |
| : 2. Off-Site Communications A. Continue maintaining communications on the activated lines after _
| |
| completing the steps above. ,
| |
| i B. After the TSC Communicator announces: WATERFORD 3 TECHNICAL SUPPORT CENTER (TSC) IS NOW RESPONSIBLE FOR COMMUNICATIONS ON THIS LINE, announce over the activated line: THE WATERFORD 3 CONTROL ROOM RELINQUISHES COMMUNICATIONS ON THIS LINE.
| |
| 3 Upon completion of the transfer, the Centrol Room Emergency Com-municator will perform the following functions:
| |
| : 1. Inform the NOS-SS that communications have been transferred to the TSC ECC.
| |
| B. Deliver all dispatched or developed Initial Notification, Follow-Up 1 Notification and Communication Logs to the TSC Lead Communicator for his retention and review.
| |
| C. Return to the Control Room and assume other responsibilities as directed by the NOS-SS.
| |
| EP-2-010 Revision 4 35 Attachment 7 9 (1 of 1)
| |
| | |
| TSC CHECKLIST FOR ACCEPTING RESPONS!BILITY FOR COMMUNICATIONS SYSTEMS FROM THE CONTROL RCOM
| |
| : 1. The TSC Lead Communicator will be delivered a copy of each Initial Notificat. ion, Follow-Up Notification and Communications Log. Sheet disseminated by the NOS Emergency Communicator and, if required, make a copy of the NOS Log Book.
| |
| : 2. TSC Lead Communicator will disseminate these reports to the staff in the TSC and assign communicators in the Emergency Control Center who I can perform the following actions.
| |
| : a. Review the material to become familiar with communications to this point.
| |
| : b. Pick up the active communications lines and listen to any transmissions. occurring at the time.
| |
| . NOTE
| |
| .Do not respond; allow the Control Room. Emergency Communicator to continue handling communications.
| |
| c.'At the direction ~of the Emergency Coordinator "to shift communications to the;TSC," make the following announcement on the active lines (one at a time to allow proper response from the Control Room): WATERFORD l 3 TECHNICAL SUPPORT CENTER (TSC) IS NOW RESPONSIBLE FOR COMMUNICATIONS
| |
| ,0N THIS LINE.
| |
| (
| |
| l d. After the Control Room Emergency Communicator responds with: THE
| |
| -WATERFORD 3 CONTROL ROOM RELINQUISHES COMMUNICATION ON THIS LINE, then communications have been shifted to the Technical Support Center.
| |
| : 3. After the above steps have been completed, inform the Emergency Coordinator in the TSC that communications responsibilities have been shifted to the TSC.
| |
| EP-2-010 Revision 5 36 Attachment 7.10 (1 of 1)
| |
| L
| |
| | |
| l TSC (EOF) CHECKLIST FOR TRANSFERRING COMMUNICATIONS RESPONSIBILITIES TO THE EOF (TSC)
| |
| I 1. Establish communications with the EOF (TSC) Communicator and provide the following information:
| |
| : c. Communication line(s) on which TSC (EOF) is currently communicating
| |
| , b. Individual / agency on the other end of the line(s)
| |
| ( -
| |
| : c. Latest information transmitted over the line(s)
| |
| : d. Latest information received over the line(s) - 1.
| |
| ~
| |
| I
| |
| : 2. Offsite communications:
| |
| : a. Continue maintaining communications on the activated line af ter completin's the steps above.
| |
| l b. After the EOF (TSC) Communicator announces: WATERFORD 3 EMERGENCY OPERATIONS FACILITT (TECHNICAL SUPPORT CENTER) IS NOW RESPONSIBLE FOR COMMUNICATIONS ON THIS LINE, announce over the activated line: .
| |
| =
| |
| THE WATERFORD 3 (EMERGENCY OPERATIONS FACILITT) TECHNICAL SUPPORT CENTER RELINQUISHES COMMUNICATION ON THIS LINE.
| |
| : c. Inform the (EOF Director) Eme'rgency Coordinator that communications l have been transferred.
| |
| l l
| |
| 1 j EP-2-010 Revision 4 37 Attachment 7 11 (1 or 1)
| |
| | |
| l r .
| |
| EOF CHECKLIST FOR ACCEPTING COMMUNICATIONS RESPONSIBILITIES FROM THE TSC
| |
| : 1. Establish communications with the TSC Commun'icator and discuss tne following information in the areas in which responsibility is to be transferred.
| |
| : a. Communication line(s) on which TSC is currently communicating
| |
| : b. Individual / agency on the other end of-the line(s)
| |
| : c. Latest information transmitted over the line(s)
| |
| : d. Latest information received over the line(s) _
| |
| l 2. Offsite communications:
| |
| : a. EOF Communicator directs the TSC Communicator to shift com- ,
| |
| munications to the EOF.
| |
| : b. The EOF Communicator picks up the line, listens to any transmissions occurring at the time and logs the communication on the Ccamunications Log Sheet (Attachment 7 1, EP-2-150, Emergency .
| |
| Plan Implementing Records). _-
| |
| j' NOTE Do not respond; allow the TSC Communicator
| |
| { to continue handling communications.
| |
| (
| |
| I
| |
| : c. At a point when there is little to no traffic on the line, the EOF Communicator announces the following: THE WATERFORD 3 EMERGENCY OPERATIONS FACILITT IS NOW RESPONSIBLE FOR COMMUNICATIONS ON THIS LINE.
| |
| : d. Stand by for the TSC Communicator to announce that THE WATERFORD 3 TECHNICAL SUPP0HT CENTER RELINQUISHES COMMUNICATION ON THIS LINE.
| |
| I After hearing the announcement, inform the EOF Communication Coordinator that communications have been transferred.
| |
| : e. The Communications Coordinator shall notify the EOF Director that off-site communications have been transferred. .
| |
| l ,
| |
| ; EP-2-010 Revision 4 38 Attachment 7 12 (1 of 1)
| |
| | |
| NOTIFICATTON CNilCELIST CONW AGustCY/PUNCTIOes 8e005 UseUSUAL RVENT ALERT SITE AREA EseERGENCT GEMNRAL EsegetGENCY ST. CNARLES BOC ^Or. NL ST. JOuti EOC OP. NL 165g-22221 LalED Dr. ML
| |
| [1-925-45101 IDEP Or. ML 81-342-547e1 N1 6 2 LP6L E-19 (11-47971 US seaC senC NL
| |
| ; MIDDLE SOuTM [569-45111 NITNIN 12 8000a8
| |
| . UTILITIES INPO (1-444- AS NEEDED .
| |
| 951-89443 MISSOURI PACIFIC RR 8705-66131 AS NEEDED AS NEEDED AS NEWW AS MEMDED ANINSURRAS 11-203- AS NEEDED AS IIEEDED AS NEMED AS NEEDED 677-7305 US COAST GUARD 1549-7101) AS NEEDED AS NEEDED AS NEEDED AS NESDED ST. CHARLES IIOSP&TAL IIIDUSTRI AL AS NEEDRO AS NEEDED AS NEEDED AS NEEDED IBOT LIIIE OCalSNER CLINIC *
| |
| [838-3980) AS NEEDED AS NEEDED AS IIEEDED AS NEEDED ,
| |
| NEST JEFFESSOel 11-800- AS MEEDED AS NEEDED AS NEmaED AS NEEDED NOSPITAL 382-44461 NEST JI:FFEASoel AID (1-844- AS NEI;DED AS NEEDED AS NEE)RD AS NEllDED AMBULANCE 302-4006]
| |
| HAllNVILLE VFD IIIDUSTRI AL AS IIREDED AS MEEDED AS NEEDED AS NEEDED IIOT LINE LA. STATE POLICE 8568-5755) AS NEEDED AS NEEDED AS NEW)RD AS MEEDED Dos 11-3e1- AS NEEDED AS NEEDED AS NEW ED AS NEEDED isi_ssssi . _ _ . . _ _ . . . . - . _ _ .
| |
| TuE NATEaI AL COe:TAINED MITisIN Tist SrsesiOLS I 3 IS enoenISTAar 08 eniv&TE NFOamATIOes EP-2-010 itevision 5 39 Attachment 7.13 (1 of I)
| |
| | |
| _ . . . _ _ - _ __ _ -- . _ = _. . . - _ _
| |
| E}ERGENCY RESPONSE VERIFICATION ESTIMATED TITLE NAME ARRIVAL TI?E
| |
| : 1. Emergency Coordinator ,
| |
| j
| |
| : 2. Health Physics Coordintor
| |
| : 3. TSC Lead Communicator
| |
| : 4. 'TSC~ Supervisor 5.. Security Superintendent
| |
| : 6. Operations Coordinator ;
| |
| : 7. Dose Assessment Coordinator
| |
| : 8. Radiological Controls Coordinator
| |
| @. HP Technician
| |
| : 10. HP Technician
| |
| : 11. HP Technician
| |
| ' 12. HP Technician ,
| |
| : 13. HP Technician
| |
| : 14. HP Technician- ,
| |
| : 15. HP Technician l 16. TSC Lead Engineer
| |
| : 17. Nuclear Engineer
| |
| , 18. Electrical Engineer I .
| |
| : 19. Mechanical Engineer
| |
| : 20. OSC Supervisor
| |
| : 21. Operations Communicator
| |
| '22. TSC Communicator #1
| |
| : 23. TSC Communicator #2
| |
| .24. Chemistry j- 25 Off-Site Technical Advisor i
| |
| NS40055
| |
| | |
| WATERFORD 3 SES PLANT OPERATING MANDAL LCutsIANA POWER & LIGHT MN POM VOLIJME 18 EP-2-020 POM SECTION Z REVISION s l
| |
| l l
| |
| l i
| |
| I Emergency Plan Implementing Procedures Contaminated Injured /Ill Personnel LP&L W-3 RECORDS l UNCONTROLLED COPY DO NOT USS IN ANY SAFETY-RELATED 'lEST!NG, 1 MAINTENANCE, OR OPERATIONAL ACTIVITY l PORC Heating No. 83-52 Reviewed:
| |
| '~
| |
| M8[ '%
| |
| PORC Chairman Approved:
| |
| L tt Plant Manager-Nuclear
| |
| \ l SY Approval Date Fuel Load Effective Date I
| |
| -- - , . . - ., ,, - - -e , , - - - - - - , - - . - - - . - ,
| |
| | |
| ~
| |
| WATZRFORD 3 SE3 -
| |
| PLANT OPEZATI:lG MANUAL ,
| |
| CHANGE / REVISION / DELETION REQUEST .
| |
| Prcsedure No. S ' b ': 'u Title C- ' < On- U A- .: . . . . - -
| |
| Effective Date N be" (if different from approval date) thel sta 1. B. er C _
| |
| A. Change No. Jd _
| |
| B. Revision No. 6 '
| |
| C. Deletion AIA 1
| |
| REASON FOR CHANCE. RETTSTON. OR DEI.ETTdN -
| |
| /,- < ,. n.v.J. c-w.'C, Lite
| |
| % A A.'. G.C ~ h
| |
| * M-t.. _
| |
| REOUTEE15 SICNATtfBES ; ,
| |
| Originator ' D-~ b - Date / M2 Tcchnical Review M b M M a d Date n/T 7UT
| |
| ~ SAFETT EVALUATION Doen this change, revision, or deletion: '
| |
| TES NO 1.
| |
| ~
| |
| : Change the facility as. described in the FSAR7
| |
| : 2. Change the procedures as described in the FSAR7- /
| |
| : 3. Conduct tests / experiments not described in the F3AR7 _
| |
| 4 Create a condition or conduct an operation which ex- "
| |
| ceeds, or could result in exceeding, the limits in Technical Spootfications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safsty Evaluation checklisu.
| |
| Safety Evaluation M 8&r<l#d _, Data Group /Dep8 t. Head Review 'bMANd Date / 7k3 l Temporary Approvale Date (NO3)
| |
| Temporary Approvale Date QC Review M OYA -
| |
| Date I- 5 &
| |
| PORC Review N M b _ Date / 8 -P M -
| |
| Meeting No.
| |
| Plant Manager-Nuclear Approval Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UNT-1-oo3 Revision 6' Attachment 6.9 (1 of 1) 2G .
| |
| w ,-,,r n-,-w--,,o- +,o_---m- w,-, .w,,-a-~~,,,, _ww,r,,,,,_,,,,,,_,_,_v. --
| |
| ~mw,---,w-~..nw.-,,,,--gn-m ,-n--,~ww -w_,-
| |
| | |
| Emergency Plan Implementing Procedure EP-2-020 Contaiminated Injured /Ill Personnel -
| |
| Revision 5 TABLE OF CONTENTS 1.0 PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| 3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5.1 Immediate Actions and Notifications 5.2 Follow-up Actions and Communications 6.0~' FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Ambulance Notification Checklist (2 pages) 7.2 West Jefferson General / Ochsner Foundation Hospital Notification Checklist (2 pages) 7.3 Security Notification Checklist (1 page) 7.4 Health Physics Responsibilities On-site (1 page) 7.5 Health Physics Responsibilities at Support Eospital (2 pages) f i
| |
| LIST OF EFFECTIVE PAGES l
| |
| Title Revision 5 1-6,9,10 Revision 5 7,8,11-14 Revision 4 LIST OF PAGES CONTAINING ,
| |
| I PROPRIETARY OR PRIVATE INFORMATION 1
| |
| ! 7
| |
| -~
| |
| 9 l
| |
| L
| |
| | |
| Emergency Plan Implementing Procedure EP-2-020 Contaminated Injured /Ill Personnel
| |
| * Revision 5 1.0 PURPOSE The purpose of this procedure is to provide guidance to the Emergency Coordinator in the event that contaminated injured /ill personnel must be transported off-site.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 'Waterford 3 SES Emergency Plan -
| |
| 2.2 Emergency Medical Assistance Program (EMAP) 2.3 NUREG 0654/ FEMA-REP-1 2.4 Emergency Management Resources Book l
| |
| 2.5 UNT-7-018, First Aid and Medical Care 2.6 EP-3-040,-Emergency Equipment Inventory 3.0 RESPONSIBILITIES ,
| |
| The. Emergency Coordinator is responsible for ensuring that the actions
| |
| 'as outlined in this procedure are carried out.
| |
| 4.0 INITIATING CONDITIONS Injured /ill personnel are contaminated and must be transported off-site.
| |
| l i-2 l
| |
| l
| |
| | |
| Emergency Plan Implementing Procedure EP-2-020 Contaminated Injured /Ill Personnel e Revision 5 NOTE
| |
| ~~
| |
| -1. Personnel injured /ill within a Radiation Controlled. Area (RCA) shall be considered contaminated until determined to be free of contamination by Health Physics .I personnel.
| |
| : 2. Serious injuries requiring medical treatment shall take precedence over decontamination of injured /ill personnel. .
| |
| 5.0. PROCEDURE -
| |
| ~
| |
| r NOTE The Emergency Coordinator shall give the Emergency First Aid Team (EFAT) immediate l access to the victim.
| |
| 5.1 IMMEDIATE ACTIONS AND NOTIFICATIONS l Upon the determination that contaminated injured /ill personnel must be l transported off-site, the Emergency Coordinator shall:
| |
| 5.1.1 Ensureithat the Emergency First Aid Team (EFAT) treats victim (s) l in accordance with UNT-7-018.
| |
| ! 5.1.2 Coordinate the activation of the EFAT with Operational. Support l
| |
| l Center (OSC) Supervisor when the OSC is manned.
| |
| 5.1.3 Ensure that Health Physics personnel perform duties in accordance j' with Attachment 7.4, Health Physics Responsibilities On-Site.
| |
| _5.1.4 Direct the Emergency Communicator (s) to notify the appropriate ambulance service (s) in accordance with Attachment 7.1, Ambulance Notification Checklist.
| |
| i 3 i
| |
| | |
| Emergency Plan Implementing Procedure EP-2-020 Contaminated Injured /Ill Personnel Revision 5 NOTE
| |
| : 1. St. Charles Ambulance Service is the primary transportation service for Waterford 3.
| |
| However, West Jefferson Air-Care Ambulance may be selected based on St. Charles ambulance ,
| |
| availability and degree of injury.
| |
| : 2. If the West Jefferson Air-Care Ambulance is used, the Security pickup truck will be used for primary transportation from the site of injury to the Helicopter Landing area. Notify Security in accordance with Attachment 7.3.
| |
| If the Security vehicle is not available, any other available pickup truck or station wagon should be used.
| |
| 5.1.5 Direct the Emergency Communicator (s) to notify Ochsner Foundation Hospital or West Jefferson General Hospital in'accordance with Attachmnent 7.2. l 5.1.6 Direct the Emergency Communicator (s) to notify the Waterford 3 Security Shift Supervisor in accordance with Attachment 7.3, l Security Notification Checklist.
| |
| l 5.1.7 Request and coordinate additional support, as required (e.g.
| |
| l search and rescue, emergency repair, etc.).
| |
| 5.1.8 Make contact with the Health Physics Coordinator or his designee and inform him/her of the event to ensure proper Health Physics staffing. Refer to the Emergency Management Resources Book. l 5.2 FOLLOW-UP ACTIONS AND COMMUNICATIONS l Upon the completion of the immediate actions and notifications of this procedure (section 5.1), the Emergency Coordinator shall:
| |
| 4
| |
| | |
| Emergency Plan Implementing Procedure EP-2-020 Contaminated Injured /Ill Personnel .- Revision 5 3.2.1 Direct that Health Physics and Emergency First Aid Team personnel move the victim (s) to a rendezvous point (if required) where the ambulance personnel can place victim (s) in the ambulance (s).
| |
| In the event that severe injuries (e.g.,
| |
| back injuries, severe bleeding) prevent the moving of victim (s), await assistance from qualified ambulance personnel.
| |
| 5.2.1.1 Step 5.2.1 should be performed in accordance with Attachment 7.2, West Jefferson General / Ochsner Foundation Hospital Notification
| |
| . Checklist, and Attachment 7.4, Health Physics Responsibilities On-site.
| |
| 5.2.2 Direct the Emergency Communicator (s) to notify the Security Shift Supervisor and inform him of the ambulance rendezvous point (e.g. , esist side of RAB,- Fuel Handling Building doorway, ate.) or location of victim to which Security will escort the ambulance i personnel.
| |
| 5.2.3 Direct that Health Physics personnel escort victim (s) to Support l Hospital (s).
| |
| 5.2.4 Direct that Health Physics personnel provide assistance at the l
| |
| Support Hospital (s) in accordance with Attachment 7.5, Health l Physics Responsibilities at Support Hospital.
| |
| , - 5.2.5 - Direct the Health Physics personnel to control potentially l
| |
| contaminated areas, equipment, and personnel involved with l on-site response (e.g., personnel handling victim (s), area f through which victim was moved, etc.) in accordance with Attachment 7.4, Health Physics Responsibilities On-site. l I
| |
| l _. .
| |
| 5
| |
| | |
| Emergency Plan Implementing Procedure EP-2-020 Contaminated Injured /Ill Personnel '
| |
| Revision 5 NOTE Communications with ambulance can be maintained through the receiving hospital.
| |
| 5.2.6 Direct the Emergency Communicator (s) to notify tne Support Hospital (s).of any changes the support Hospital (s) may not be .
| |
| aware of (e.g., changes in estimated time of arrival, condition of victim (s), number of victims, etc.).
| |
| 6.0 FINAL CONDITIONS 6.1. Victim (s) are admitted to Support Hospital (s) and are under professional medical supervision. ,
| |
| 6.2 Health Physics personnel at Support Hospital (s) have all potentially contaminated personnel, areas, and equ'ipment controlled in accordance with Attachment 7.5, Health Physics Responsibilities at Support l
| |
| ! Hospital.
| |
| i 7.0 ATTACHMENTS 7.1 Ambulance Notification Checklist 7.2 West Jefferson General / Ochsner Foundation Hospital Notification Checklist 7.3 Security N0tification Checklist 7.4 Health Physics Responsibilities On-site 7.5 Health Physics Responsibilities at Support Hospital D
| |
| I i
| |
| 6 p - y r, m.-,, - ..ee. -.-,s.--. w ,_yw, ,. ,. - . . , , , , ,. , , -
| |
| | |
| AMBULANCE NOTIFICATION CHECXLIST (Notification via PABX Telephone)
| |
| St. Charles Hospital Ambulance Dispatched via St. Charles. Parish Sheriff Dept. - Industrial or Operational Hot Line West Jefferson Ypspital Air-Ambulance
| |
| : 1) Emergency Communicator (name) ,
| |
| : 2) Time and date of call / /
| |
| (24-hour clock) day mo. yr.
| |
| : 3) E0C Communicator on-line (name)
| |
| : 6) Repeat the following message: MY NNfE IS
| |
| - I AM THE (emergency posirien)
| |
| AT THE WATERFORD 3 STEAM ELECTRIC STATION. WE NEED AMBULANCE SERVICE (S) FOR THE
| |
| ;. TRANSPORTATION 05 CONTAMINATED l
| |
| l INJURED PERSONNEL FROM WATERFORD 3.''
| |
| r i .
| |
| : 5) Then discuss the following information:
| |
| i i
| |
| a) Number of victims __
| |
| ! b) Type of. injuries (discuss) l.
| |
| c) Contamination (circle) YES NO d) Type of contamination ':ircle) Skin Clothing Internal e) .. Gate ambulance is to enter (if known)
| |
| (gate) l THE MATERIAL CON'.AINED WHITH THE SYMBOLS [] IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| EP-2-020 Rev. 9 7 Attachment 7.1 (1 of 2)
| |
| -_ . . _ . . - . _ _ . - __ _ .- . , - , - _ _ , _ . - ~ . _ _ . . . _ . _ , _ _ , _ _ . _ , _ . _
| |
| | |
| X!BUI.ANCE NOTIFICATION CHECKLIST 6)- Method of. transport (circle) Ground .\ir
| |
| : 7) Name.of ambulance service (s)
| |
| (name(s))
| |
| : 8) If Air. Care is to be employed, the following transportation to the 3
| |
| Helicopter Landing Area isto be used: -
| |
| a) Security pickup truck (circle) YES NO b) Other available pickup (circle) YES NO truck or station wagon
| |
| : 9) Additional Information I'
| |
| EP-2-020 Rev. 4 8 Attachment 7.1 (2 of 2)
| |
| | |
| WEST JEFFERSON GENERAL /0CHSNER FOUNDATION HOSPITAL NOTIFICATION CHEChT.IST West Jefferson Hospital Telephone # .
| |
| Ochsner Foundation Hospital Telephone # _ .
| |
| 1)' Emergency Communicator
| |
| : 2) Time and date of call / /
| |
| (24-hour clock) day mo. yr.
| |
| : 3) Circle the hospital to be called: ,
| |
| 3a. West Jefferson Hospital -
| |
| Dial 3b. Ochsner Foundation Hospotal - Dial , '',
| |
| : 4) When the Emergency Department is on the line for Ochsner or the Air Care Dispatcher for West Jefferson, request his or her name and positim ; then repeat the following message: l
| |
| ~
| |
| My name is . I am -
| |
| the (emergency position).at the i Waterford 3 Steam Electric Station. We are preparing to transport contaminated injured personnel to your facility.
| |
| Prepare your radiation emergency area.
| |
| : S) -Then discuss the following information:
| |
| j a)' Number of victims l b) Type of injuries (discuss) c) Degree of contamination (circle) cpm mrem d) Type of contamination (circle) Skin Clothing Internal I
| |
| L THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE INFORMATION.
| |
| b* EP-2-020 Revision S 9 Attachment 7,2 (1 of 2) i _ _ ,___ _. . . _ . _ _ _ _ _ _
| |
| | |
| tiEST-JEFFERSON GE'!ERAL/0CHSNER FOCIDATION HOSPITAL .}f0TIFICATION CHECKLIST e) First aid already administered on-site (discuss) f) Method of transport (circle) Ground Air If Air Care transport is to be used, ensure .
| |
| that site transportation is available in accordance with Attachment 7.1, section 8.
| |
| g) Name of ambulance service (s) h) Estinited time of arrival (24-hour clock)
| |
| : 6) Inform the Hospital that Waterford 3 Health Physics personnel will l
| |
| accompany victim in ambulance.
| |
| l l 7) Inform the Hospital that they will be notified of any changes and l give them your phone number.
| |
| I
| |
| ! 80 Additional Information l-I l
| |
| l- EP-2-020 Revision 5 10 Attachment 7.2 (2 of 2)
| |
| -*- r . . , . . , _.%.. , _ . - _ - , , , , . - . , , . , , , . .._, -
| |
| | |
| SECURITY NOTIFICATION CHECKLIST
| |
| : 1) Emergency Communicator '
| |
| (name)
| |
| : 2) Time' and date of call ___/ /
| |
| (24-hour clock) day mo. yr.
| |
| 3 ) .. Name of Shift Security (name)
| |
| : 4) Repeat the following message: MY NAME IS _
| |
| . I AM THE (emergency position). WE REQUEST SECURITY SUPPORT TO ,
| |
| AID IN THE PREPARATION OF TdE ,
| |
| TRANSPORT OF CONTAMINATED INJITnED PERSONNEL TO THE HOSPITALTS).
| |
| : 5) Then discuss the following information:
| |
| a) Location of victims (discuss) b) Number of victims c) Gate ambulance shall enter site (discuss) d) Method of support (Circle) Ground Air e) Estimated time of arrival (24-hour clock) f) Name of ambulance service (s)
| |
| (name) g) Security pickup truck needed for transport to the Helicopter Landing Area _(circle) YES N0 h) Other Security support (discuss) ,__
| |
| : 6) Additional Information EP-2-020 Rev. 4 11 Attachment 7.3 (1 of 1)
| |
| | |
| HEALTH PHYSICS RESPONSIBILITIES ON-SITE
| |
| : 1. ' Notify the Emergency Coordiantor of radiological c'onditions associated with the victim, including:
| |
| : a. Approximate contamination levels on victim and nature of
| |
| : contamination'(i.e., skin, clothing,. internal uptake)
| |
| -b. If overexposrue:has-occurred or is possible due to the victim's location
| |
| : c. If ambulance personn&l are required to be issued TLS's and protective clothing prior to gaining access to the victim l (Emergency First Aid Team will determine mobility of victim)
| |
| - 2. If victim's injury does not permit decontamination prior to transport off-site, consider:
| |
| : a. Covering stretcher with plastic sheets to contain contamination
| |
| : b. Removing protective clothing from victim
| |
| : c. Setting up a system for transporting the victim to an ambulance.
| |
| System should minimize the spread of contamination (i.e., provide ;
| |
| a " clean" access path for, ambulance personnel)': move. victim to a ,
| |
| controlled area outside-the RCA where the ambulance may access d)' Spreading plastic sheets in ambulance e) Having protective clothing and dosimetry available for ambulance personnel upon arrival on-site (perferably at the security access l . point to be issued by the security escort) r l-l
| |
| : 3. When time allows, complete the Skin Contamination Record.
| |
| : 4. Ensure that ambulance personnel have been issued TLD's by security
| |
| ( upon arrival, if determined to be acecesssary under part Ic above.
| |
| l l' 5. Ensure that the Health Physics technician escorting the victim to the l-l hospital is not contaminated. Control at the hospital will be extremely difficult if the Health Physics technician is restricted due to his/her own contamination.
| |
| L l-l EP-2-020 Rev. 4 12 Attachment 7.4 (1 of 1) l l
| |
| . ,,--,-n , , _ _ _ , - ~ , - - . - - , , . . _ _ . - . - _ . . _ . . - . . - - . . , - , . , _
| |
| ..-.-__..m...-, - - . - - . - _ ., . - - , , - - .
| |
| | |
| HEALTH PHYSICS RESPONSIBILITIES AT SUPPORT HOSPITAL While at the support, hospital. it is important to remember the following:
| |
| : 1. Hospital personnel are trained and may support you in regard to control of the ambulance; access ways, and monitoring personnel for contamination. _ _ _
| |
| : 2. Only authorized LP&L representatives may discuss the situation with the news media.
| |
| : 3. Keep the Emergency Coordinator informed.of the situation at the hospital.
| |
| : 4. Provide information to the Emergency Room physician as required.
| |
| Take the following measurps upon arrival at the support hospital:
| |
| ~1. Instruct the ambulance driver to close the ambulance after the victim has b2en removed. Restrict access to the ambulance until the driver and vehicle are surveyed for contamination.
| |
| : 2. Visually survey the access to the emergency facility if no provisions have been taken to control contamination and restrict access, then request that hospital personnel be assigned to physically restrict access until the area is set up. .
| |
| : 3. Set up a frisker at the exit / access point and personally monitor perstanel or request hospital staff to monitor under your guidance
| |
| : 4. Check hospital staff for proper dosimetry and protective clothing.
| |
| Close out the incident as follows:
| |
| : 1. Ecsure that all involved pcraonnel have been monitored and decontaminated (document names of monitored personnel).
| |
| '2. Collect all dosimetry devices, noting the name and social security number of the individuals.
| |
| : 3. Monitor all affected areas, decontaminate as necesssary, and package contaminated waste (all final surveys must be documented).
| |
| : 4. Return contaminated waste at Waterford 3.
| |
| EP-2-020 Rev. 4 13 Attachment 7.5 (1 of 2)
| |
| : r. ,
| |
| | |
| HEALTH ?HYSICS RESPO!!SIBILITIES AT SU??CRT HOSPITAL
| |
| : 5. Notify the Emergency Coordinator of the final statue of ambulance / ambulance personnel.
| |
| Personnel Exposures Personnel Contamination and Current Status Equipment Contamination and Current Statu]
| |
| _ Material being returned to Waterford 3 for decontamination or disposal l
| |
| i b
| |
| i EP-2-020 Rev. 4 14 Attachment 7.5 (2 of 2)
| |
| NS10008
| |
| .. _ =. , . - - . . _ . .
| |
| | |
| 'NATERFORD 3 SES
| |
| _ PLANT OPERATING MANUAL LOUISIANA POWER & LIGHT N N SY EP-2-030 POM VOLUME 18 REVISION 2 POM SECTION 2 ,
| |
| APPROVAL DATE: SEP 191983 EFFECTIVE DATE: Fuel Load T
| |
| EMERSENCY PLAN IMPLEMENTING PROCEDURE EMERGENCY RADIATION EXPOSURE GUIDELINES AND CONTROLS -
| |
| LP&L W-3 RECORDS U\ CONTROLLED COPY DO NOT USE IN ANY SAFETY-RELATED TEST!NG' MAINTENANCE, OR OPERATIONAL ACTIVITY PORC Meeting No. Tf 3f -7 f
| |
| Reviewed:
| |
| b' d'-e t .
| |
| F C Chairman Approved: -
| |
| S hkkb M '
| |
| Plant Manager-Nuclear r
| |
| | |
| WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST
| |
| ~
| |
| Procedure No. ' -
| |
| Title - -
| |
| Effective Date D L M (if different from approval date) ,s.-
| |
| (*am n1 e ta A. B_ ar C A. Change No.
| |
| n . -
| |
| B. - Revision No. m
| |
| * C. Deletion A//f aranns ron ennuar_ nrvTmTom on nrt_rrios
| |
| , - - ?
| |
| . . ,x .
| |
| & %;2.. ,
| |
| * Gn -a, .;
| |
| M.QHIRT3LAIGRATIIRED,n ], f Originator I7F k- Date ''I N Technical Revich '
| |
| IM//N Date d/h/r 1 SAFETT EVALUATION Does this change, revision, or deletion: TES NO
| |
| : 1. Change the facility as described in the FSAR? 2(_
| |
| : 2. Change the procedures as dasoribed in the FSAR?- _
| |
| /
| |
| : 3. Conduct tests / experiments not described in the FSAR? d
| |
| : 4. Create a condition or conduct an operation which ex-coeds, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to ar.y of the above is yes, complete and at.
| |
| tach a 10 CFR 50.59 Safety Evalunt a checklist.
| |
| Safety Evaluation d 7h4
| |
| * Date <f M 'O d 'M // '.'6/- ' ' " Date Jb'b !
| |
| ~
| |
| Group /Dep't. Head Review -
| |
| Temporary Approval
| |
| * Date (N05)
| |
| Temporarv Approvale Date 1
| |
| QC Review Aa e f'--J - Date ' - ~ '
| |
| l PORC Review O[2/b>-u Date 7-2^P3 Meeting No. G W4 Plant Manager-Nuclear Approval 8/8 d Date 4 /8 '1 -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| l UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G l
| |
| ___ _ , _ _ . _ . . _ _ . . ~ . _ _ _ _ . - _ _ . _ _ . . _ _ _ _ . , - , . _ _ _ _ _ , _ _
| |
| _..____..._,_.1,,,.-,-
| |
| | |
| l-Emcrgency Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 2 l and Controls TABLE OF CONTENTS 1.0 PURPOSE REFERENCES 2.0 30 RE8PONSIBILITIES 4'0--INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS .
| |
| 70 ATTACHMENTS 7.1 Emergency Exposure Authorization Form (2 pages) 72 10CFR20 Limits (1 page)
| |
| LIST OF E,FFECTIVE PAGES ,
| |
| i Title Revision 2 !
| |
| i 1-8 Revision 2 l
| |
| l l
| |
| l 1
| |
| | |
| E2;rgoncy Plan Implcmenting Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 2 end Controls -
| |
| 1.0 FURPOSE To provide guidelines and administrative controls for radiation ex-posures in excess of 10CFR20 limits during life saving or accident--
| |
| mitigating activities.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 Waterford 3 SES Emergency Plan .
| |
| 2.2 Title 10, Code of Federal Regulations, Part 20, Standards for Protection Against Radiation 23 National Council on Radiation Protection Report No. 39, Basic Radiation Protection Criteria 3.0 RESPONSIBILITIES The Emergency Coordinator is responsible for ensuring that the actions outlined in this procedure are carried out.
| |
| 4.0 INITIATING CONDITIONS This procedure is to be initiated upon reaching the following condition:
| |
| l 4.1 Defined emergency response actions to perform life saving or ac-cident-mitigating functions are expected to result in radiation ex- .
| |
| ' l posures in excess of the 10CFR20 limits. 10CFR20 limits are provided for reference in Attachment 7 2.
| |
| 50 PROCEDURE l
| |
| NOTE The Emergency Coordinator is the only indivi-dual who can authorize emergency exposures in excess of 10CFR20 limits.
| |
| l 2
| |
| i
| |
| | |
| Em rgancy Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 2 and Controls 5.1 The Emergency Coordinator will determine the need to perform specific tasks which are anticipated to result in exposure in excess of 10CFR20 limits by evaluating the risk of not performing the tasks against the anticipated exposure.
| |
| NOTE To the extent practicable, the Emergency _
| |
| Coordinator will confer with NRC personnel prior to authorizing exposures in excess of 10CFd20 limits. It is recognized that coordination with the NRC may not be possible in all cases due to the nature of the situation.
| |
| 52 The guidelines for emergency exposure are:
| |
| Organ Corrective Action Life Savina ,
| |
| Whole Body 25 rems 100 rems Extremities 100 rems 300 rems Thyroid 125 rems No limit 53 Personnel selected to perform the task should be chosen in ac-cordance with the following guidelines:
| |
| 5.3.1 Individual is a volunteer.
| |
| 5 3.2 Individual is generally familiar with the radiological consequences of the exposure. ,
| |
| 533 Fertile females shall not be used.
| |
| 534 Individual has not previously received emergency exposure.
| |
| 535 All other things being equal, and capabilities being the same, the :
| |
| oldest individuals should be selected for these activities.
| |
| 3
| |
| | |
| Emergency Plan Implementing Procedure EP-2-030 Energency Radiation Exposure Guidelines Revision 2 and Controls ,
| |
| 5.4 Personnel shall not enter any area where dose rates are unknown or unmeasurable with dose rate instruments.
| |
| 5.5 All reasonable precautions for minimizing the radiological consequences of the emergency action shall be taken (i.e.,
| |
| protective clothing, respiratory protection, thyroid prophylaxis, etc.).
| |
| ~
| |
| 5.6 The Emergency Coordinator (or designee) will complete Section A of Attachment 7 1.
| |
| NOTE
| |
| : 1. The Emergency Cocrdinator is the only indivi-dual who can sign Section A authorizing the emergency exposure.
| |
| : 2. Although it is preferable to perform and doc-ument these steps prior to the exposure, the
| |
| ! Emergency Coordinator may verbally authorize the exposure and complete the documentation at a later time.
| |
| 57 The individual who will receive the emergency exposure will complete Section B.
| |
| 5.8 The Radiological Controls Coordinator will complete Sections C and D. Follow-up medical evaluation will be in accordance with the following guidelines:
| |
| 5.8.1 If an individual's dose equivalent exceeds 10 rems for the wnole body, 30 rems for the thyroid, 60 rems for the skin and/or 150 rems to an extremity, the details of the exposure incident shall be brought to the attention of a physician. The physician shall determine the need, extent and nature of any clinical, biological or biochemical examinations.
| |
| 4
| |
| | |
| Emcrgsney Plan Impicmsnting Procedure EP-2-030 Ecergency Radiation Exposure Guidelines Revision 2 cnd Controls 5.8.2 If an individual's dose equivalent exceeds 25 rems for the whole body, 75 rems to the thyroid, 150 rems for the skin and/or 375 rems-for an extremity, the individual shall be examined by a physician. The physician shall determine the need, extent and nature of any clinical, biological or biochemical examinations or necessary medical surveillance.
| |
| 5.9 The Radiological Controls Coordinator shall designate an individual ,
| |
| responsible to complete the exposure evaluation and complete a full report on the emergency exposure, including necessary reports in ac-cordance with 10CFR20.403 6.0 FIN AL CONDITIONS All sections of Attachment 7 1 are complete and assignments have been made for completing necessary exposure reports.
| |
| 70 ATTACHMENTS 71 Emergency Exposure Authorization Form 72 10CFR20 Limits ,
| |
| i i
| |
| i l
| |
| I I
| |
| i 5 .
| |
| h
| |
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| i EMERGENCY EXPOSURE AUTHORIZATION FORM SECTIOtl A .
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| : 1. Name (to receive exposure):
| |
| Soc. Sec. No.:
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| i
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| : 2. Individual TLD Number: Employer /LP&L Department:
| |
| 3 Task (s) to be Performed: _
| |
| : 4. Date of Authorization: Authorized Limit: .
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| ; 5. Conditions:
| |
| l Individual is a volunt'eer or professional rescue person.
| |
| Individual is broadly familiar with radiological consequences or ex-posure.
| |
| Fertile females shall not take part (Reg. Guide 8.13).-
| |
| [
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| i Individual has not. received an emergency exposure before.
| |
| Dose rates in area are known/ measurable.
| |
| Life sa.ving action?
| |
| Corrective action?
| |
| : 6. Energency Coordinator: (signature)
| |
| SECTION B l
| |
| : I have been briefed in the radiological consequences of the proposed Gmergency exposure, and I have volunteered to perform the emergency ceasures during which I will receive the emergency exposure.
| |
| l 7 Signature: Date:
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| l
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| \ .
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| i i
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| l l
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| EP-2-030 Revision 2 6 Attachment 71 ( l of 2 )
| |
| | |
| EMERGENCY EXPOSURE AUTHORIZATION FORM SECTIOH-C (Attach exposure evaluation)
| |
| : 1. Dose equivalent assigned for entry: _.
| |
| : 2. TLD/ Dosimeter Results: --
| |
| 3 Bioassay Results:
| |
| l.
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| : 4. Medical Evaluation / Action:
| |
| Doctor: +
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| : 5. . Radiological Controls Coordinator: Date:
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| SECTION D l 1. Disposition (Allow additional exposure, restricted access, etc.):
| |
| D =4 l . .
| |
| l
| |
| : 2. Individual assigned to follow up reports (s):
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| 3 Radiological Controls Coordinator: Date:
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| EP-2-030 Revision 2 7 Attachment 71 (2 of 2 )
| |
| | |
| 10CFR20 LIMITS
| |
| - Orcatii Limit cer Calendgr_gyarter Whole Body 1.25 rems (3 rems with completed NRC Form 45)
| |
| Extremities 18.75 rems Skin 7 5 rems Thyroid and other organs due 520 mpc-hours to inhalation exposure i
| |
| cTotal accumulated. occupational dose-not-to exceed 5 (N-18) rems where
| |
| #N" equals the individual's age in years at his last birthday. -
| |
| EP-2-030 Revision 2 8 Attachment 7 2 (1 of 1)
| |
| . m .. , _ . . _ . . - , , , - . , . - -
| |
| | |
| TNATERFORD 3 SES PLANT OPERATING MANDAL LOUISIANA POWER & LIGHT UNNY EP-2-031 POM VOLUME. 18 REVISION 3 POM SECTION 2 APPROVAL DATE: SEP 191983 EFFECTIVE DATE: Fuel Load EMERGENCY PLAN DIPLEMENTING PROCEDURE IN-PLAlfr RADIOLOGICAL CONTROLS -
| |
| AND SURVEYS DURING EIIERGENCIES LP&L W-3 RECORDS UNCONTROLLED Du !<!Or 09E IN ANY SAFETY-REL/nTED TEST 8NG, COPY l*
| |
| fv.AIN ItiiANCE, OH OPERATIONAL ACTIVITY PORC Meeting No. f3 - 3/;
| |
| Reviewed: -
| |
| [d , g PORC Chairman ,
| |
| DM i App roved: .h-%1..,k O S\
| |
| l Plant Manager-l Nuclear l
| |
| l l
| |
| l
| |
| | |
| WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. -
| |
| Title -
| |
| Effective Date &t IM (if different from approval date) .,3 - ,
| |
| t'n-nlata 1. B. or C A. Change No. * /s Revision No. L
| |
| ~
| |
| B. ,
| |
| C. Deletion A//I BRAMnN FOR CHAMMR. RETTMTOM_ OR DELRTTOM -
| |
| / : n '- , ., -~
| |
| A,n,, ,-
| |
| REQUIRED SIGNATURES -s.
| |
| Originator -
| |
| -M - Date _- -
| |
| Technical Review MNd#k '
| |
| Dato 1 // J/r').
| |
| / /
| |
| SAFETT EVALUATION Does this change, revision, or deletion: YES NO
| |
| : 1. Change the facility as described in the FSAR7 "
| |
| : 2. Change the procedures as described in the FSAR7- -'
| |
| : 3. Conduct tests / experiments not described in the FSAR7 <
| |
| : 4. Create a condition or conduct an operation which ex-coeda, or could result in exceeding, the limits in Technical Specifications?
| |
| [ If the answer to any of the above is yes, complete and at-I tach a 10 CFR 50.59 Safet aluation checklist.
| |
| Safety Evaluation I //N Date *[~ M d Group /Dep't. Head Mo dew N M M e' d Date MN/f3 r
| |
| Temporary Approval
| |
| * Date (NO3)
| |
| Temporary Approvale Date QC Review i" d!! % / Date 'I ;-T ^
| |
| PORC Review N M 8 b ,
| |
| * Data f /Mf3 Meeting No. W 4:
| |
| Plant Manager-Nuclear Approval /'- " ' '
| |
| Date ' -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| l UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
| |
| | |
| Emergency-Plan' Implementing Procedure EP-2-031
| |
| 'In-Plant Radiological controls Revision 3 and Surveys During. Emergencies TABLE OF CONTENTS
| |
| : 1. 0 ' PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| 30 RESPONSIBILITIES 4.0 INITIATING CONDITIONS-5.0 PROCEDURE 6.0 FINAL CONDITIONS 70 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 3 1-12 Revision 3 l
| |
| i
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| . 1
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| | |
| v
| |
| ' Emergency Plan Implementing Procediare EP-2-031 In-Plant Radiological Controls Revision 3 and Surveys During Emergencies
| |
| ~
| |
| ' 1.0 PURPOSE To provide guidelines for the implementation of the in-plant radiological controls program during emergency conditions, which will ensure the protection of Waterford 3 emergency workers while performing emergency-maintenance or operations activities.
| |
| | |
| ==2.0 REFERENCES==
| |
| 2.1 EP-2-030, Emergency Radiation Exposure Guidelines and Controls
| |
| ~
| |
| 2.2 EP-2-032, Monitoring and Decontamination 23 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation ,
| |
| 2.4 EP-2-130, Emergency Team. Assignments 2 5 [HP-1-110, Radiation Work Permits 2.6 -HP-2-201, Radiation Survey Techniques 27 HP-2-210, Contamination Survey Techniques 2.8 HP-2-215, Airborne Survey Techniques f 2.9 HP-2-216, Air Sample Analysis and Evaluation 2.10 HP-300 Series of Procedures, Instrument Operation 2.11 =EP-3-040, Emergency Equipment Inventory l
| |
| 2.12 _EP-2-034, Onsite Surveys During' Emergencies 30 RESPONSIBILITIES
| |
| ; The Health Physics Coordinator and/or the Radiological Controls Coordinator is responsible for implementing this procedure.
| |
| 2 1.
| |
| | |
| Emergency-Plan Implementing Procedure EP-2-031 In-Plant Radiological Controls Revision 3 and Surveys During Emergencies 4.0 INITIATING CONDITIONS This procedure is to be initiated upon reaching the following conditions:
| |
| 4.1 One of'the following emergencies has been declared:
| |
| 4.1 ~.1 Alert
| |
| ~4.1.2 Site Area Emergency 4.1 3 General. Emergency and 4.2 The emergency has resulted in radiological problems with the plant and/or 43 In the judgement of the Health Physics Coordinator and/or the Radiological Controls Coordinator, normal Health Physics procedures
| |
| ~~
| |
| alone would restrict.the response . capabilities necessary to mitigate the consequences of the emergency condition.
| |
| 5.0 PROCEDURE 5.1 During emergency conditions, the Health Physics Coordinator and/or the Radiological Controls Coordinator will evaluate the potential
| |
| (-
| |
| radiological hazard within the plant and the maintenance and operaticas necessary to mitigate the consequences or the incident.
| |
| l L 5.2 If, in the opinion of the Healtn Physics Coordinator and/or Radiological Controls Coordinator, a normal Health Physics procedure alone will not support the emergency response in a specific area, the Radiological Controls Coordinator will consider the following l guidelines:
| |
| 1 i .
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| 3
| |
| | |
| l l
| |
| Emcrgoney Plan Implementing Procedure EP-2-031 In-Plant Radiological Controls Revision 3 and Surveys During Emergencies i
| |
| NOTE The objective of emergency radiological controls is to utilize as many of the normal Health Physics l procedures and practices as practical. In many l cases, these normal Health Physics procedures may be used in conjunction with the guidelines in this
| |
| ~
| |
| procedure, depending on the particular emergency l
| |
| situation. If any of the,following guidelines are implemented, normal Health Physics procedures should be reinstituted.as soon as practical. l l
| |
| l i
| |
| 53 The following guidelines are established in a checklist format with i l discussion as to how each should be implemented. The Radiological l Controls Coordinator will determine.which of .the guidelines will be l
| |
| ( implemented. Specific individuals shall be assigned by the Radiological Controls Coordinator as necessary to implement the following guidelines:
| |
| { 5.3 1 General Guidelines for Entry into Potential or Real Radiological Hazard Areas During an Emergency 5 3 1.1 Use good Health Physics practices at all times.
| |
| 5 3 1.2 Use the Radiation Monitoring System for guicance prior to entry into the affected area.
| |
| l 5313 Use proper instrumentation for specific surveys (i.e., R0-2, R0-2A, Teletector, frisker, air samplers, etc.)
| |
| NOTE Pay particular attention to anticipated radiation levels when selecting instrumentation--ensure that the inst. ament has the range needed.
| |
| l l 4
| |
| | |
| Emergency Plan Implementing Procedure EP-2-031-
| |
| ~In-PlantiRadiological Controls Revision 3 and-Surveys During Emergencies
| |
| -5.3 1.4 Enter suspected High Radiation Areas with survey meters on the high scale.
| |
| 5 3 1.5 Prevent' cross-contamination.of equipment, personnel and areas.
| |
| 5'.3 1 .6~ Samples of reactor coolant, containment atmosphere and plant.
| |
| stack may be extremely radioactive. Extreme caution should be exercised when obtaining and handling such samples. In .
| |
| .particular, the need for shielding and extremity monitoring should be considered.
| |
| 5317 For work in very High Radiation Areas, dose rates should be calculated to mR/ minute (or mR/second, as appropriate), stay times should be set', and a timekeeper assigned maintaining com-munications with personnel in the area.
| |
| 532 Access Control 5 3 2.1 Potential Problem: Normal Health Physics Control Point (s) does (do) n'ot~ provide adequate control over access and egress to the affected area due to significant radiological hazards within the
| |
| -Reactor Auxiliary Building, or the affected area includes areas not normally controlled-for radiological purposes.
| |
| l 5 3 2.2 Guidelines: Through evaluation of the operational and radiological aspects of the incident, reestablish Health Physics
| |
| ! Control Points to encompass the entire affected area. For areas .
| |
| of significant radiological hazard (greater than 1 R/hr, greater than 100 times MPC), evaluate all possible access routes into l the area and ensure that each is positively controlled by:
| |
| i l.
| |
| A. Posting personnel to restrict access B. Locking access doors or gates l
| |
| 5
| |
| | |
| ' Emergency Plan Implementing ~ Procedure E?-2-031 In-Plant Radiological Controls Revision 3 and Surveys During Emergencies l
| |
| 533 Health Physics Control Point Operations 5 3~3 1
| |
| . Potential Problem: Individuals entering through control points are not fully aware of radiological hazards involved in their specific task.- Time does not allow for planning meetings, mock-up training, etc., due to emergency conditions.
| |
| l~
| |
| 5332 Guidelines: Health Physics Control Point personnel will brief '
| |
| individual (s) prior to entering the affected areas, using At-tachment 7 2 of EP-2-130. The briefing will ensure that the proper radiological control materials are being utilized, the individuals entering are fully aware of the potential radiological hazards they may encounter, and the methods or minimizing exposure are understood. Health Pnysics Control Point personnel will debrief personnel exiting the affected area, using Attachment 7 2 of EP-2-130. The debriefing will identify-the exposure received by each individual. Contaminated personnel.are identified and directed to appropriate decon f aci'11 ties for decontamination in accordance with EP-2-032, and high dose rates and other radiological hazards encountered during the entry are identified and documented.
| |
| 534 Radiation Work Permits
| |
| ; 5 3 4.1 Potential Problem: Normal administrative requirements of RWP's would restrict critical operations and maintenance activities aimed at mitigating the consequences of the emergency.
| |
| 5 3 4.2 Guidelines: RWP's will be utilized to document each entry into the'affected. area, identifying each individual who made the entry, the purpose of the entry, the exposures received by each individual and any other relevant information. The RWP's may be controlled by the Health Physics Control Point personnel and used in conjunction with the briefing and debriefing forms, At-( tachment 7 2 of EP-2-130.
| |
| l L 6 l
| |
| | |
| Emergency Plan Implementing Procedure
| |
| . EP-2-031 In-Plant Radiological Controls Revisien 3 and Surveys During Emergencies NOTE RWP's will normally be filled out prior to entry into an affected area when time permits.
| |
| During an emergency when time does not permit the filling out of an RWP, the briefing, debriefing and Health ohysics Control Point Log will be used 14 lieu of an RWP until an RWP can be completed.
| |
| 5.3 5 Respiratory Protection 5 3 5.1 Potential Problem: Time is not available or the hazard is changing too rapidly to allow air sampling prior to entry to determine appropriate respiratory protection.
| |
| 5 3.5.2 Guidelines: Maximum available respiratory protection shall be utilized provided it does not seriously restrict the emergency response or cause significant increase in external exposure.
| |
| Each individual or, as a minimum, one individual per group should be given a breathing-zone air sampler during the entry.
| |
| All individuals entering the affected area shall be identified for subsequent bioassay analysis to determine internal exposure.
| |
| 5 3.6 Bioassay Program 5 3 6.1 Potential Problem: Significant numbers of personnel have entered areas with high airborne activity and should be rapidly evaluated to determine if medical assistance is necessary and to determine internal dose commitment.
| |
| 5 3 6.2 Guidelines: Personnel exiting areas of significant or unknown airborne radioactivity should be directed to the individual responsible for bioassay analysis by Health Physics Control Point personnel. Lists of personnel requiring bioassay analysis shall be forwarded by the Health Physics Control Point personnel 7
| |
| | |
| Emergency Plan Implementing Procedure EP-2-031 "In-Plant Radiological Controls Revisien 3 and Surveys During Emergencies to the individual responsible for bioassay to ensure all individuals requiring evaluation are properly evaluated. For individuals who have received uptakes in excess of Waterford 3 guidelines,, follow-up evaluations will be scheduled. For individuals who have received in excess of 50% of a derived organ _ burden, the Radiological Controls Coordinator and Health Physics Coordinator shall be notified to determine the need for _
| |
| medical consultation. Any individual who has received an uptake in excess of Waterford 3 guidelines should be restricted frem reentry into the affected area.
| |
| 537 Radiological Surveys l 5371' Potential Problem: Surveys of affected areas cause significant-
| |
| ! exposures to Radiological Controls personnel, or dose-rate and airborne activity concentrations are changing too rapidly to re'ly on previous data for purposes of estimating exposures on L subsequent entries.
| |
| 5.3 7 2 Guidelines: Surveys will be performed in conjunction with entries for specific maintenance and operations tasks. Health Physics Control Point personnel shall ensure that appropriate monitoring devices are being utilized. Dose rates encountered during the entry will be identified during the debriefing of personnel. During entries, breathing-zone air samplers can be utilized to identify airborne activity levels, or low-volume air samplers may be placed in areas by one team and retrieved during subsequent entries. All information shall be documented on routine survey forms.
| |
| l-l 8
| |
| | |
| l 1
| |
| Emergency Plan Impleranting Procedure EP-2-031 In-Plant Radiological Controls Revision 3 and Surveys During Emergencies NOTE Dose rates and airborne activity levels deter-mined during one entry should be considered as estimates for future entries but shall not substitute for continuous monitoring during those subsequent entries. _
| |
| i i I
| |
| 5 3.8 Available Health Physics Technicians During an Emergency '
| |
| 5 . 3 . 8 .1 Potential. Problem: Limited number of qualified Health Physics technicians to support emergency activities.
| |
| 5 3 8.2 Guidelines: The Radiological Controls Coordinator should give guidance to entry teams to control personnel exposure through means of good health physics practices as'follows:
| |
| A. Provide good coverage on a job in a High Radiation Area by providing initial surveys and going to a lower radiation area wnile still maintaining necessary degree of assistance to the entry team.
| |
| B. Maintain up-to-date exposure status of each Health Physics technician upon entry into High Radiation Areas and' areas where habitability conditions are unknown, and in handling of high activity samples.
| |
| C. Provide Health Physics coverage for initial surveys and issue instruments to other qualified self-monitors in lieu of Health Physics technicians if they are not entering an area that has a high potential for changing radiological conditions.
| |
| D. The Radiological Controls Coordinator will provide the maximum radiological protection during emergencies through means of shift coverage based on work requirements and assigning Health Physics technicians to responsible positions when needed.
| |
| 9
| |
| | |
| Emergency Plan Implementing Procedure EP-2-031 In-Plant Radiological Controls Revision 3 and Surveys During Emergencies NOTE ,
| |
| If additional Health Physics technicians l will be needed beyond normal staff,'the
| |
| ~
| |
| . Radiological Controls Coordinator should notify the Health Physics Coordinator as soon as possible so that additional tech- .
| |
| nicians may be obtained from outside sources through existing agreements.
| |
| NOTE Work to be performed, available qualified technicians, and personnel exposures may limit Health Physics job coverage. Priorities for assignment of Health Physics personnel are based upon the work to be performed as directed by the Emergency Coordinator and coordinated with the OSC Supervisor, Health Physics Coordinator and Radiological Controls Coordinator. Work affecting personnel safety and/or accident mitigation will generally take precedence over other work (see EP-2-130) .
| |
| 539 Radiological Instrumentation 5391 Potential Problem: Survey instrumentation used during emergencies may cause depletion of the normal available inventory on the -4 elevation of the RAB.
| |
| 5.3 9.2 Guidelines: When normal supplies of radiac instrumentation dwindle, utilization of the dedicated emergency radiac instrumentation located in the OSC locker should be considered.
| |
| 10
| |
| | |
| Emergency Plan Implementing Procedure EP-2-031 In-Plant: Radiological Controls Revision 3
| |
| -and Surveys During Emergencies l 5 i
| |
| These dedicated ~ instruments are listed in the attachments to ,
| |
| EP-3-040.
| |
| If additional instrumentation is needed, the Radiological
| |
| -Controls Coordinator should notify the Health Physics Coordinator as soon as possible so that additional instruments may be=obtained from outside sources through existing agraements.
| |
| . 5310 Onsite Surveys 5 3 10.1 -Potential Problem: Emergency conditions (such as release or radioactive materials) may cause changes in radiological status in onsite areas normally considered unrestricted and/or free or .
| |
| radiological concerns.
| |
| t 5 3 10.2 Guidelines: Surveys should be made to arrive at habitability requirements for occupied areas and ascertain site environmental. conditions. -Specific guidance on onsite surveys .
| |
| is given in EP-2-034.
| |
| 54 Requests for manpower assistance from onsite support personnel shall be made by the Radiological Controls Coordinator to the Operational Support Center.
| |
| 5.5 -If additional technician support or radiological control supplies ,
| |
| beyond the resources of Waterford 3 are needed, the Radiological Controls Coordinator shall notify the Health Physics Coordinator, who will in turn request the assistance through the Radiological Assessment Coordinator at the EOF. The Emergency Coordinator and EOF Director shall be informed of the request.
| |
| 6.0 FINAL CONDITIONS 6.1 All normal Health Physics procedures (modified, if required) are implemented.
| |
| 6.2~ A recovery Health Physics organization is established and implemented, if necessary.
| |
| 11
| |
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| I l
| |
| l
| |
| .an Implementing Procedure EP-2-031 adiological Controls Revision 3 ys During Emergencies ,
| |
| aTTACHNEMTS NONE O
| |
| O 12
| |
| ~
| |
| | |
| WATERFORD 3 SES TW PLANT' OPERATING MANUAL LOUISIANA POWER & LIGHT NibN POM VOLUME ie EP-2-032 POM SECTION 2 REVISION 4 Emergency Plan Implementing Proceduras Monitoring and Decontamination LP&L W-3 RECORDS UNCONTROLLED COPY DO i4C'T U4E IN /elY GAFETY---RELATED TESTING, Mali (I uiANC't, OH OPERATIONAL ACTIVITY PORC Meeting No. 23-52 Reviewed:
| |
| Md/d_ ___
| |
| PORC C4 airman Approved: 0:Je Ad / $f Plant Manager-Nuclear Approval Date Fuel Load
| |
| . Effective Date
| |
| | |
| l
| |
| ~
| |
| j r
| |
| WATERFORD 3 SES ~
| |
| PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Prcoedure No. d #~ N 32 Title ~/'L h - c-~ Ib "A~~ L ..
| |
| t Effootive Date A '' M'I (if different fro'it approval date) t%-nimes 1. a a= c A. Change No. ^1 i B. Revision No. d '
| |
| dA l C. Deletion REASON FOR CHAMGE. REYISIDE. OR DELETIDM .
| |
| 7 L,~. .J. .,w.. 4C,S ,
| |
| REntIIRED SIGNATURES /-6-7 0 Originator ( A M A J LJ L - Date Mb '>
| |
| Tcchnical Review M N M a<S U Date /N7783 SAFETT ETALUATION -
| |
| Does this change, revision, or deletion: TE3 NO
| |
| : 1. Change the facility as. described in the F3AR7 _
| |
| '/
| |
| : 2. Change the procedures as described in the F3AR7- '
| |
| : 3. Conduct testa /experimenta not described in the F3AR7 - '
| |
| : 4. Create a condition or conduct an operation which ex- -'
| |
| coeda, or could result in exceeding, the limits in Technical Specificacions?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50 59 Safety Ev tion checklist.
| |
| 32fety Evaluation GM M Date /Z ~7!83 Grcup/Dap't.. Head Review h e Md Date /?IvhT __
| |
| Temporary Approvni' Date (NO3)
| |
| Temporary Approvule Date QC Review M dtM~ d- Date / - t- Cn PORC Revie NSA- Date / S -P[/ Meeting No.
| |
| Plcat Manager-Nuclear Approval Date -
| |
| 'Tempcrary approval must be followed by Plant Manager-Nuclear approval '
| |
| within 14 days.
| |
| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
| |
| ._,,_..,.~_.--,,.vm-- -. - , , ,.y..c.--, -
| |
| v.-- -r--*-- - - - - - - - * - - - ' " ' - - ' ' - - ' '
| |
| | |
| . Emergency Plan Implementing Procedure EP-2-032 Monitoring and Decontamination. ,
| |
| Revision 4 TABLE OF CONTENTS 1.0 PURPOSE" 2.0 .REFERESCES
| |
| -3.0 RESPONSIBILITIES 4.0 ~1NITIATING CONDITIONS 5.0 ' PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Skin Decontamination Record (2 pages) 7.2 Vehicle Decontamination Record (1 page)
| |
| LIST OF EFFECTIVE PAGES Title Revision 4 1-8 Revision 4 9-11 Revision 3 i-1
| |
| | |
| Emergency Plan Implementing Procedure EP-2-032 Monitoring and Decontamination Revision 4 1.0 PURPOSE To provide guidance and instruction for the decontamination of Waterford-3 personnel, vehicles, areas and equipment and for the documentaion and follow-up on those contamination incident during emergencies when the normal pl' ant Health Physics procedures can no longer be effectively implemented.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 EP-2-031, In-Plant Radiological Controls and Surveys During Emergencies 2.2 EP-2-150, Emergency Plan Implementing Records 2.3 EP-3-040, Emergency Equipment Inventory 2.4 Emergency Management Resources Book l
| |
| 2.5 HP-2-704, Personnel Decontamination 2.6 HP-1-220,-Bioassay Program 2.7 RW-2-600, General Area.and Cubicle Decontamination 2.8 HE-1-219, Radiological Posting Requirements 2.9 HP-2-201, Radiation Survey Techniques 2.10 HP-2-210, Contamination Survey Techniques -
| |
| 2.11 HP-1-201, Scheduling of Health Physics Sucveys
| |
| , 3.0 RESPONSIBILITIES The Radiological Controls Coordinator is responsible for ensuring the
| |
| ( implementation of this procedure and for advising the Operational Support Center (OSC) Supervisor on the status of contaminated personnel and vehicles. The assigned Decontamination Supervisor is l responsible for implementing the procedure.
| |
| 1 I
| |
| 2 i
| |
| l l
| |
| l
| |
| | |
| ' Emergency Plan Implementing Procedure EP-2-032 Monitoring and Decontamination Revision 4
| |
| -4.0 INITIATING CONDITIONS This procedure shall be initiated by the Radiological Controls Coordinator upon reaching any of the following-conditions:
| |
| 4.1 Under emergency conditions:_ areas, equipment, personnel and/or vehicles are or are suspected to be contaminated.
| |
| 4.2. As directed by the Emergency Coordinator or Health Physics Coordinator.
| |
| 5.0' PROCEDURE 5.1 ONSITE PERSONNEL MONITORING AND DECONTAMINATION .
| |
| 5.1.1 The Radiological Controls Coordinator shall assign an Onsite l Decontamination Supervisor for onsite pers'onnel monitoring and decontamination. This individual can be a Health Physics supervisor, engineer, or ' technician and can eventually be a consulting Health Physicist.
| |
| 5 . '. 2 During emergencies, the primary decontamination facility for Waterford 3 emergency' response personnel is'at the Radiation Controlled Area (RCA) Access Point on the -4 ft elevation of the Reactor Auxillary Building (RAB). A backup facility is located on the +7 ft elevation of the RAB. Monitoring equipment and personnel decontamination kits are located in the Health Physics l
| |
| Laboratory.
| |
| 5.1.3 All personnel with contamination levels in excess of 1,000 disintegraticas per minute (100 counts per minute) as determined l f by a pancake-type Geiger Muller (GM) tube shall be considered I contaminated. '
| |
| 5.1.4 The-Onsite Decontamination Supervisor shall:
| |
| 5.1.4.1 Assign Health Physics Centrol Point Monitors to perform
| |
| [- monitoring of all personnel leaving affected areas.
| |
| l 3
| |
| l l
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| l I
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| | |
| Emergency Plan Implementing Procedure EP-2-032 Monitoring and Decontamination Revision 4 5.1.4.2 Direct Health Physics Control Point Monitors to provide periodic updates and lists of contaminated personnel to the Decontamination Supervisor via PABX.
| |
| 5.1.4.3- Direct all contaminated personnel to be sent to the appropriate --
| |
| decontamination facility.
| |
| 5.1.4.4 Direct emergency response personnel to utilize the techniques of HP-2-704,- Personnel Decontamination, for decontamination.
| |
| ~
| |
| 5.1.4.5 If attempts to decontaminate personnel to levels below 1,0u0 disintegrations per minute (dpm) (100 counts per minute) are unsuccessful, contact the Radiological Controls Coordinator or Health Physics Coordinator for further guidance.
| |
| 5.1.4.6 Record all predecontamination and postdecontamination information on Attachment 7.1, Skin Decontamination Record.
| |
| 5.1.4.7 Return _all records to the Radilogical Controls Coordinator.
| |
| 5.2 0FFSITE PERSONNEL MONITORING AND DECONTAMINATION 5.2.1 The Radiological Controls Coordinator shall assign an Offsite Decontaminati'on Supervisor for otfsite personnel monitoring
| |
| ~
| |
| and decontamination. This individual can be a Health Physics supervisor, engineer, or technician and can eventually be a consulting Health Physicist.
| |
| 5.2.2 For a site evacuation to St. John the Baptist Church or Monsanto Park (depending on plume), personnel decontamination will take place at the assembly area using the portable decontamination kit from the Operational Support Center (OSC). The Decontamination Supervisor shall direct monitoring personnel to bring monitoring equipment from the Health Physics Laboratory.
| |
| 5.2.3 All personnel with contamination levels in excess of 1,000 dpm (100 counts per minute) as determined by a pancake-type GM tube shall be considered contaminated.
| |
| 4 I
| |
| i UW
| |
| | |
| i Emergency Plan Impigraenting Procedure. EP _-032 Monitoring and Decontamination . Revision 4 5.2.4 The Offsite Decontamination Supervisor shall:
| |
| 5.2.4.1 Obtain a portable radio from the OSC HP locker and perform a radio check.
| |
| 5.2.4.2 Direct emergency response personnel to obtain monitoring equipment and portable radios from the OSC HP locker and bring them to the offsite assembly area.
| |
| 5.2.4.3 Assign emergency response personnel to perform monitoring of all personnel entering the offsite assembly area.
| |
| 5.2.4.4 Direct' monitoring personnel to provide periodic updates and a list of contaminated personnel ta the Decontamination
| |
| - Superviso r.
| |
| 5~.2.4.5- Direct all contaminated personnel to be decontaminated with portable decontamination kit using the techniques of HP-2-704, Personnel Decontamination.
| |
| NOTE The Offsite Decontamination Supervisor shall ensure that l a controlled araa (or areas) is established for decontamination activities in order to facilitate contamination control.
| |
| 5.2.4.6 If attempts to decontaminate personnel to levels below I,000 dpa are unsuccessful, contact the Radiological Controls Coordinator or the Health Physics Coordinator for follow-up decontamination.
| |
| 5.2.4.7 Record all predecontamination and postdecontamination information on Attachment 7.1, Skin Decontamination Record.
| |
| 5.2.4.8 . Return all records to-the Radiological Controls Coordinator.
| |
| l l
| |
| ^
| |
| l 5
| |
| l l
| |
| l l
| |
| | |
| Emergency Plan Implementing Procedure EP-2-032
| |
| !!onitoring and Decontamination .
| |
| Revision 4 5.3 VEHICLE MONITORING AND DECONTAMINATION 15.3.1 The Radiological Controls Coordinator shall assign a Vehicle Decontamination Supervisor for vehicle monitoring and decontamination. This individual can be a Health Physics supervisor, engineer, or technician and can eventually be a consulting Health Physicitt. This can be the same individual i
| |
| designated to the Offsite Decontamination Supervisor in Section 5.2. '
| |
| 5.3.2 All vehicles with contamination levels in excess of 1,000 dpm/100 cm 2 shall be considered contaminated.
| |
| 5.3.3. The Vehicle Decontamination Supervisbr shall perform the following l steps if not already done.
| |
| 5.3.3.1 Obtain a portable radio from the OSC Emergency locker and perform a l radio check.
| |
| 5.3.3.2. Assign emergency reponse personnel to obtain monitoring equipment and portable radios from the OSC Emergency locker and -
| |
| bring them to the offsite assembly area. _
| |
| 5.3.3.3. Assign emergency response personnel to monitor all vehicles entering the offsite assembly area.
| |
| A vehicle should not be considered free of contamination unless the vehicle air cleaner has been monitored.
| |
| ^5.3.3.4 Determine a specific location for vehicle decontamination at the offsite assembly area.
| |
| 5.3.3.5 Direct monitoring personnel to provide periodic updates and a list of contaminated vehicles to the Vehicle Decontamination Supervisor.
| |
| 5.3.3.6 Direct all contaminated vehicles be sent to the above location and carefully wiped down with masslinn cloths (or equivalent) 6
| |
| | |
| 4 Emergency Plan and Implementing Procedure EP-2-032 Monitoring'and Decontamination . Revision 4 NOTE
| |
| .Masslina cloths-(cr equivalent) are located.at the Health Physics' Laboratory, Site Warehouse and in portable decontamination kits.
| |
| 5;3.3.7 If a'ttempts to decontaminate vehicles'to levels below I','000 dpa/100ca~ are unsuccessful, detain-the vehicle for additional decontamination.
| |
| 5.3.3.8 - Record all predecontamination and postdecontamination information on Attachment 7.2, Vehicle Decontamination Record.
| |
| S'.3.3.9 ? Return all records to the Radiological Controls Coordinator.
| |
| ." ' 5.4 Instances of f skin contamination involving real or suspected internal
| |
| . deposition of radionuclides will be handled in accordance with
| |
| .HP-1-220, Bioassay Program.
| |
| 5.5 ' Personnel and vehicles shall be considered fully decontaminated when levels are less than 1,000 dpa (less than 1,000 dpm/100cm for vehicles).
| |
| ' 5.6 AREA AND EQUIPMENT DECONTAMINATION
| |
| .5.6.1. Decontamination activities shall be performed in accordance with RW-2-600, General Area and Cubicle Decontaminction, and this procedure.
| |
| 5.6.2 All areas and equipment with contamination levels in excess of 1,000Edps/100cm (100 counts per minute /100 cm )as determined by a pancake-type Geiger Muller (GM) tube shall be considered contaminated.
| |
| 7 k
| |
| ' ul _
| |
| | |
| Emergency Plan-and Implementing Procedure EP-2-032 Monitoring and Decontamination , Revision 4 5.6.3 Contaminated areas and equipment shall be posted and controlled in accordance with HP-1-219, Radiological Posting Requirementa, while awaiting decontamination activities.
| |
| 15.6.4 All contamination survey results are documented on the appropriate forms in accordance with HP-1-201, Scheduling of Health Physics Surveys. Then the results are forwarded to the Radiological Controls Coordinator in accordance with EP-2-150,
| |
| ~
| |
| -Emergency Plan Implementing Records.
| |
| 6.0 FINAL C0FDITIONS 6.1 All personnel and vehicles identified as contaminated have been decontaminated or have been detained for further evaluation and possible additional decontamination.
| |
| 6.2 All areas and equipment requiring decontamination have been decontaminated or identified for further evaluation and possible additional decontamination.
| |
| 6.3 All records are in accordance with EP-2-150, Emergency Plan Implementing Records.
| |
| 6.4 Normal procedures for decontamination are fully implemented.
| |
| 7.0 ATTACHMENTS 7.1 Skin Decontamination Reco-d 7.2 Vehicle Decontamination Record r
| |
| I 8
| |
| | |
| - - - . - - -- - _ .._=. . - . . . - . . - . . - - . _ _ _ . - _ . - . . . _ - . . - . _ ._.-
| |
| t M P- AO-;
| |
| a TYPC
| |
| ! C 7.4 8 * -
| |
| SKIN DECONTAMINATION RECORD f MAME.0F CONTAMMIATED 18008YIOUALs .
| |
| 17y-5 TLD NO.i EMPLOTEN/t.A & 1. OEFT,s ,
| |
| SSSIs .
| |
| DATE AND Tiut OF CONTAmseA, TION OCCURRENCE 8 AWP NC.WCA:UNG UNCER WHEN CONTAM4MATEE STATION LOCATION WNERE CONTAM8KAT10N OCCUAREDs . t
| |
| ( * -
| |
| APPARENT CAUSE OF OCCURASNCSs MP SUPENVISOR NO71FIEDs Cf00 CYES .
| |
| i 1U2Y INWOLVEDs .
| |
| l ~
| |
| l ONS OTE: cf.,s.ic , ,
| |
| MED9 CAL ASSISTA80CE OSTAINEDs ,
| |
| ONO OTES (Espl.i.)
| |
| FAC8AL CONTAMesd4TIONs ONS OYES tes,s.a.>
| |
| l .
| |
| , NASAL SMEARS TAKE188 r
| |
| lNO C TES RT NOSTRE dpsa LT NOSTRfL -
| |
| data i
| |
| : s. ., ATE AND TIME DECON SEGANs N. .
| |
| DATE AND TIME DECON COMPLETEDs .
| |
| b
| |
| ~
| |
| ^^^ ^ ^^'^^ ' i __ ___nC;ACnment t.4 QL GT cf
| |
| | |
| SKIN DECONTAMINATION RECORD (CON'T) !
| |
| . LOCATION OF CONTAMINATION (INQlCATE CN APPROPRIATE SKETCH CR SXETCNES)
| |
| ' 1 CLEFT
| |
| . (* i MAND,5ACX N. ;
| |
| l CRT. HAND, I- O PALM l
| |
| 1 1 .
| |
| I a
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| M C%
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| ($ t [3 ,d i.i I
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| 4 l l >
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| O. }
| |
| cat n.um, SACK
| |
| 'D - ) E
| |
| * C HAND, ,'
| |
| SACE l FACE FRONT SECONTAMINATION DATA OMAumATION LM CONTAMINATION LEVEL DECON TECNNtOUE ANO AFTER COMPLET)NG THIS CONTAMatATED -
| |
| EFORE SMS N , ,gg,, ,g, Sumt W2 TION OECON CTCLE(spel DECON STCLE(spel
| |
| . $4
| |
| #? . * . .
| |
| ~
| |
| I
| |
| .FURTNEN ACTI,0NS REOutREDs Q NO ore 3 SKIN CONDITION AFTER DECON8 (ExPtAnn **
| |
| StOASSAT R50'08 C NO CTES Q W3C Q THYROIO SCAN Q EXCRETA
| |
| ^
| |
| Q OTHEA* .
| |
| REMAAKSs CISTRIBUTION HE ALTM PHYSICS CFFICE(CRIGINAL)
| |
| REVIEWED ST*
| |
| INDIVIQUAL'S EXPOSURE FILE NEALTH PHYSIC 3 ENGINEER .
| |
| * - 2 10 - _ ---.. . A::achment 7.1 (2 of 2)
| |
| | |
| VEIO.E DECCNTAMIMATICM RECORD I
| |
| LICENSE f: COLOR: C'4NER:
| |
| l
| |
| (, 5: MODEL:
| |
| 1F OWNED BY OFF5ITE AGSCY, PRINT DEPARTMENT AND ADDRESS-
| |
| , STATION LOCA"7: L+1stE CONTAMINATION OCCURRED: TYPE OF WORK BEING PERFORMG:
| |
| ( APPARENT CAUSE OF OCCURRENG:
| |
| l .
| |
| L 30DY DMAGE TO VGICLE7 YES N0 l 9EALTH PHYSICS SUP BYi30R NOTIFIED 7 YES NO explain DA E AND TIME DECONTMINATION SEGAN: DATE AND TIME DECCNTAMINATICN C"NPL:.ir.9:
| |
| i d
| |
| hM' r .
| |
| g
| |
| \
| |
| / i-
| |
| * i /eB B
| |
| ,?
| |
| Q. " .
| |
| ,D A
| |
| Q , ,
| |
| U U
| |
| .I '
| |
| DECONTMINATION DATA Contamination Level Decontaannation -
| |
| Centamination Level Before Beginning tsis Technique and After Seg16ning .this Contamination - .-
| |
| Agent Used' Decen Cycle (dge)-
| |
| Location Decon Cycle (dpe) -
| |
| .- l :
| |
| t EURP''"4 ACTICM REQUIRED? Remarks:
| |
| a- 15 MO
| |
| *aVkEt!ED BY:
| |
| (. ._
| |
| i 17-2-032 Revision 3 -
| |
| n Attacnment 7.2 (I cf 1) e
| |
| -----g. . - , - - - y, _ _ ___._--,.__.,.7 ,,,,,,,y,___,.,y- . , , , , , , _ . , ,.,,,__-,_.,.,.______m _ , _ . _ _ , . - . . _
| |
| | |
| WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA -
| |
| POWER & LIGHT
| |
| =?MsvMu POM VOLUME 18 EP-2-033 POM SECTION 2 REVISION 3 Emergency Plan Implementing Procedures Administration of Iodine Blocking Agents LP&L W-3 RECORDS UNCONTROLLED DO NOT U35 IN ANY SAFETY-RELATED TEST;NG, COPY MAINThiNANCE< OR OPERATIONAL ACTIVITY PORC Meeting No. 83-52 Reviewed d.[ // _ w PORC Chairman Approved: j) // !bf Plant Manager-Nuclear Approval Date Fuel Load Effective Date i
| |
| | |
| WATERFORD 3 SE3 PLANT OPE 3ATING MANUAL CHANGE / REVISION / DELETION REQUE3'T Procebre No. G^ 1 - G 15 Title %-~ ~ D ~ . _
| |
| L- 'l ~a8: M-1 Effective Date ' ~ O "~
| |
| (if different from approval date) l t%= n1 sta 1. B. are C A. Change No. 'i B. Revision No. 3 ,
| |
| C. Deletion WI'#
| |
| nranns ran entwar_ nrvision. on art rTrow ,
| |
| h &~ e-v ~J > o J.M , ,~, . & C-l q ',q .
| |
| REQ _UIRED SIGRAEp m /~5'I Y - ;
| |
| Originator YSkbt<AY $la<sNDate /7 *b3 Tcchnical ReviewIMrN /-> Date WA'/M l
| |
| i SAFITT EYALUATION
| |
| ; Does this change, revision, or deletion: TE3 NO
| |
| : 1. Change the fat.ility as described in the F3AR7 _
| |
| /
| |
| : 2. Change the procedures as described in the F3AR7- ._ 4
| |
| : 3. Conduct testa /experimenta not described in the F3AR7 _
| |
| : 4. Create a condition or conduct an operation which ex- '-
| |
| coeda, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 3afety Evaluation checklist.
| |
| Safety Evaluation M MNcM*> Date /t[1 7 Group /Dep't. Head Review Ms / mad
| |
| _ Dato M2 dr7 7
| |
| Temporary Approval
| |
| * Da te (NO3)
| |
| Temporary Approvale Date QC Review Al$ 'WL J- Date / - ! P ''
| |
| PORC Revierd88Id Date bd W Meeting No.
| |
| Pircat Manager-Nuclear Approval . _ . _ Date -
| |
| ' Temporary ap_oroval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2(e
| |
| | |
| Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine. Blocking Agents Revision 3 TABLE OF CONTENTS 1.0 PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 3.0 RESPONSIBILITIES 4.0- INITIATING CONDITIONS
| |
| ^
| |
| 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Thyroid Dose Graph (1 page) 7.2 KI Issue Record (1 page) 7.3 Potassium Iodide Administration Form (1 page) 7.4 Potassium' Iodide Precaution Leaflet (1 page)
| |
| LIST OF EFFECTIVE PAGES Title Revision 3 1-6 Revision 3 7-10 Revision 2 ,
| |
| 1
| |
| | |
| 4-Emergency Plan I.uplementing Procedure EP-2-033 .
| |
| , Administration of Iodine Blocking Agents Revision 3 1.0 PURPOSE To provide guidelines on the administration of potassium iodide (KI) to site personnel to minimize uptake in the Thyroid gland 2.0~ REFERENCES 2.1 NCRP Report No. 55, Protection of the Thyroid Gland in the Event of Releases of Radioiodine ,
| |
| 2.2 IAEA Technical Report No. 152, Evaluation of Radiation Emergencies and Accidents 2.3 Patient Package Insert for. Commercial Packaged Potassium Iodide 2.4 EP-3-040, Emergency Equipment Inventory 2.5~ EP-2-150, Emergency Plan Implementing Records 3.0 RESPONSIBILITIES The Health Physics Coordinator is responsible for the implementation of this procedure. The Emergency Coordinator authorizes the distribution of KI. Use of KI'is voluntary.
| |
| 4.0 INITIATING CONDITIONS
| |
| .This procedure shall be initiat ed upon reaching the following .
| |
| condition:
| |
| Whenever'a calculated iodine dose of 10 rads or greater to the thyroid is likely to be received by an individual.
| |
| 5.0 PROCEDURE 5.1 Determine the need for KI administration by using Attachment 7.1.
| |
| 2
| |
| | |
| Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine blocking Agents Revision 3 NOTE In all cases where airborne contamination is anticipated, proper respiratory equipment should be used.
| |
| 5.1.1 'lerify and record the calculations / measurements / estimates on Attachment 7.3. .
| |
| 5.1.2 Report the results to the Emergency Coordinator.
| |
| 5.2 The Health Physics Coordinator shall advise the Emergency Coordinator on the conditions for and need to administer KI. ,
| |
| 5.2.1 If the thyroid dose is estimated to be 10 rads or greater, consideration should be given to administration of KI.
| |
| 5.2.2 The Emergency Coordinator must authorize the use of KI and designates when and who shall receive KI.
| |
| 5.3 ' Upon authorization by the Emergency Coordinator, the following steps are taken:
| |
| 5.3.1 The Emergency Coordinator designates the individual (s) to administer KI.
| |
| NOTE KI is contained in field monitoring kits and field monitoring teams may use KI in the field.in accordance with this procedure when authorized by the Emergency Coordinator.
| |
| 5.3.2 Individuals to receive KI are notifed to report to the location designated by the Emergency Coordinator for the administration of KI.
| |
| NOTE Assign one or more escorts to transport and assemble the individuais at the designated administration area.
| |
| 3
| |
| | |
| Emergency Plan Iinplementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 3 5.3.3 Individual (s) designated in step ~.3.1 procure KI from those storage locations listed in EP-3 040 and report to the designated administration area.
| |
| 5.3.4 The transport and assembly of those persons to receive KI is verified by the Emergency Coordinator.
| |
| 5.4. ADMINISTRATION OF KI 5.4.1 Individuals to receive KI must read the Potassium Iodide Precaution Leaflet (Attachment 7.4) and sign Attachment 7.3, indicating they have read the leaflet and understand the taking of KI to be _ voluntary.
| |
| NOTE If-possible, KI should be administered approxi-mately one to one-half hour.before exposure for maximum blockage. Final uptake is '-1ved if KI is administered within 3-4 hours after exposure. Little benefit is gained with KI administration 10-12 hours after exposure.
| |
| 5.4.2 'One (1) 130 mg KI tablet shall be issued to each individual to receive KI.
| |
| NOTE Once the KI is taken and the I-131 concentration is verified or the calculated dose determined, the tablets should be issued for a' minimum of six (6) to a maximum of ten (10) consecutive days.
| |
| One (1) tablet is issued each day.
| |
| 4
| |
| | |
| Emergency Plaa Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision.3 NOTE KI shall not be issued to individuals suspected of having iodide allergy as noted in the Emergency Management Resources Book. --
| |
| 5.4.3 KI issue for each day shall be recorded on Attachment 7.2. .
| |
| 5.4.4 Individuals issuing KI shall' complete all records and forward them to the Emergency Coordinator. Records are handled in accordance with EP-2-150.
| |
| 5.4.5 Individuals receiving KI should have a whole body count and/or bicassay analysis at the earliest opportunity.
| |
| NOTE Whole body counts and/or bioassay analysis should be given on a regular basis throughout the KI-issue period to verify the effectiveness of the KI and to estimate dose commitment.
| |
| 6.0 FINAL CONDITIONS 6.1 Each individual whose estimated exposure to radioiodine exceeded 10 rads 'tas been identified and administered KI, as appropriate.
| |
| 6.2 All Potassium Iodide Administration Forms and KI Issue Records are.
| |
| completed, signed / initialed, and returned to the Emergency Coordinator; final disposition has- been performed in accordance with EP-2-150.
| |
| 6.3 Each exposed person has been scheduled for bioassay analysis.
| |
| 7.0 ATTAC4MENTS 7.1_ Thyroid Dose Graph 5
| |
| | |
| T Emergen:y. Plan Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Reyision 3 7.2 KI Issue Record 7.3 Potassium Iodide Administration Form 7.4 Potassium Iodide Precaution Leaflet 6
| |
| | |
| e-. . - - . .. -... - . - - - . _ _ - - . - , _ _ _ - - - . __. -
| |
| 1 .. _._ . . _ ._.
| |
| INSTRUC,TIONS FOR USE
| |
| *-,_-._ i
| |
| " - - l'. Detarsina (estimata or actual) the I-131 airtorne conct tration in the ares (s) of interest. Divide this by the l protection factor of the equipment ssed (if unkncua, l
| |
| use 1). Locata this numoer on the Hori: ental Axis. .
| |
| : 2. Folicw that line vertically until it intarlacts . tith th
| |
| ,'' Horizontal Line frca tne duration of exposure in minuts ;
| |
| (Vertical Axis).
| |
| 2 3. If this point of intarsection is to the left or belev t M.-
| |
| e =cm line curve, the thymid dose is less than 10 rad.
| |
| ,y r .o '~?.
| |
| , t og - - -((TII 4
| |
| J 4. If this point of intarsection is to the right or above
| |
| - i g, .
| |
| line curve, the thyroid dose is greater than 10 rad.
| |
| llb 3 S 5. If this point is on, the line, then the thyroid dose is 10 rad. _
| |
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| t v
| |
| A u-o in-e n-r u4 u -g u-4 u-a - c.
| |
| , . I-131 Concentration Factor / Protection Facto.r
| |
| ~
| |
| EP-2-033 Revision 2 - 7 Attachment 7.1 (1 of 1) ;
| |
| | |
| l.-
| |
| 7 C ISSIE RECORD -
| |
| _e l
| |
| - e
| |
| .,> EI Adadaistration l g y 3 3 10 -
| |
| 3 3 4 5 1 Data _l Data Data Data Date Date Data Data Data Date Int. Int. Int. Int.
| |
| Int. Int. t Int. Int. Int.
| |
| Int. i e l 7
| |
| Name l _
| |
| ss N u .
| |
| Hamm .
| |
| ~
| |
| M Nw Nemas .
| |
| Ja
| |
| . 46 4 g M MM Ncmas '
| |
| z- .
| |
| 35 No.:
| |
| Names i Nemes SS No.: _
| |
| M
| |
| - =====
| |
| SS NN - mammmmum- - mammmesummme summmes Names SS N o.: .
| |
| - . g' f ss No.: (.. } ,
| |
| [
| |
| P-2-033 Revision 2 -
| |
| .. s Attachment 7.,2 (1 of 1 e
| |
| ,-- w ,
| |
| r----+----,TT 4 v.sw -g eyy,+% -~ww w - .,,-,,m--m,.,,,,_m.--- ,, - wm
| |
| | |
| POTASSI"M IODIDE ADMINISTRATION FORM Name of Exposed Individual .
| |
| Last Middle First l Social Security Number - -
| |
| LP&L Badge- Number -
| |
| Duration of Exposure Minutes Jaci/cc in Air I-131 Concentration Estimated t
| |
| Thyroid Dose },,10 RAD / <10 RAD (Check One)
| |
| Date of Exposure Respiratory Protection Worn During Exposure Yes No PF Known Iodide Allergy / Previous Allergic Reaction Yes No l
| |
| I verify that I have read and understand the precaution leaflet and .
| |
| ( understand that taking thyroid' blocking agent is voluntary.
| |
| i' l
| |
| /
| |
| Signature of Exposed Individual / Data Potassium Iodide tablets issued by:
| |
| /
| |
| Signature of First Aid Team Member /Date NOTES:
| |
| i N
| |
| l EP-2-033 Revision 2 9 Attachment 7 3 (1 of 1) i
| |
| | |
| . 'POTASSItM IODIDE PRECAUTION 1. EAR.ET 1
| |
| mow porAsams momEWons C= tam f mo el 5. dim. hei, ye= thymd siendMw?
| |
| = krisha. es '
| |
| ,,s m ,em'w e., ,.
| |
| pample sus the insime they need freum fases. Ese issumed sait, or san.Theshyred mme = hidoeir a a.s e a smisma.
| |
| ' Im a = mal = a==s==r. r=d=a8'* 3=8== ==r k em3==d 3=
| |
| THYRO-8 LOCK" the W. This ==a==mi may be basehad w seeGemed. Is mer
| |
| =ese the thyved sined and dammes is.The samass wenid pre.
| |
| ,,,,, beidr uma samit for ream. Os1ds= == =uss meir te n =
| |
| If yes take ponensium Indide,1s wa asep year thysoid simed.
| |
| vamms amesousnou #
| |
| us.P. This redeems the chases thus h====8=8 redisassive indise wE asser the thysoid sland.
| |
| I WHO SHOULD NOTTAME PGTASSENs IODIDE 3E FOTAEEIU38 IODIDS ONLY WWEN POELIC Theonly pompis who shsmida' ss take peaaamine iends ase people ,
| |
| l ALT 3E OFFICIALS TELL YOU. IN A RAIMATION who huser ther are aEaram no imede. Yes mar tahm &
| |
| nennesCT. mADIO4cTIVE toDINE COULD sE ledideouse M yes ase enidag sandshuss far a thyseid psehise(for , j
| |
| * w*=*n UrIO TEE AIE. POTASIEUM IOD3DE IA amample, a thyveld hermans er ==skhyuuid dregi. Presumes and 331QF 10DINEl CAN EEIJ PSDIECT105. mursingismasas and behime and childres may aise talso this drug.
| |
| YOU ARE TOLD TO TAEI TE!1MEDICDfE. TAEE IT HOW AND WHEN TO TAKE POTA333 Ens ICCICE EE T23EE EVEET 24 HOUES DO NOT TAXE IT MORE Potammlues Iedido shemid be taham as seen as pensible agar PTEN. h803E W1LL NOT EELP YOU AND MAY D5 puhEs heelsk entairds tar yen.Yes shemid taissemedeseevesy 24 '
| |
| TEASE THE EZIK OF SIDE'EFFECTK. DO #07 TAKN hemsn. Mase wE mes help yes bessene the thyrmid as -beid'* es. '
| |
| (23 DEDO I.F 70sT KN05F YOF AAS E F1h8N <
| |
| 70 W Emiend assammes d ledom. Larger deems wa Imareams the risk .
| |
| ines' (SEE SIDE EFFECTS BELOWJ et side essans. Yes we prehehir he said ass ta mains thedrag fee mese the 10 days. l SCE EFFECTS ;
| |
| I UsmEr, side admes of pseums iodido happse whos people IMOICATIONS tahs bisher deems for a leeg tien. Yan should be enseh! mes to g, o nIacEING IN A aADIATION msERGBICT . take mee sham the ressammedad dose er take is far lameur them )
| |
| N1 yes ase told. 51dee5meen assumiilesir beamuse of the low done and l
| |
| the shaus tien yee we be saidesthe drug.
| |
| ggtecfteses.POR USE .
| |
| Pusmible side edCases feminde shim sambus, sammEleg of the saEvery hevely as diremend by Seado erlemmi pahEs health aushedsimo im sinada, and "5eema"t=== amine sesse. beambst mensk and steams.
| |
| me seems d oredissianamargamar. asse temak and smsen, syumpanums ed a humd eeid. and senseimses DOSE M apesandderhul.
| |
| ahiness ADULTS Aug <=rre.nment TEAEoy A ise pasple have an eEsegis reassium with amuse ===8=== syemp.
| |
| ACE OR OLDES: One m tables ames a tamme.Theseasund be fever and jelms palma, or souEles of pois of ,
| |
| day.Crashier senEehildsum. .
| |
| the faseand body and as timmes snouse eheremens of beenthes- (mis- ~
| |
| l EABIES UNDER 1 YEAR OF AGE lagImmmsamme mademiassamaise. j OmohmM QAW tahlus amas a day. Crush '
| |
| Taking imede mer rarely mese - - My of the thyroid lhan' simed, andsseusivity d the thyveid glead, er emiersamens W the Beimeles ADUI .TS AND CHILDREN 1YEAROF tnyroid sinad tsmiest, AaB On OLDEpi Add a drope to ,
| |
| halfsimmedEsyddanddrinkanskdmy. ,
| |
| WHATTO 00 !P SOE EPpWCTS OCCUR )
| |
| EABIES UNDER 1 YEAR OF AGEt If the side dInses ase savese er N you have en allarsis remsk Add 3 deues se a ammE assues ed Equid emmeeday.
| |
| semp taidag pasasalmas Indida.Them. E pommible, enE a desser er -
| |
| ymnse hemism anskaster forinsamanimen.
| |
| bar.gdansse Ansur Tahs ser le dare emises dhessed seherwise .
| |
| tv ==. . w.mt ,.hEs haah .= hew =. Mc W 58ppuRD
| |
| 'ammissesse Endsessneempammes hmenesets andsregy TETBt>BLOCEm TABLETS (Feemasinun Iodida. U.S.FJ hat.
| |
| b m=75. Esup emmentaur tishek elemed and preassa hem Eska, ties si H sabines OfDC ass 74ensal Easin whdem somed, suured De ans ums theseemstunNtappemus hussadah ts the assaises the tahima aumenius las og psamamimm iseda, bensin. . TEYEOSIACEM SOLIFr!ON (Penessium 2 fodde Selmeism.
| |
| U.S.FJat atn S.asJ eNm _ _ dspammin WAmaMe esdes(MDCosm si.Esshdeepamtaims21 mispsammene g
| |
| ' Ameskum ledids esmid ass ne mend my paspie aihrsfe = sedda ledida.
| |
| ' Easy est of the sansk ad ehEdren. In ames of soudsee er aEmals reassism, as,emas a physision er the pahEs h==hh ausherier. wau.acst.asonatosuus m.mau. m onscarmus ca.,.e- m asc.-
| |
| ,z TNTao.sLOCxm TABLET sensaias 1ao =c af eransury, see Jesmer casta unledida,
| |
| , w . hey.dTNYnO.sLOCxm SOLUTION cunemme 21 meof g,,,,,,,,,,,,,,, m poenseium1seda.
| |
| EP-2-033 Revision 2* 10 Attachment 7.4 (1 of 1)
| |
| I .
| |
| l .
| |
| ,--,-~,.-,,---,.,,.,.w.~,.r,- -
| |
| --.,,-,.r--m,.- em., -- - ,--- ,.,- _ _ - -
| |
| | |
| WATERFORD 3 SES
| |
| ._ PLANT OPERATING MANUAL l OUISIANA POWER & LIGHT
| |
| $$hNkN POM VOLUME in EP-2-034 POM SECTION 2_ . REVISION 1 Emergency Plan Implementing Procedures On Site Surveys During Emergencies LP&L W-3 RECORDS Oa ' -
| |
| UqhnqMTP.0LLED h'- m' e-so ns=o-w]OV -
| |
| DO Ng g u E IN AN' OPsRATIONAI. ACTIVtTY MAINTENANCE, l
| |
| l PORC Meeting No. 87-52 Reviewed: A((/Mbc_
| |
| PORC Chairman Approved: 1 I Plant Manager-Nuclear Approval Date Fuci Load Effective Date 1
| |
| l
| |
| - e ___.._. _
| |
| | |
| WATERFORD 3 SE3 -
| |
| PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUES'T .
| |
| Prcoedure No. tN ~' ' 0'3 '' Title r - L. An . w 2 - -~ G ~ .
| |
| vx :
| |
| Effective Date E >' I'M (if different from approval 'date) eaantata 1. R. er c.
| |
| A. Change No. ^d'l
| |
| : 3. Revision No. /
| |
| C. Deletion ^A" l nennna ran enmuer_ nrvisTan_ on nrtrtTom .
| |
| k ~ *w *-s r L. L.C Lus..s G...
| |
| t.
| |
| . ~6
| |
| . w. .m l
| |
| meanTurn stewArnars
| |
| ? ') -
| |
| pg.;
| |
| p% i l Originator [ I M M b 'l l I w o Date /2-2 7 M l Tcohnical Review MMdd Date / ? - E ~7 - F 3 i
| |
| SAFETT ETALUATION Does this change, revision, or deletion: TE3- NO
| |
| : 1. Change the facility as described in the F3AR7
| |
| : 2. Change the procedures as described in the FSAR7-
| |
| : 3. Conduct tests / experiments not described in the F3AR7 i
| |
| : 4. Create a condition or conduct an operation which ex- ~
| |
| coeds, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 3 y Evaluation checklist.
| |
| ; Safety Evalua?. ion [a e d M Date / 7 - 2 7 -f 3 Group /Dep't. Head Review Na N' ' Date // -2 7-f 3 Temporary Approval
| |
| * Date (NCS) i Tcaporary Approvale Date QC Review A# W/5-~C Date /- / - / "
| |
| PORC R4 view f Y M [28/#
| |
| Plant Manager-Nuclear Approval Date /-4 [ V Meeting No. l l
| |
| Date -
| |
| 1
| |
| '. ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UNT-1-003 Revision 6* Attachment 6.9 (1 of 1) :
| |
| ?. (s l _ _ . _ , _ . - . . . . . , _ . - .,__ _____.-____ _ __.._ _. _ _ __
| |
| | |
| 4 Emergency Plan Implementing Procedure EP-2-034 l Onsite Surveys During Emergencies Revision 1 TABLE OF CONTENTS
| |
| ~
| |
| 1.0 -PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS ,
| |
| 5.0 PROCEDURE 5.1 Surveys to Determine Conditions in Occupied Areas 5.2 Surveys to Determine Site Conditions l 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Onsite Surveys Map LIST OF EFFECTIVE PAGES Title Revision 1 1-7 Revision 1 1
| |
| | |
| s Emergency Plan Implementing Procedure EP-2-024 Onsite Surveys During Emergencies Reyision 1 1.0' PURPOSE To provide guidance and instruction on the conduct of radiological surveys onsite (out of' plant) during emergency conditions.
| |
| 2.0' REFERENCES 2.1 EP-2-030, Emergency Radiation Exposure Guidelines and Controls 2.2 EP-2-032, Monitoring and Decontamination 2.3 EP-2-101, Operational Support Center (OSC) Activatian, Operation, and Deactivation 2.4 EP-2-102, Emergency Operations Facility (EOF) Activation, Operation, and Deactivation 2.5 *EP-2-031, In-Plant Radiological Controls and Surveys During Emergencies 2.6 EP-2-130, Emergency Team Assignments 2.7 EP-3-040, Emergency Equipment Inventory 2.8 HP-1-110, Radiation Work Permits 2.9. HP-2-201, Radiation Survey Techniques 2.10 HP-2-210, Contamination, Survey Techniques 2.11 HP-2-215, Airborne Survey Techniques 2.12 HP-2-216, Air Sample Analysis and Evaluation 2.13 HP-300 Series of Procedures, Instrument operation 2.14 EP-2-060, Radiological Field Monitoring t
| |
| l 3.0 RESPONSIBILITIES The Health Physics Coordinator and/or Radiological Controls Coordinator is responsible for implementing this procedure.
| |
| i i h'
| |
| 2 l
| |
| l i
| |
| | |
| Emergency Plan Implementing Procedure EP-2-034 Onsite Surveys During Emergencies Revision 1 4.0 INITIATING CONDITIONS 4.1 This procedure is to be initiated upon any of the following conditions:
| |
| 4.1.1 Declaration of any of the following emergency classifications in which tne event includes an actual or potential release- of radioactive material to the atmosphere and/or degradation of plant conditions such that onsite, out-of-plant areas are radiologically'affected:
| |
| ~
| |
| 4.1.1.1. Alert 4.1.1.'2 Site Area Emergency 4.1.1.3 General Emergency 4.1.2 At the discretion of the Health Physics Coordinator or Radiological Controls Coordinator.
| |
| 4.1.3 At the direction of the Emergency Coordinator. l 5.0 PROCEDURE 5.1 SURVEYS TO DETERMINE CONDITIONS IN OCCUPIED AREAS 5 .' 1.1 The Health Physics Coordinator and/or Radiological Controls Coordinator will evaluate the potential radiological hazards within the onsite (out-of-plant) areas to ascertain habitability conditions in occupied areas that may be affected by plume passage or plant conditions.
| |
| 5.1.1.1 Surveys shall be completed as necessary in the Emergency Response Facilities (EOF and OSC), Security access and control areas and other affected onsite locations based on plume direction and habitability of those areas.
| |
| l
| |
| | |
| Emergency Plan Implementing Procedure EP-2-034 Onsite Surveys During Emergencies Revision 1 NOTE Dose rate and airborne activity levels (if other than acble gases released) shall be determined at a minimum in affected areas.
| |
| 5.1.1.2 Surveys shall be conducted in accordance with normal Health Physics procedures and/or those instructions in EP-2-031 and EP-2-06n, 5.1.1.3 Equipment for conducting onsite surveys is available in the normal Health Physics inventory. Dedicated emergency equipment is also available in the OSC and listed in EP-3-040.
| |
| 5.1.2 The Health Physics Coordinator and Radiological Controls Coordinator' are responsible for ensuring that personnel in ,
| |
| affected areas are made aware of survey results and precautions to be taken.
| |
| 5.1.3 The Radiological Controls Coordinator shall ensure that areas are posted and that appropriate protective equipment is used by personnel performing surveys and personnel working in the l affected areas, as necessary.
| |
| I 5.1.4 Once initial surveys are made, the Health Physics Coordinator and/or Radiological Controls Coordinator determines the need for
| |
| ! and frequency of periodic survey updates.
| |
| 5.1.5 . The Health Physics Coordinator shall keep the Emergency Coordinator informed of all survey results and make recommendations to the Emergency Coordinator regarding stay times, evacuation, etc., in accordance with EP-2-030.
| |
| l 4
| |
| . __ ~ _ , . _ , . _ _ _ __, _ _ _ , _ , - . _ _
| |
| | |
| Emergency Plan Implementing Procedure EP-2-034 Onsite Surveys During Emergencies , Revision 1 5.1.5.1 Consideration should be given to evacuating affected areas when radiation levels are 100 mrem /hr or greater and/or total weighted spc airborne concentration levels are 10 mpe or. greater, and there is no indication that these levels will significantly decrease.during the next four hours.
| |
| 5.1.5.2 Areas shall be evacuated when radiation levels are 500 mrem /hr and/or total weighted spc airborne concentration levels are 100mpe or greater.
| |
| NOTE Accumulated doses to personnel shall also be i taken into account. Consideration should be given to evacuation when 10CFR20 limits (see -
| |
| EP-2-030) are approached and there is no indication that conditions will improve before' limits will be exceeded.
| |
| 5.2 SURVEYS to determine site conditions 5.2.1 The Radiological Controls Coordinator shall ensure surveys are performed onsite to determine site conditions as directed by the Health Physics Coordinator in accordance with EP-2-060 and/or EP-2-061.
| |
| 5.2.2 Survey results should be noted on Attachment 7.1 to provide an easy reference for the Health Physics Coordinator / Emergency Coordinator.
| |
| 5.2.2.1 Provide on the map the date, time of survey and initials of individuals performing the survey.
| |
| 2 5.2.2.2 Indicate dose rates in mr/hr, contamination levels in dpm/100CM and airborne activity levels in uCi/cc.
| |
| 5.2.2.3 Indicate any special items, such as areas that have been evacuated.
| |
| 5
| |
| | |
| Emergency Plan Implementing Procedure EP-2-034 Onsite. Surveys During Emergencies.
| |
| * Revision 1 6.0 FINAL CONDITIONS 6.1 Releases have terminated or reduced to levels below the Emergency Action-Levels (EAL's) for an Alert emergency classification.
| |
| 6.2 All areas are posted as required.
| |
| 6.3 All surveys and samples requested have been completed. .
| |
| 6.4 All data sheets and. samples ahve been returned to the OSC or other locations as defined by the Health Physics Coordinator.
| |
| 7.0 ATTACHMENTS 7.1 Onsite Surveys Map l L
| |
| L i
| |
| e i' 6 l
| |
| I
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| | |
| 9 -_
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| c - .
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| ' h_ .1s-i:l lq-v..--d .h : n. !
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| = = = ,. s= ;
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| I 0
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| - , , , e - - , , . . . . , . - -
| |
| | |
| WATERFORD 3 SES
| |
| -g PLANT OPERATING MANDAL ~~
| |
| l QUISIANA POWER & LIGHT ~
| |
| UNO:NEsb POM VOLUME 18 EP-2-050 POM SECTION 2 REVISION 3 Emergency Plan Implementing Procedure Off-Site Dose Assessment (Manual)
| |
| - LP&L W-3 RECORDS
| |
| .UNCONTRO '':"cD'+-m %)n
| |
| 'i' :
| |
| DO NOT use gr
| |
| * MAINTENANCE TrD ;59 q, R PEsk g .
| |
| PORC Meeting No. 84-01 Reviewed:
| |
| /
| |
| At a ni ud$ ~
| |
| /4~#0RCChairman Approved: l' Il Plant Manager-Nuclear Approval Date Fuel Load
| |
| , Effective Date l
| |
| l l
| |
| l l
| |
| | |
| ~
| |
| WATERFORD 3 SES -
| |
| PLANT OPERATING MANUAL CHANGE /RE7ISION/ DELETION REQUEST Prccedure No. _ '; '' ' '
| |
| ~
| |
| l '- Title N ' > - -
| |
| 4.L.
| |
| o~ i o~- '
| |
| Effective Date ''M (if different from ai: proval date)
| |
| (*- nista 1. R. ae c A. Change No. YA 3
| |
| B. Revision No. '
| |
| C. Deletion 'U/4 l nranns ren ennuar_ arvTsTnu _ on art _rTTom -
| |
| 7 ,, ! . i V ., hm ,, ._y
| |
| .. 4 ,0- .m
| |
| .) eJ.LC '
| |
| nronTurn MTnwatuar/ h 9 Originator ! [ Date /'
| |
| Tcchnical Revieb 0' A/E IM Date / - /- -YY-1 3AFETT ETALUATION Does this change, revision, or deletion: ,
| |
| TE3 NO
| |
| : 1. Change the facilitF aa' described in the FSAR7 _
| |
| '/
| |
| : 2. Change the procedures as described in the F3AR7- __
| |
| : 3. Conduct tests / experiments not described in the F3AR7 '
| |
| : 4. Create a condition or conduct an operation which ex-coeda, or could result in exceeding, the limits in Technical specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 3 Evaluat$on cheelclist.
| |
| Safety Evaluation *>R M S % Date /~d Group /Dep't. Head Review [ M < IA / Date /'4-5Y Temporary Approval
| |
| * Date (NO3)
| |
| Temporary Approvale Date QC Review Af'' M d b Date '
| |
| ~
| |
| s' - W PORC Review M'I2, hNau Date
| |
| /MM Meeting No. .
| |
| PicatMana[r-NuclearApproval_. Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval
| |
| -within 14 days.
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| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2(
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| Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) . Revision 3
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| . TABLE'0F CONTENTS 1
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| 1.0 PURPOSE-
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| ==2.0 REFERENCES==
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| 3.0 RESPONSIBILITIES-
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| ~
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| 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS
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| ~
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| 7.0 -ATTACHMENTS 7.1 Nomogram Procedure (2 pages) 7.2 Computerized Dose Assessment (Back-up) (2 pages) 7.3 Dose Projections Based on Plant Monitoring Data (22 pages) 7.4 Dose Projections Based on Field Monitoring Data (7 pages) 7.5 Dose Projections Based'on Known~ Isotopic-Release Data (5 pages) 7.6 Dose Projections Based on FSAR Accident Data (4 pages)
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| - 7 .~ 7 Meteorological Data (18 pages)
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| LIST OF EFFECTIVE PAGES Title r Revision 3 1-67 Revision 2 1
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| Emergency Plan Implementing-Procedure IP-2-C30 Off-Site Dose Assessment (Manual)
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| Revision 3 1.0 PURPOSE Provide methods for determining projected off-site doses following a major-accidental release of radicactive material; for purposes of recommending off-site protective actions; and for long-term continuous updating of the off-site doses in the event the primary computer-based system (CEPADAS) is not available.
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| NOTE Control Room personnel may use Attachment 7.1, l Nomogram Procedure to estimate offsite doses.
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| NOTE This is a very conservative method and should be used by Control Room personnel in the initial ,
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| stages of an event. - !
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| l
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| ==2.0 REFERENCES==
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| 2.1 EP-2-051, Off-site Dose Assessment (Computerized) 2.2 Meteorology and Atomic Energy - 1968, D. H. Slade USAEC Report TID 241090 2.3 U.S. NRC Regulatory Guide 1.23, Meterological Programs in Support of Nuclear Power Plants 2.4 U.S. NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I 2.5 U.S. NRC Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants 2.6 EP-1-001, Recognition and Classification of Emergency Conditions.
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| 2.7 EP-2-052, Protective Act on Guidelines 2
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| Emergency Plan Implementing-Procedure EP-2-050 Off-Site = Dose Assessment Olanual) . Revision 3 3.0 RESPONSIBILITIES The Radiological Assessment Coordinator, Dose Assessment Coordinator, (CRS)
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| Field Team Controller, or Health-Physics Coordinator is responsible l for implementing this procedure and ensuring that all calculationa are performed in accordance with this procedure.
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| 4.0 INITIATING CONDITIONS 4.1 Any of the following' emergencies has been declared:
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| '4.1.1 Alert 4.1.2 Site Area Emergency ''
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| 4.1.3 General Emergency and 4.1.4 A release of radioactive material to the. atmosphere has occurred or has the potential to occur.
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| 4.2 As determined by the Radiological Assessment Coordinator, Dose
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| ~
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| Assessment Coordinator, EOF Director, Field' Team' Controller or .
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| l Health Physics Coordinator or the Emergency Coordinator.
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| 5.0 PROCEDURE NOTE This procedure is arranged in attachments.
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| i Attachment 7.1 is used by Control Room personnel in the initial stages of an event.
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| Attachment 7.2, Computerized Dose Assessment-(Back-up), is used to rapidly assess off-site doses when CEPADAS is not available. The back-up computerized system is based on the other attach-ments. Each attachment describes a specific method of assessing off-site doses. Back-up computerized calculations are performed on an Osborne 1 portable computer. Attachments 7.3 through 7.7 are to be l used when neither' computerized method is available.
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| 3 L-
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| Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) Revision 3 The specific attachment (s) which is (are) to be utilized in perfcraing dose assessment shall be based upon availability of plant operating data and radiological field data. Only if no plant or field data is available should Attachment 7.6, Dose .I Projections Based on FSAR Accident Data, be used.
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| Each attachment is described below.
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| NOTE A weather forecast should be obtained for the next 12 hours in accordance with the methods in
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| -Attachment 7.6. Obtain forecasts periodically l thereafter on a frequency ' determined by the ~
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| Health Physics Coordinator / Radiological Assessment Coordinator.
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| 5.1 Attachment 7.1 - Nomogram Procedure. This attachment instructs
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| ! _ Control room personnel on the use of the Nomogram on the Shift Supervisor's desk in rapidly assessing the consequences of a radiological release in the initial stages of an event.
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| 5.2. Attachment 7.2-Computerized Dose Assessment (Back up). This l attachment provides instructions for calculating off-site doses on the Osborae I portable computer. It is used when CEPADAS is not available.
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| NOTE Two Osborne 1 portable computers are provided for emergency use--one in the TSC Vault and one in the EOF Dose Projection Area 4
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| L ..
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| Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) ,
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| Revision 3
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| '5.3 Attachment 7.3-Dose Projections Based on Plant Monitoring Data. This i attachment is used to rapidly assess the maximum off-site doses to determine if off-site Protective Action Guides will be exceeded and if recommendations for protective actions should be made. It is the fastest means of manually calculating projections and should be followed up by further detailed calculations (Attachments.7.4 and j 7.5), especially those that may be based on actual field data.
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| * 5.4 Attachment 7.4-Dose Projections Based on Field Monitoring Data.
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| This ,
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| attachment provides methods of performing dose projections based on actual measurements by off-site monit& ring teams.
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| 5.5- Attachment 7.5-Dose Projections Based on Known Isotopic Release Rate. l This attachment provides methods of calculating off-site doses when isotopic analysis of the release path exists.
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| 5.6 Attachment 7.6-Dose Projections Based on FSAR Accident Data. This l attachment provides methods of calculating off-site doses based on nine types of accidents analyzed in the FSAR. Dose projections utilizing this technique should be used only if there is insufficient information to utilize the procedures identified in Attachment 7.3, 7.4 or 7.5.
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| 5.7 Attachment 7.7-Meteorological Data. This attachment provides the method for obtaining meteorological data needed to perform dose projections. The attachment providee the method for using overlays to determine dispersion factors.
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| NOTE An adequate supply of all forms for each attachment is maintained in the TSC and EOF (primary and back-up) for the Field Team Controller / Dose Assessment l Coordinator's use.
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| i 5
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| Emergency Plan Implementing Procedure EP-2-050 Off-Site Dose Assessment (Manual) Revision 3 6.0 -FINAL CONDITIONS 6.1 . Releases of radioactive material to the atmosphere have been terminated or decreased below the Emergency Action Level (EAL) for an --
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| Alert category or:
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| 6.2 Releases are' controlled and a long-term monitoring program has been established.
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| ~
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| 7,0 ATTACHMENTS ,
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| 7.1. Nomogram Procedure 7.2 Computerized Dose Assessment (Back-up) ;
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| 7.3 Dose Projections Based on Plant Monitoring Data -
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| }
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| 7.4= Dose Projections Based on Field Monitoring Data 7.5 Dose Projections Based on Known Isotopic Release Data i
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| 7.6 Dose Projections Based on FSAR Accident Data l 7.7- Meteorological Data 6
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| g NOMOGRAM "ROCEDURE
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| < ~ 1.0 Purpose This attachment provides instructions on the use of the Nomogram in the Control Room to quickly estimate offsite consequences of a release.
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| NOTE This procedure should only be used initially and CEPADAS or other methods of calculation used as soon as possible. -
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| - 2.0 Procedure 2.1 Remove the nomogram from the top of the Shift Supervisor's desk (under plexiglass) and place it on a flat surface or clean the desk where the initial nomogram can be seen and used at the desk.
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| Other copies of the nomogram are available in the TSC vault.
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| 2.2. Ensure-the nomogram can be read properly (large' numbers and letters at the bottom of number lines, labels at the top).
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| 2.3 Using a ruler or other straightedge, connect lines A and B to get C.
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| Line A B the release flew rate in CFM and line B is the uCi/cc jg; Mr/hr monitor reading. (CFM's are cantained in Attachment 7.3)
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| NOTE l This nomogram can be used for monitors that read out in uCi/cc Sg; mr/hr (main steam line monitors) by using the proper scale.
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| ^
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| CAUTION Ensure that the scales are being read correctly. A different number line may have a different scale.
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| 2.3.1 This is the noble gas release rate in curies per second.
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| 2.4 Determine temperature difference at 60m - 10m and wind speed-at-10m from the meteorological towers or backup means as described in Attachment 7.7 t
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| EP-2-050 Revision 3 7 Attachment 7.1 (1 of 2)
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| 2.5 ~ Connect lines.1 and 2 at the appropriate points to get a dispersion ,
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| factor X/Q on line 3. .
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| 2.6 connect the point found on line 3 to that found on line C in section 2.3 above to get the Mr/hr whole body projected dose at the EAB on line 4D.
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| ,2.6.1 If.this number is 250 or greater, use EP-2-052.to determine offsite protective actions.
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| 2.6.2 Use the value found on line<4D in EP-1-001 to determine emergency classification based'on whole body dose rates at the EAB (as noted on line 4D). .
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| 2.7 To determine child thyroid dose rates, take the'value found on line 4D and multiply by 6.
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| 2.7.1 If the result. is 1250 mR/hr or greatcr, use EP-2-052 to determine offsite protective actions.
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| 2.7.2 Use the value found in 2.7 above to determine emergency classification based on child thyroid dose rates at the EAB.
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| ~~
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| 2.8 The nomogram will only produce values for the EAB, GO TO Attachment 7.3 and use the-appropriate wrok sheet or use CEPADAS in accordance -
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| with EP-2-051 if other values are needed - out to 2, 5, and 10 miles. '
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| EP-2-050 Revision 3 8 Attachment 7.1 (2 of 2)
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| V C0t!PUTERIZED DOSE ASSESS"ENT f BACK-UPi 1.0 PURPOSE'
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| .This attachment provides instructions for calculating off-site doses on the Osborne I portable computer when CEPADAS is not available.
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| - 2.0 PROCEDURE 2.1 Set up and energize equipment as follows:
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| 2.1.1 Set up. computer and plug in power cord.
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| NOTE
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| ~
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| At this time, initiate charging the Powr-Pac to ensure it is fully charged should it become necessary to use.
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| 2.1.2 - Set up FX-80 printer by connecting the printer cable between the computer IEEE488 port and the plug on the rear of the printer.
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| '2.1.3 Feed the pin-feed paper into the printer NOTE Never advance paper manually when the machine is turned on.
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| 2.1.4 If Jac power is not available, set up battery Powr-Pac to operate computer (without printer).
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| [ ___
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| NOTE l The battery will power the compuer for approx-l
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| : l. imately one hour of normal use. When battery power becomes too low for reliable operation I' the unit will give a " beep" signal.
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| 2.1.5 Turn on computer and printer. The following message will appear on the screen:
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| i EP-2-050 Revision 3 9 Attachment 7.2 (1 of 2) i m.
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| COMPUTERIZED DOSE ASSESSMENT (BACK-UP)
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| OSBORNE 1 Rev 1.43(c) 1982 OCC Insert disk in Drive A and press RETURN.
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| 2.2 Run the off-site dose calculations program as follows:
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| 2.2.1 Insert the emergency calculations diskette in drive labeled "A",
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| put latch down and press l RETURN} The-following will appear on the _
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| screen when the program is loaded and ready to run:
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| EMERGENCY DOSE CALCULATIONS
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| : 1. DOSE PROJECTIONS BASED ON PLANT MONITORING DATA
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| : 2. DOSE PROJECTIONS BASED ON FIELD MONITORING DATA
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| : 3. DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASES
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| : 4. DOSE PROJECTIONS BASED ON FSAR ACCIDENT DATA
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| : 5. QUIT WHICH7 2.2 General. notes on program operations.
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| 2.2.1 Certain areas of the program require operator input based on values in other areas of this procedure (Attachments 7.3-7.7); i.e. X/Q l values are taken from Attachment 7.7, l 2.2.2 All responses must be followed by pressingIRETURM.
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| 2.2.3 Numbers in scientific notation should be entered using the following
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| -formats 9.2 x 10 3 =BL2JLU 4.0 x 10 ~0 =thE-sj 2.2.4 All responses requiring a yes or no, are to be answered with a y[]
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| or[H[
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| EP-2-050 Revision 3 10 Attachment 7.2 (2 of 2)
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| DOSE PROJECTIONS BASED ON PLANT MONITORING DATA
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| '1.0 . PURPOSE This attachment provides the methods for quickly calculating projected off-site doses in order to determine the need for protective actions.
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| 2.0 PROCEDURE 2L1.' Determination of whole. body and child thyroid doses at specific off-site locations is performed using the attact ed work sheets.
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| 2.2 Determination of accident type.
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| 2.2.1 Based on information communicated by the Emergency Coordinator, select the form for the most appropriate accident type and tog tne exposure duration in Column 5.
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| NOTE The exposure duration (for all except main steam link break) should be assumed as two hours unless plant information provides an accurate, dependable
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| . prediction of-release duration.
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| Attachment 7.3, Page 5 - Fuel Handling Accident Attachment 7.3, Page 6 - Waste Gas System Failure ,
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| Attachment 7.3, Page 7 - Liquid Waste System Failure ,
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| Attachment 7.3, Page 8 - LOCA, Major Fuel Failure Attachment 7.3, Page 9 - LOCA, <1% Failed Fuel l
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| Attachment 7.3, Page 10 - S.G. Tube Rupture, Major Fuel Failure Attachment 7.3, Page 11~- S.G.' Tube Rupture, <1% Failed Fuel MAIN STEAM RELEASE = MSR Attachment 7.3, Page 12 - MSR, Major Fuel Failure, Steam Line Break I Attachment 7.3, Page 13 - MSR, Major Fuel Failure, Relief Valve Attachment 7.3, Page 14 - MSR, Major Fuel Failure, Atmos. Dump Valve Attachment 7.3, Page 15 - MSR, Major Fuel Failure, Emer. Feed Pump Turbine Attachment 7.3, Page 16 - MSR, <1% Failed Fuel, Steam Line Break Attachment 7.3, Page 17 - MSR, <1% Failed Fuel, Relief Valve Attachment 7.3, Page 18 - MSR, <1% Failed Fuel, Atmos. Dump Valve Attachment 7.3, Page 19 - MSR, <1% Failed Fuel, Emergency Feed Pump Turbine
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| ~
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| EP-2-050' Revision 3 11 Attachment 7.3 (1 of 22)
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| *n NOTE It is possible that two release paths and two forms i are applicable. If this occurs, the projected doses and release rates from each form should be added together.
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| ; 2.3 Record'the date and time on the selected forms.
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| 2.4s-Record the:following meteorological data:
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| NOTE Data from both the primary aud back-up meteoro-logical towers is available on the CRT in the-Centrol Room. Data from the back-up tower should be used only if the required information is not available from the primary tower. Figure.1 of Attachment 7.3 provides an example of the l meteorological. data to be available in the Control ,
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| , Room. If data from neither tower is available, follow the procedure outlined in Attachment 7.7. l 2.4.1 Record the 10-meter wind speed in mph in Column 3 of the selected form. - Multiply meters /see times 2.24 to obtain miles / hour.
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| 2.4.2 Record the wind. direction in whole degrees from which the wind is blowing in Section 7 of the selected form.-
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| 2.4.3 Record the delta T (60 m - 10 m) in degrees centigrade ( C) in section 8 of the selected form.
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| i-
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| ) 2.4.4' Based on the. delta T, select the proper Xu/Q values from the Xu/Q table and record them in Column 2.
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| 2.5 Record the proper radiation monitor reading in Columu A.
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| .EP-2-050 Revision 3 12 Attachment 7.3 (2 of 22)
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| L.
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| f DOSE PROJECTIONS BASED ON PLANT MONITORING DATJ.
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| NOTE The_ gas channel should be used for the lowest range monitor that is on scale. The Main Condenser Evacuation System (MCES) Monitor is not normally used since any significant radioactivity will divert-the MCES to the plant stack; use the plant stack monitor.
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| j 2.6 Record the flow rate in cfm in Column C. See Attachment 7.2, Tab,le 1, page 20, to determine efm to use in Column C.
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| 2.7 Multiply A x B x C and record the product in Column D as noble gas release rate.
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| 2.8 Multiply D x E and record the product in Column F. If more than one release path exists, sum Column F to use for dose calculations.
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| 2.9 Multiply D x G and record the product in Column H, as iodine release rate.
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| 2.10 Multiply H x I and record the product in Column J. If more than one release path exists, sum Coluan H to use for dose calculations.
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| 2.11 Enter the value from Column F in Column 1 in each row designated for noble gas (NG).
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| 2.12 Enter the value from Column J in Column 1 in each -row designated for l
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| l Iodine (I).
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| 2.13 Complate the calculations below for each row.
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| 2.13.1 Multiply 1 x 2 and divide by 3. Record the result in Column s as the dose rate (mree/hr) for whole body and for a child's thyroid.
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| 2.13.2 Multiply 4 x 5 and record the product in column 6 as projected dose in mrem.
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| 2.14 When there is a significant chauge in the monitor reading ( t 20% of instrument decade); wind speed (next tabulated valve in Attachment 7.7);
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| wind direction 15 nr
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| {
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| c EP-2-050 Revision 3 13 Attachment 7.3 (3 of 22) i s
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| DOSE PROJECTIONS BASED ON PLANT MONITORING DATA a change in stability class, the dose projections should be revised i on another sheet.
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| 2.15 The data recorded on each sheet should be appropriately entered on the Dose Assessment Status Boards locted in the TSC and EOF.
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| 2.16 It should also be entered at the appropriate locations on the 10-mile
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| ' Emergency Planning area maps located in the TSC and EOF. ~
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| 3.O ATTACHMENTS ~
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| '3.1 Worksheets -Dose Projections- Based on Plant Data (15 pages)
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| ~
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| 3.2 Table 1 - System Flow Rates (2 pages) 3.3' Figure 1, Example of Meteorological Data Available in the Control Room (1 page)
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| , EP-2-050 Revision 3 14 Attachment 7.3 (4 of 22) i
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| 1 . Deenttime -
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| 3 Pient lost name 810netmo ph nelease itele Dose IWe is/ I nele E thsee nele MOM 10H W Eton M sganci , FAcion M T.." so=& reiosi JL PRM-IRE-5032(I,0 l 4.72E-04 6.70E-04 3.02 E4 6.45 E-t 1.55 E9 PRM-IRE-5032(MI )) -
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| PRM-IRE-5032 (IIJ l 1.00E-03 -
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| 1.02 R& 6.as m_s a_gs_g t PRM-IRE-5107Aor 1 4.72E-04 PRM-IRE-0100.lg 4.72E-04 ,
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| l PRM-IRE-0100.2S . 4.72E-04 1.55 E9 i
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| 6.70E-04 3.02 E4 6.45 E-f l PRM-IRE-0110(MI t)
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| PRM-IRE-0110 (III i 1.00E-03 - __
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| 0 0 @ @ O
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| : 0) DoseTlate Exposure Projected Dose Hale Xu Wind ~
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| l Speed Mj[ Duration Dose = ()=@ imewn)
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| ; LOCATION Factor o mph +g (Hours) i @lgll@J ,
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| mnem Wlolo Bmly(EAD) i FAD-Noble Oes EAD-Imane mewn V $ (EAD) mnem Wicio Daly(2 mi)j 2 nde -Noble Oss (2mi}j innom py 2 nde -lodine mnem was navyL5 mi) 5 nde -Hoble Oss mne iy ou (6mi) 5 mus -lodine _
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| mikn WIiole Umly(10#196) i OpnBe-Noble Gac __
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| knthil Ny"gl (10sini) i CD nee-todine O Xuo Table EAD 2 miles 5 ndles 10 miles 96.e.Q e.l.
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| * 1.8i st 1.s tel 7.8(-il r. (-H
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| @ Wind Direction From a u-i.o A 5.4(-51 4.5 001 r.r(q) 7. (q)
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| -1.046T+-o'.9 R
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| -a " ^ * -" * ""' "'~'' ""' "'" -
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| FUEL HANDLING -0. 8 ( A TS-o . 3 0 1.8 04) 3.705) 1.st-s) 4.c( s)
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| .o.3 a u s.8 E uni uai um i.oal ACCIDENT +0.8(6T6+2.0, F _
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| 4.4 04) t,304) 5.U( 51 2.4( 61 1.t ( 4) 6A05)
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| F2.0 M T G /.3 4 4) 2.4(-41 {
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| EP-2-050 Revision 2 At inchnmut 7.3 (5 of 72) 15 ,
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| 1 Del:17lme
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| . Peint test name 81pielwe e e '
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| U e e Does nele o
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| loew!
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| o notamme nele DOSE (D
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| Dose nele
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| *'""'" tioSE j MU A40t# ion W N f90N FAC10n ,1 IMnC FActon M NkD d FACIOlt ]N rRN-IRE-Oll0(IA) 4.72 E-04 PRH-IRE-Oll0(HID) 5.85 E-04 FRM-IRE-Oll0(lit) ..
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| S.Ot E-04 4.86 EiO4 4.08 E-07 9.67 Et08 PRM-IRE-0100.ls 4.72 E-04
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| , taH-IRE-DIDD 22.__. 4.n a-na _
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| 4 .
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| 4 G O O
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| ! W O Wind Dose flate Expostne Projecte(I l
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| Dose Hale Xu -
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| Duration Dose G >@ (mtwn IDCATION Factor O Speed LHours)
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| @$@j mple +)
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| mnemme. omsy(EAD)
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| ! EAD-nous Gas (EAD) l mnem VS EAB-wane ndkn Wla Do%(2mll E
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| i 2 ndle -HuNe Gas ndiem S$g (2nd
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| ; 2 ndle -bane ndwn wivg ewsy(5 mi) l s nele -Nous oes newn y $w (Srni) l s mee -bane ^ ndhn WluAa Daly(10ml)
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| I w pine-Notdo One
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| ~
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| mtwniMu (10ni) to nele-Imane
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| $ Xuv0 Table
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| ! 5 miles 10 inil0s IDLa.Q al. EAB 2 miles ~
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| * a s.i(.si s.3 (in 7.i (-n 7. ( n
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| @ Wind Direction From 3 3 _i,o '
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| y.I (
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| -1.0<ATs ,0.9 H BA! Si 4 A (-el 7.7 (-7) -- . .-, -y l
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| - *^'* -o 8 T ''"' '*"' ""'"' "'
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| WASTE GAS -0.84T'5 -0.3 D 1.6( 4) 3.7 ( 6) 1.18-6) ".210) 4 0.aoi ui .i . 0 ai SYSTEM FAILURE -0.3mTs.o.e E ... ai 4.4 ( 4) I.3 04, 5.0(-51 'J.4 0 5)
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| F H) .8<dTS' ' ''+2.0 F2.0ddT tO
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| '! 7.3 (4) 2.41-4) 1.1141 5405) dP-2-050 Revision 3 16 Attachment 7.3 (f> "I 2D
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| | |
| f Dess/ Time
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| + 7.L4 last name BWee V o o o e Doseltste o
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| 06 e/
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| o nelease Hate DOSE Does llele nEg m
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| pgon g(j! noease % if floGE FMOn [EN *] 8 M"- Duof%ec Fmon _[ggf_
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| l MONHOR rah-lut-0t10 (tm) '
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| _1J2E-04 eaH-IRE-0t10Ogpl 6 DIE-04 l'RM-IRE-0t to (MIJ 6.42E-84 .
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| 1.7sE109
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| ' 3.DEt04 1.99E-04 I A lar nA ,
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| _ rah-IBE-DIQQJa__
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| 1 J PRM-IRE-Ol00.28 4.78E-04 i
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| i O O I
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| W O Dose le Exposuis
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| ! Dose Rate Xu Durative' Dose = #6 (ndwn (DCATION Factor O 8 peed j j inph y (Hours) g@ g M ! mrw.we,4e iuxey(EAD) l i
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| EAD-Hotse one EAD-iodira newn y $ (EAD)
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| .nnemwhose twig (2 vd}
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| 2 mbe -NotAs Gas -
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| mtwn jl$g__f2 Id) a ame -kxsine newn vaioia tws,[6.nd) 6 ndle -Nolde One - mnem Vpu (5 nd) e ame -kxmm toinh-Notdo Gas sikwii wluso ikxty(
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| 10 id) mlwn I g f El mNo-todine 0 xuri Teide l 2 miles 6 milea 10 miles 916 .8Q s.t. EAB g u _i.0 A u t-si s.a t si uu u t-n f @ Wind Direction From -
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| 7.7(-il 7.107) 9 5406) 4.6 Lei
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| -1.0eA s-0.9
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| -a * ^ =-o 8 LIQUID WASTE -0.8ca Ts-0.3 D 1.8 HI -
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| +2.orar EP-2-050 Revision 3 19 Attachment 7.J (9 of 22) l .
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| Print tool nome 81pielure Dose Release Hele DO! E Dose tale Nf1910N MTOR EW FAcion M %" sapc FActon M T. 8'' maoflhec rActosi JL PRM-IRE-5500A 5.55E-06 3.42505 S.56E-0: 5.09E08 PRM-IRE-55008 5.555-06 1 .
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| 2 sidles 5 ndles 10 miles j @ Wind Directiost From y ,_i.o A u t-si s.a til n (-n 7. a n 8.405) 4.5 06) 7.T(-7) 7.1by)
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| A LS) 1:l'-2-050 Hevision 3 25 At t m Innent 7.3 (15 of 22)
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| D U @ 0 0 U 0) @
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| (bm nele lhDe so6m/ nehm e(We MoHnon comenow ra w neienesy Dose DOSE jg_
| |
| i i OE E a Tr FAClon 'M @M FAcion M Y-Y GDm0fibec FActon l
| |
| l FRM-IRE-5500A 9.44E-05 5.lE03 6.12 E404 4.17E-04 7.65EIO8 FRH-IRE-55005 9.44E 815_ 5.!E03 i
| |
| 1
| |
| ! 0) 0 0 @ 0 0 Dose Hale Wind Dose Hale Exposure p I l Xu Dose =
| |
| LOCATION Factgr O Speed y -
| |
| Duration )=0(ninem) l @gM! mph y + l (Hours) mnem wiose nody(EAD)
| |
| . EAD-ewe oss a W user mesm Vlb (EAD) l EAD-iodkw mnen wione Body (2ml)
| |
| I 2 mue -two oss 2 mue -lodkm a ~~ '
| |
| mnem I$3 (2n/I mile n'wiohi nody(5 nd I s nee -two one ~
| |
| l s mee -sodkie mnem Sfou (5ml) l mobn wiole Ib4(10ml) j so nee-Noble oss inse-sodias 4 -
| |
| nmnksow N0r:d) i e Xwo Table 5 miles 10 miles 82l2!.lo?. e.l. EAD 2iniles l *
| |
| @ Wind Direction From ut-si s.s (-el n (-n 7.i t-n
| |
| ) a u _no__ _A 4.s(-el 7.11-7) j _i,ocarg_o,g s eA(-si 7.7 (-7) _
| |
| ! Main Steam -0.xa m-0.8 T uu w ai uia a.ai n
| |
| -a a d =-a 3 Y ""' " " ' ""' '''''
| |
| i Steam Line Break -0. var _44n.a t-2.el-4) s.st-sl _
| |
| 2.3(-si 1.01 si i
| |
| < 8 "4 Failed Fuel r 4.4 ui - uun smai 2AiS l 40.a<ar o i o'O F2.0 /-AT ' ..f 7.3(41 _
| |
| 2A H1 1 1 ( 41 At toclinient 7 3 (16 of 22)
| |
| ;AL'53 j EP-2-050 Revisinti 3
| |
| | |
| 4 1 Delettine .
| |
| Print test name stenetwo .
| |
| @ U U IO @ U U nelease fiele (D GI)
| |
| D use neie A40MIGl 'I''"'' Do6E Does asse DOSE MONHOR W Com/ Ens 10P4 FAcion M 8@*cl . FActon M ''K0** eosoflhec racion _ [ifeW PRM-IRB-5500A 9.448-05 7.65E08 S. 82 F.804 4.17E-04 PRM-IRE-55008 9.448-05 l
| |
| HOTE: For stee a released throuuh
| |
| * as or a :ack, use- s.o. Tutu Rupture forse.
| |
| I - ,
| |
| : 0) 0 0 @ 0 0 Dose Rate Wind Dose Rats Exposure l .Xu i LOCATION Factor o Speed Ji y Duration Dose = eG tmnmni
| |
| ; @gMj rsph (P +0 (Hours) mno.n wliola uody(EAD) i EAD-two oss l EAB-sonine mnom Q!4: (EAD) l ~
| |
| mnemwhoso poh.(2mi) l 2 mile -Noble oss 2 nee -lodine mne;n Now (2mi) j _
| |
| j s ame - Hobie oss neiem'mia now(5 mi) s nee -lodine mnem Qou (5mi) l '
| |
| e mise-Noble oss n41mn Wiiole ikx$(10mi) 10 mile - todine newn Nou (10mi) i e xe rom I 9l0.a1,$,
| |
| , s.t. EAD 2 miles 6 miles to mitos
| |
| @ Wind Direction From g _,,, 7 ,,, i.., ,,3 ::,, ,. , g ., , ,,, i ., ,
| |
| 4.s(-el
| |
| -1.041T s-o.9 e a4(-51 7.7(-7) 7.s (-7) ~
| |
| U.2i ri l Main Steam -0.9<aTx-0.8 e i.2i 4i ..a i .i . i .i
| |
| ' "~"' *''''
| |
| 1
| |
| ~
| |
| ''^'S 3 ''''' '"-'' '
| |
| ReHef WW l
| |
| 6.5(-51 2.3(-5) 1.0 (-Si l -0.3 4T pto.8 E 2.8 l-4) r i.at c soi5 2.4i-5i i <''M Falled Fuel +0.8etT a2.0 4.4 i n 7.3 (4) 2.4l-4) 1.1 (-4) 54(-5l
| |
| +2.0tl T , il El'-2-050 Hevisluis 3 27 At taclimenit. 7.3 (IP of 22) l t
| |
| | |
| 1 Date/Thee ~
| |
| , Print Isot nome 91gnetwo .
| |
| @ U D FKW U
| |
| natesse Rete
| |
| @ E Dosihete G
| |
| dust U
| |
| Rolesso nate W @
| |
| Does note ascetion ensION DOGE DOGE MM W FAClon S %I FACion [M Y " d FAClotl [fn@
| |
| FRM-IRE-5500A 9.44E-oS s.32seo4 4.tys-04 7.65Eles FEM-IRE-5500s 9.44R-05 i
| |
| Il0TE: For etese reteneed thrt ugli HCES or stock, esf3.0. Tube Repture Fa ran 0
| |
| ' W O O 0 Dose Rate Xu Wind bose@ RateEgosure 1 LOCATION Factor o Speed Duration Dose = )= 6 ( nemi l
| |
| l gi g $$gg$ ngdi + (Hours)
| |
| EAO-nous one nine wione umsy(EAB)
| |
| ; EAD-kxnne mnem M*'o u (EAD) l 2 mEe -NoWe One ,
| |
| nh wuse Do@l2Hi) 2 mne -kxskm esie.n SEu (2nd) l _
| |
| ! 5 nele -NoNe oss adkun'Wiole Do@(G nd) j s mim -kxsine ,% y *,,sou (5ni) newn wuAe ikxty(10rni)
| |
| ! 10 mue-NoWe Oes nm Y $u m adk - kx8ka (10nd) e l
| |
| xwo Table M.G s.t. EAD 2 miles 5 iniles u t-n 10 initos u t-n
| |
| @ Wind Direcilon Fiorn d is -i.o A ut-a. i.s t el _ ,_
| |
| -1.5:A m o,9 e s A(-sl 4.stel 7.7 (-71
| |
| ~
| |
| 7.I I-7)
| |
| _3*a
| |
| ~
| |
| l Main Steam -o.9:t w o.8 I" i.2ui i.s ( =
| |
| *"~"
| |
| nie
| |
| "'~" ''''"
| |
| ; Atmos. Dump Valve -o.3ATn+0.8 2
| |
| E 2.e H) 0.st-sl 2.st-51 1.U( 61 i
| |
| l <'"' Failed Fuel 4o.8<4mu.o r 4d ui -
| |
| 'su' 9at-5' 2 d '-S
| |
| +2.0<dT 7.3 ( 4 ) 2 A(;4) 1.1 ( 4l M5l EI'-2-050 Revison 3 28 Attactienent 7.3 (lit of 22)
| |
| | |
| a.'r:;sy v:L.,..-z.; ;- W :?v + A,a :-;a.. v .n + e ..-e v. s -y v.,s., .
| |
| ..:.: e, - v: w w. w . ;. ..
| |
| I Date/ M e tsine sees name siennewe
| |
| % O O U O O O U noisese nelo Di m flate Does timle losEne/ DOSE M0 tis'iUR cOHVEf9 0td IIUW M
| |
| N'I'888 II80' ()oSE ppggggy g y,,h A pggggg ,g N EM FAc1081 IMsC)
| |
| Pldt-IRE-5500A 9.445-05 es12Ete4 4.17 E-04 7.65E00 1 PRH-IRE-55008 9.44E-05 .
| |
| 0 0 0 0
| |
| : 0) Dose @ Rate Exposure Projec f Dose Rate Xu Wind Speed Durallon Dose = )e6 (mnomi LOCATION Factor o ttiph (Houis)
| |
| @gMj +
| |
| nhn wioso twsy(EAD)
| |
| EAD-tious oss EAD-kxnne mnem V $
| |
| mne.nwine tkxsy.(2riW)
| |
| (EAD) 2 mile -tJoble Oes nhn u (2mi) 2 mile -kxilne _ _
| |
| nmn w h nody(5mi) 5 mile -tioble Gas odloenV y (5 mi) 5 mile -kxilne mnom wmu u04(10mi) 10 mile-Hotde Gas mnom ystu (10:19) 30 mne-kxane Xurl Tatjie O 5 miles to miles 0
| |
| M.Q s.t. EAB 2 miles 1.3(el 7.g(-j) 7.3 (-7)
| |
| IOm AT_$-1.0 A 1.1 (-5) s r.:( 7,5
| |
| -I .HArd-0. 9 [ 5 A( si
| |
| : i. ai 4.s ( el iu5i T.7(-71 2 ( .i om; Ma.in Steam -o.0erso.8 .c EFWP Turbine
| |
| -o 8* *-o '
| |
| -0. NTsu),8 E 2.6 HI o.5151 2.3(-51 ".o (' a' f -s) s.sHi . .oi-5 m oi
| |
| <l% Falled Fuel moauu.o 7 u ni r.314) 2AHI 1,1 H) 5 4t-sl
| |
| +2.04AT O (19 of 22)
| |
| At t ar tinwnt 7 .')
| |
| 12.P-2-050 Reviuloin3
| |
| '"M
| |
| | |
| SYSTEM FLOW RATES TABLE 1
| |
| : 1. The stack flow rate will vary as follows:
| |
| Normal RAB - 91,400 cfm Normal RAB + Containment Purge - 106,400 cfm SIAS - RAB and Shield Building ventilation may vary from 3,500 to 26,000 cfm
| |
| : 2. The FHB ventilation varies from 28,260 to 8,000 cfm Emergency Flow-rate.
| |
| Actual flow rates should be obtained from Control Room data.
| |
| : 3. Main Steam Releases -
| |
| : a. Atmospheric Dump Valves (ADV's)
| |
| A flow rate of 7.87 E3 cfm (two valves) or 3.99 E3 cfm (one valve) should be used in Column C. If an ADV is partially open, the flow is determined by Ibn flow rate x (3.99 E3 cfm) = cfm 1 E6 lba/hr .
| |
| : b. Stuck-open SG Safety (Relief) Valve A flow rate of 9.08 E3 cfm per safety valve should be used for Column'C.
| |
| I valve = 9.08 E3 cfm 2 valves = 2(9.08 E3) cfm and so on If the valve is stuck partially open, use the flow rate from Control Room and ratio the efm as follows:
| |
| lbe flow rate x (9.08 E3 cfm) = cfm 1.36 E6 lbe/hr
| |
| : c. Emergency FW Pump Turbine Release The Emerg. FW Pump releases 188.8 cfm; use this number in Column C. .
| |
| EP-2-050 Revision 3 30 Attacitment 7.3 (20 of 22)
| |
| | |
| SYSTEM FLOW RATES
| |
| : d. Main Steam Line Break The Main Steam Line Break will not give a continuing release rate but will empty the SG in less than two minutes (assuming feedwater is stopped). Subsequently, the only releases will be the amount of primary to secondary leakage. The Engineering Technical Assessment Group must be consulted for a flow rate for- the primary to secondary leakage rate.
| |
| For Main Steam Line Break:
| |
| : 1) Record the Main Steam Line Monitor reading prior to the -
| |
| break (conversion factor will not be valid after break).
| |
| : 2) Use 5.1 E3 cfm for flow rate.
| |
| : 3) Use 2 min (1/30 hour) for release duration.
| |
| : 4) After initial release (2 min), request Engineering Technical Assessment Group to provide flow rate of release due to primary-to'-secondary release and calculate release based on reactor coolant concentration (let-down monitor, grab-samples,etc.).
| |
| 1..
| |
| l l
| |
| l l
| |
| EP-2-050 Revision 3 31 Attachment 7.3 (21 of 22) l u.
| |
| | |
| DOSE PROJECTS BASED ON PLANT MONITCPCNG DATA FIGURE 1 WATERFCRD 3 POINT GROUP SGENVIRO 03/16/83 12:00:00 NO. OF POINTS: 14 12:00:00 A48500 PRI METR TWR 33 FT WIND SPEED 3.58 M/B 12:00:00 A48510 PRI METR TWR 33 FT WIND DIR 240.0 DEG 12:00:00 A48504 PRI METR TWR DIF TEMP PRI -0.95 DEG C
| |
| ~
| |
| 12:00:00 A48502 PRI METR TWR 199 FT WIND SPEED 4.08 M/S 12:00:00 A48512 PRI METR TWR 199 FT WIND DIR 230.0 DEG 12:00:00 A48507 PRI METR TWR 33 FT AIR TEMP 20.60 DEG C 12:00:00 A48505 PRI METR TWR DIF TEMP SEC -0.95 DEG C
| |
| -12:00:00 A48513 PRIMARY METR TWR PRECIPITATION S 0.000 IN/HR 12:00:00 A48501 BKUP METR TWR 33 FT WIND SPEED 2.12 M/S 12:00:00 A48511 BKUP METR TWR 33 FT WIND DIR 240.0 DEG 12:00:00 A48506 BACKUP METR TWR DIF TEMP -0.90 DEG C l 12:00:00 A48503 PRI METR TWR 199 FT SIGMA THETA 19.5 DEG 12:00:00 A48508 PRI METR TWR 33 FT SIGMA THETA 21.0 DEG 12:00:00 A48509 BKUP METR 33 FT SIGMA THETA 20.8- DEG EP-2-050' Revision 3- 32 Attachment 7.3 (22 of 22)
| |
| . . ~ . - . __ - .
| |
| | |
| DOSE PROJECTIONS BASED ON FIELD MONITORING DATA 1.0 PURPOSE This attachment provides the methods for obtaining field. monitoring team data, recording,that data and utilizing field monitoring data for projecting doses at other off-site locations.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 Field monitoring will be performed in accordance with EP-2-060. Data will be radioed by the monitoring team to the Dose Assessment Communicator at the TSC or the Field Team Communicator at the EOF when ,
| |
| activiated.
| |
| 2.1.1 Record field monitoring data on the data sheet (Attachment 7.4, l page 4).
| |
| 2.1.2 Calculate the Net Count Ratelat eaca loction by:
| |
| Total Sample Counts /5 - Total Background Counts /2 = Net Count Rate (cpm)
| |
| Record on the data sheet.
| |
| 2.1.3 Record the D/C factor for the instrument used, on the data sheet.
| |
| 2.1.4 Determine the child thyroid dose by using the Child Thyroid Dose Rate Worksheet (Attachment 7.4, page 5). Record the dose rate on l the Calculation Wocksheet, Block B.
| |
| NOTE The factor 1.85 E9 includes the child thyroid inhalation dose factor from Reg. Guide 1.109, Table E-9, and a child breathing rate of 7.04 liters per minute and appropriate unit conver-sions. The Dose Equivalent Iodine (DEI) Factor incorporates the dose from other iodine isotopes not accounted for in the field measurement of air samples.
| |
| EP-2-050 Revision 3 33 Attachment 7.4 (1 of 7)
| |
| L -
| |
| | |
| - DOSE PROJECTIONS BASED ON FIELD MONITORING DATA NOTE The DEI should be based on a conservative assumption of two hours.
| |
| '2.2 Determination of whole body or child thyroid dose at other locations is performed using the Dose Projection Worksheet.
| |
| 2.2.1 Complete the information at the top of the worksheet, including wind speed,. wind direction, date and time.
| |
| 2.2.2 Record the location for which monitoring data is available.
| |
| 2.2.3 Record the whole body dose rate (closed vindow reading from the data sheet) and/or child thyroid dose rate at that loction in Blocks A and B.
| |
| 2.2.4 Record-the X/Q for that location in Block C. The X/Q can be determined from Attachment 7.7. !
| |
| NOTE For projections to be valid, the meteorological
| |
| ~ conditions must be nearly constant during the transit time from release point to monitoring point. _
| |
| r 2.2.5 To determine the projected whole body dose at any other location:
| |
| 2.2.5.1 Record the location.
| |
| 212.5.2 ' Record the X/Q for that location in Block D.
| |
| 2.2.5.3 Determine the dose rate by multiplying the known dose rate by the X/Q at the location of interest or concern and dividing the X/Q for the location of the known dose rate (Block A x D
| |
| * C). Record in Block E.
| |
| -2.2.5.4 Record the anticipated or projected exposure in hours in Block F.
| |
| (Use two hours unless specific data is available.)
| |
| EP-2-050 Revision 3 34 Attachment 7.4 (2 of 7)
| |
| L
| |
| | |
| . . DOSE PROJECTIONS BASED ON FIELD MON 1!0 RING DATA 2.2.5.5 Determine the projected whole body dose by multiplying the whole body dose rate by the release duration (Block E x F).
| |
| 2.2.6 To determine the projected child thyroid dose at any other location:
| |
| 2.2.6.1 Record the location.
| |
| 2.2.6.2 Record the X/Q for that location in Block H.
| |
| 2.2.6.3 Determine the-dose rate .by multiplying :the known dose rate by the X/Q at the location of interest and dividing by the X/Q for the location of the known dose rate (Block B x H'- C). Record in ~
| |
| block I.
| |
| 2.2.6.4 Record the anticipated or projected exposure in hours in bi. k J. (Use two hours unless specific data is available.)
| |
| 2.2.6.5 Determine the projected child thyroid dose by multiplying the projected child thyroid dose rate by the release duration (Block I x J). Record in Block K.
| |
| 2.2.7 Each worksheet can be utilized to project doses at more than one location based on field monitoring data at only one location. If
| |
| . projections are to be based on field monitoring -at other locations,
| |
| . separate worksheets should be used.
| |
| 3.0 ATTACHMENTS l ,
| |
| 3.1 Data Sheet - Dose Rate and Air Sample Data Log 3.2 Child Throid Dose Rate Worksheet 3.3 ' Calculation Worksheet 3.4 Figure 1 - Dose Equivalent Iodine Correction Factor
| |
| ?
| |
| EP-2-050 Revision 3 35 Attachment 7.4 (3 of 7)
| |
| | |
| C . _
| |
| ' /s I
| |
| . T N
| |
| E N
| |
| U R ~
| |
| T y S
| |
| N ),
| |
| I 7 f
| |
| o T ~4 N (
| |
| U O E*
| |
| CT I.
| |
| A 7 TR E t N n e
| |
| m i
| |
| D -
| |
| . . l c
| |
| G ) a KS . t OI n t A Ni A _
| |
| l .Um I
| |
| * _
| |
| A AO .
| |
| D TC2 G O (
| |
| 0, E T e I L m i
| |
| W' E T A P A L /
| |
| T S P ) e A M . . t l R Asn a I Sii D E. A LU Nm .
| |
| t P AO5 TC(
| |
| H O A I S
| |
| . T E R
| |
| I E
| |
| E H
| |
| LE l t
| |
| A t' fl S '
| |
| . Ae b A SV r_ A N T 5 M Wt Ot 6 _
| |
| E LA t 3 T Fi A '
| |
| R i l _
| |
| Eg E LI S PT .
| |
| MA O AR D $U ,
| |
| D
| |
| * )
| |
| r W h NO
| |
| / ED R PN ~
| |
| (
| |
| m GI W
| |
| E T
| |
| A UW M EO 5D E
| |
| S O
| |
| l0.
| |
| CW N
| |
| I .
| |
| , D i e
| |
| W _ r u
| |
| l t l a A n g
| |
| C 3 i
| |
| O S n L o
| |
| // i
| |
| ) e s
| |
| , E r m i
| |
| v .
| |
| L Eh n M H e N' I4 R N
| |
| S T2
| |
| (
| |
| t s
| |
| a, 0 I 5 R 0 E t -
| |
| I n 2 N i -
| |
| N r P n
| |
| i P E i i
| |
| | |
| e b
| |
| CMil.D T!!YR0tD DOSR RATE WORKSIIEET
| |
| /
| |
| Print I. ant Name / Signature Date/ Time SAMPLE A a e o E r !
| |
| net Vol. of D.E.I.
| |
| Niemi,c r Time '
| |
| nample tecntion CPM -
| |
| Factor Conversion Child Thytold Imsc-(from I cit . t. (FIK.1 ) Factor Rate (prem/lir) data) )
| |
| (from data ) -
| |
| 2.978-02
| |
| .___ ..._i ._
| |
| Mieltiply A x n. divide by c h neuttiply by D x t to Ket F:
| |
| (A x B/C) x b x k - mrem /lir.
| |
| The conversion factor conwette DPM to sect, cie. f t. to ec, and uCt/cc to mrem /lir.:
| |
| (4.55E-07 isCt/prH)(3.51K-05 cu. f t./cc)(l .85El09 mren's/br-cc/uCI). '
| |
| - 2.97K-02 mrem /hr/prH. -
| |
| EP 050 Revision 3 37 Aktachment7.4(5of7')
| |
| | |
| 4 .
| |
| 1
| |
| ,. t
| |
| . t-DOSE PROJECT 10NS BASED DN FREl.D. MONITORING DATA
| |
| . p cal.CtfLAtt0N ifoWRSWEET fintn 1.ocnt f em t Ddtet . Time
| |
| , l. Fleid Ilonttoring and Heteorologledi Datn ,
| |
| (A) Whole Hody Dose Ratet *I/ht Wind Speed: mph (R) Child Thyroid Dose Rate: mN/hr Wind Directiort ,
| |
| (C) X/Qt sec/ or det nitoring i
| |
| Data Location) o T/ Stability Class
| |
| +
| |
| I
| |
| : 2. Projected Whole Rody Done De E F C 1.ocation of X/q (seq /se ) for Dose Rate '
| |
| . Exposure 87 oration Done urem Interest I,ocatlon of interest A x (Dic) Ilours ExF 11 1
| |
| 4 eAB . .
| |
| ! 2. Otit ES 5 mit,ES .
| |
| l l 10 Mit,E s
| |
| =
| |
| 4
| |
| : 3. Projected Chlid Thytold Done 11 4 ! J K Exposure Duration Child Thyroid I,ocntion of X/q (nec/m ) for Dose Itale 1.ocallon of interest & x (H -[-t!) Hours Done IxJ
| |
| ] Interent mrem
| |
| ) EAB ,.
| |
| ! 2. Mi t.E 5 -
| |
| 1 5 mit.ES
| |
| . _ _ _ 10 wilt E_S
| |
| * n nnd Il are X/qs for t he_'ioention of interest or toHeern and enn be determleicd' trom Attachment 7.2 Done I -
| |
| Projectionn anned on Finnt Honttoring Date,anil 7.6 'leteorologien! Datft. . .
| |
| Cd(culaleil by .
| |
| EP-2-050 Revision 3 38
| |
| . . Attacheent 7,4 (6 of 7)
| |
| | |
| '0 )
| |
| 5 7
| |
| f Ni- 5 o 4
| |
| 7 s gEBO p08 (
| |
| E!I 5 4
| |
| 4 7
| |
| 5 4 t n
| |
| e 2 m
| |
| '4 h c
| |
| a t
| |
| m d 4 A t
| |
| 5 3
| |
| '6 3
| |
| '4 3
| |
| d 3
| |
| b 3
| |
| 8 2
| |
| 6 2
| |
| )
| |
| 4 s I r u
| |
| o h
| |
| d (
| |
| 2 9 E 3 M
| |
| d I 2 T 8
| |
| 'l
| |
| '6 l e 4 f
| |
| r u
| |
| l i
| |
| a 2 1
| |
| F l e e r b u u l F l i
| |
| r a 8 o F j
| |
| a l M e '6 3 u
| |
| F n
| |
| % o 1 '4 i s
| |
| i v
| |
| $ e R
| |
| 0 5
| |
| - - - ~
| |
| 0 0 0 0 0 0 0 2 6 5 4 3 2 1
| |
| . l 1 1 1 1 I 1 E Dose yACT0R
| |
| | |
| L DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC PII. EASE RATE 1.0 PURPOSE This attachment provides the methods for caculating projected off-site doses when the concentration of the isotopes released is known and the flow rate is determined.
| |
| 2.0 PROCEDURE 2.1 Determination of the whole body dose at any specific off-site location is performed using Worksheet 1.
| |
| 2.2.1 Complete the information at the top of Worksheet 1, including the date, time, wind speed, and direction for the projection being -
| |
| calculated.
| |
| 2.1.2 Record in Column B the concentration of each isotope being released on sample analysis or other means of identifying the radionuclide composition of the release. Ensure that the concentrations are expressed in terms of uCi/cc.
| |
| 2.1.3 Multiply the concentrations recorded in Column B by the dose factor for that isotope (Column C) and record in Column D.
| |
| NOTE J
| |
| The dose factors are determined from Reg. Guide 1.109, Table B-1. Conversion factors of 1.14 x 10 to convert mrem-m /uCi-yr to mrem-cc/uCi-hr; 6
| |
| 472 to convert cfm to ec/sec; and 1 x 10 to convert cc to M3 are included in the dose factor. ,
| |
| 2.1.4 Sum the results of Column D.
| |
| 2.1.5 Record the specific location for which the projection is being made in Column E. Several locations may be used for the specific radionuclide mix as measured. Calculations will be accurate as long as the radionuclide concentrations remain constant.
| |
| 2.1.6 Record the sum of Block D in Column E.
| |
| EP-2-050 hevision 3 40 Attachment 7.5 (1 of 6)
| |
| | |
| i
| |
| (
| |
| DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE 2.1.7 Record the flow rate for the release path in Column G. Ensure that flow is recorded in cubic feet per minute (cfm).
| |
| 2.1.8 ~ Record the X/Q for the specific location in Column H. X/Q is l
| |
| determined in Attachment 7.7.
| |
| 2.1.9 Multiply the> sum of Block D, the flow rate and the X/Q (Column F x G x H) to determine the whole body dose rate at that location in terms of ares /hr. Record the result in Column.J. Tbis result is the: projected dose rate at the-specific location identified and should be used to evaluate the need for protective action (s) and to compare with field measurements.
| |
| 2.1.10 If the release duration is known oc can be projected, enter the duration in hours in Column K. (Use 2 hours if release duration is unknown.)
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| 2.1.11 Determine the projected dose by multiplying the dose rate at the specific location by the release duration (Column J x K).
| |
| 2.2 Determination of the limiting thyroid. dose at any specific off-site location is performed using Worksheet 2.
| |
| NOTE The limiting dose is to the child (5-10 yrs) ,
| |
| i thyroid and should be calculated first.
| |
| 2.2.1 Complete the information at the top of Worksheet 2, including date,
| |
| - time, wind speed and direction for the projection being calculated.
| |
| : i. 2.2.2 Record in Column B the concentration of each iodine isotope being released, based on sample analysis or other means of identifying the radionuclide. composition of the release. Ensure that the l concentrations are expressed in terms of uCi/cc.
| |
| 2.2.3 Multiply the concentrations recorded in Column B by the dose factor ,
| |
| l' ~ for tnat isotope (Column C) and record in Column D.
| |
| I L
| |
| .~ EP-2-050. Revision.3 41 Attachment 7.5 (2 of 6) l' i
| |
| .~. . - . . . - . . , . - . , - . . . - _ . . . - . . _ - - _ . . - . - . . - - , . - , -
| |
| | |
| DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE NOTE The dose factors are determined from Reg. Guide 1.109, Table E-9, and a child breathing rate of 7.04 liters per minute. Conversion factors of 472 to convert liters /per minute to ec/hr are ___
| |
| included in the dose factor.
| |
| 2.2.4 Sun the results of Column D.
| |
| 2.2.5 Record the specific location for which the projection is being made -
| |
| in Column E. Several locations may be used for the specific radionuclide mix as measured. Calculations will be accurate as long as the radionuclide concentrations remain constant.
| |
| 2.2.6 Record the sum of Block D in Column F.
| |
| * 2.2.7 Record the. flow rate for the release path in Column F. Ensure that the flow rate is recorded in cubic feet per minute.
| |
| 2.2.8 Record the X/Q for the specific location in Column H. X/Q is determined in Attachment 7.7 l 2.2.9 Record the fraction of radioiodines being released through the charcoal filters. If'the filter efficiency is unknown, use 0.05 as the release fraction.
| |
| NOTE If the flow path does not include a filter system or the sample was obtained downstream of the filters, the release fraction is 1.
| |
| 2.2.10 Multiply the sum of Block D, the flow rate, the X/Q and the release fraction (Column F x G x H x J) to determine the projected thyroid dose per hour exposed in terms of mrem /hr exposed. Record the result in Column K.
| |
| EP-2-050 Revision 3 42 Attachment 7.5 (3 of 6)
| |
| | |
| DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE 2.2.11. If the release' duration is known or can be projected, enter the duration in hours in Column L. (Use 2 hours if release duration is unknown.)
| |
| 2.2.12 Determine the projected dose by multiplying the dose per hour exposed by the release duration (Column K x L). Record the projected child thryoid dose in Column M. .
| |
| 3.0 ATTAC10ENTS 3.1 Projected Whole Body Dose Worksheet 1 3.2 Projected Thyroid Dose (Child Thyroid) Worksheet 2 -
| |
| EP-2-050 Revision 3 43 Attachment-7.5 (4 of 6)
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| L_
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| | |
| PROJECTED WHOLE Q0Y 00SE .
| |
| WORK 3HEET 1 i
| |
| Wind Speed: mph Wind Directien: Fr:m: Date: Time: .
| |
| a.m,./p.=.
| |
| dT/ Stability, Class A 8 l C 0 Concentration Oose Isotoos (uCf/ce) Factor BxC Kr-85m l 63. ~
| |
| Kr-85 l l .624 l Kr-87
| |
| ~
| |
| ! l 319. l
| |
| ( Kr-88 l 791. l l l
| |
| Kr-89 893. l Xa-131m l 4.92 Xa-133n l -
| |
| 13.5
| |
| , , 4e-133 l l 15.8 ;-
| |
| Xe-135s ! !
| |
| 158. i
| |
| ~
| |
| i* r* - .
| |
| Xa-135 97.4 l .
| |
| . Ie-137- f 76.4
| |
| . Xe-138 '
| |
| 475.
| |
| Block 0 = -
| |
| '~
| |
| E F G H l J K l L Dose Rate 'xmosura r Oose l Flow Rate X/Q (mram/hr) Duration (mrem)
| |
| Location Block 0 (CFM) (sec/m3 ) FxGxH "(hr) JxK m I I I -
| |
| I 2 Miles l l 5 nu.s I
| |
| : 10. Miles l.
| |
| I I I I I i 1
| |
| . l l-l l l Calculated by:
| |
| l EP-2-050 Revision 3 44 Attachment 7.5 ( 6f di)
| |
| . _ - _ . . ._,,,.-_.-.,,,.___.-...,,,.,.._,..,..m - _ _ , . . . .
| |
| | |
| ~
| |
| . PROJECTED UfYROID-DOSE (CHILD UfYROID)
| |
| ,- WORKSHE.T 2
| |
| 's -
| |
| l l
| |
| Wind Speed: r.ah ,
| |
| Wind Direction: Fr:m: Data: Time: a.m./p.m.
| |
| d T/ Stability Class
| |
| . QiILD THYROID
| |
| ~
| |
| A l- 5 'C l 0 Concentration Dosa -
| |
| l Isotope uC1/cc Factor 8xC
| |
| ~
| |
| I-131 3.75E5 l _
| |
| I 132 l ' l 1.04E4 : l
| |
| ~ '
| |
| I.133 1 '2.08E5 I.134 l2.74E3 l I.135- L4.2734-Block U ~ = ,
| |
| I 6). - E F G H i J K '
| |
| L M
| |
| ~
| |
| Dose Ra'ta I 6erunjhr Irposure Dose ;
| |
| Flow Rata X/Q Duration Aalease exposed) (meen)
| |
| Location Block D (CFM) (sac /m3 ) Fraction FxsxHzJ (hr1 ' Kzi, m
| |
| l ,
| |
| 2 w .. I I
| |
| !~
| |
| 5 Miles ! l 10 Miles i l l. l Calculated by:
| |
| l l .
| |
| \
| |
| l l
| |
| l l
| |
| U-2-oso Revision 3 45 Attachment 7. 5 ([ cy) l
| |
| | |
| }
| |
| DOSE PROJECTIONS BASED ON FSAR ACCIDENT DATA 1.0 PbRPOSE This attachment provides a method for calculating the projected dose rate at the EAB. It is based upon nine accidents that were analyzed in the:FSAR.
| |
| NOTE This technique should be used only when there is no plant or field monitoring data available. It, should be used only as a first approximation and -
| |
| quickly replaced as plant and/or field data becomes avaiable.
| |
| 2.0 PROCEDURE 2.1 From.the nine accidents identified on the worksheet, select the type of accident based on the actual occurrences (Attachment 7.6, page 3, l FSAR Accident Assumptions, provides background information for this selection and is used for additional data).
| |
| 2.2 Using the Short Form worksheet Attachment 7.3, page 5, develop the l X/Q at the Exclusion Area Boundary (EAB) and record in the appropriate location on the FSAR Accidents worksheet. X/Q = Xu/Q from Column 2 divided by wind speed from Column 3 on worksheet.
| |
| 2.3 Multiply the X/Q by the appropriate dose factor (includes correction I factor) for that accident (whole body and/or child thyroid) to obtain the projected dose at the EAB and record.
| |
| 2.4 Additional worksheets are to be used to calculate doses at other
| |
| , distances using the appropriate dispersion (X/Q) factors.
| |
| l - 3.0 ATTACHMENT 3.1 FSAR Accident Assumptions
| |
| ' - ~
| |
| EP-2-050 Revision 3 46 Attachment 7.6 (1 of 4)
| |
| | |
| J Y
| |
| FSAR ACCIDENTS - DOSE PROJECTIONS WORKSHEET .
| |
| ' Wind' Direction: Date: Time:
| |
| ~ 0,T/ Stability Class Dose Factor Dose Rem Whole Body- Whole Body-
| |
| - ACCIDENT-- X/Q* Child Thyroid Child Thyroid-Nain Steam Line Break x 2.55 E-2 =
| |
| 2.18 E1
| |
| ^~
| |
| Inadvertent Steam Dump. x 1.02 El =
| |
| 8.73 E3 CEA Ejection Accident x 8.71 E3 =
| |
| 2.47 ES
| |
| - Letdown line Break' xr2.73 El =
| |
| 8.36 E3 S/G Tube Rupture x 4.91 =
| |
| 4.55 El Waste Gas System Leak x 8.36 =
| |
| 5.09 Loss of Coolant Accident ,.
| |
| x 6.91 E2 =
| |
| 2.73 E3 1
| |
| -Liquid Waste Release x 1.91 =
| |
| 2.54 E2 LFueliHandling Accident x 8.55 =
| |
| 3.64 E1
| |
| *For Exclusion Area Boundary, 914 m. Calculated by:
| |
| EP-2-050: Revision 3 47 Attachment 7.6 (2 of 4)
| |
| | |
| FSAR ACCIDENT ASSIRIPTIONS
| |
| ~
| |
| This attachment provides the basic assumptions and radiological consequences (Design Basis) for the incidents that are not expected to occur but are postulated because their consequences would include the potential for the release of significant amounts of radioactive material. This attachment is to be used when instrumentation used for assessment is off-scale or inoperable.
| |
| Identify the type of incident which has occurred from the nine incidents defined in this attachment. If no identification is possible, use the most restrictive accident which cannot be reasonably excluded. -
| |
| The information given below should be used in ratioing and adjusting assumed FSAR values with any known actual values in the event of an incident at Waterford 3 Steam Electric Station.
| |
| IDENTIFICATION A.DURADIOLOGICAL CONSEQUENCE ASSUMPTIONS
| |
| : 1. Main Steam Line Break This incident is defined with a simultaneous loss of off-site power.
| |
| Steam is vented directly to the atmosphere.
| |
| : 2. Inadvertent Steam Dump For an inadvertent opening of steam generator atmospheric dump valve with a concurrent single failure of an active component and loss of off-site power, the activity released from the Steam Generators is immediately vented to the atmosphere.
| |
| : 3. Control Element Assembly (CEA) Ejection Accident 1
| |
| This accident assumes a loss of off-site power at the time of turbine !
| |
| trip and a 6.5 (uci/g I-131) dose equivalent for the primary system (activity in the coolant systems prior to the accident).
| |
| : 4. Primary Sample or Letdown Line Break i For primary sample or letdown line break incidents, a two-inch schedule 160 pipe'is analyzed. _A rupture outside the containment causes a
| |
| . release to the Reactor Auxiliary Building (RAB).
| |
| EP-2-050 Revision 3 48 Attachment 7.6 (3 of 4) l l
| |
| i l
| |
| I-
| |
| | |
| FSAR ACCIDENT ASSUMPTIONS
| |
| : 5. Steam Generator Tube Rupture (SGTR)
| |
| This accident assumes a loss of off-site power and allows transport of reactor coolant into the main steam system. Release is via the Steam Generator safety valves and atmospheric dumps.
| |
| : 6. Loss of.. Coolant Accident (LOCA)
| |
| A LOCA provides a release path to the environment via containment leakage pathways.
| |
| : 7. Radioactive Waste Gas System Leak or Failure
| |
| ~
| |
| -This incident assumes an unexpected and uncontrolled release to the atmosphere of radioactive xenon and krypton fission gases.
| |
| : 8. Liquid Waste System Leak ,
| |
| A Liquid Waste System leak or failure results in a telease to the atmosphere and a release of all liquids in the Boron Management System (BNS) and Waste Management System (WMS) to the Reactor Auxiliary (RAB). Off-site doses will occur as a consequence of released nobla gases and iodines assumed to volatilize from the spilled liquids.
| |
| : 9. Fuel Handling Accident _
| |
| A fuel handling accident is the most restrictive accident defined in the FSAR.
| |
| EP-2-050 Revision 3 49 Attachment 7.6 (4 of 4)
| |
| U,
| |
| | |
| METEOROLOGICAL DATA 1.0 PURPOSE This_ attachment provides two alternative methods of obtaining meteorological data required to perform dose projection calculations.
| |
| It should be used when data from either the primary or backup meteorological tower is not available on the'CRT in the Control Room or in the Computer Room.'
| |
| 2.0. PROCEDURE 2.1 The alternative methods for obtaining meteorological data are:
| |
| ~
| |
| 2.1.1 Dispatch an individual to the primary meteorological tower to record the following data from the analog recorders at the tower location:
| |
| Instruct the individual at the tower to turn the digital selector switch to the desired parameter, record the digital readout and report the value.
| |
| Delta T (60 m - 10 m) = 'C Wind Speed (10 m) x (2.24 mph /sps) = sph (eps .is meters- per seconds; aph is-miles per hour)
| |
| Wind Direction (10 m)'
| |
| NOTE If primary tower data is not available, instruct individual to go to back-up tower.
| |
| :2.1.2 Contact the National Weather Service (NWS) by commercial telephone at ,(504) 525-0823 or (504) 649-0429.
| |
| Obtain the following inforamation from the NWS:
| |
| Weather forecast for next 12 hours (including wind speed and direction)
| |
| EP-2-050 Revision 3 50 Attachment 7.7 (1 of 18)
| |
| =
| |
| | |
| METEOROLOGICAL DATA Stability Class (for 60 m - 10 m) = (A-G)
| |
| Wind Speed =
| |
| Wind Direction =
| |
| NOTE If there are any problems in getting the forecast or more information is needed, contact the NWS Office and request the forecaster-in-charge. .
| |
| 2.1.3 Determine the appropriate Pasquill stability class from the following table based on data obtained in section 2.1 above.
| |
| Class Delta T (60 m - 10 m) C A - Very Unstable A T 5 - 1.0 B - Moderately Unstable -1.0<aT i -0.9 C - Slightly Unstable -0.9<AT $ -0.8 D - Neutral -0.8<AT 1 - 0.3
| |
| . E Slightly Stable -0.3<AT $ + 0.8 F - Moderately Stable +0.8<AT $2 G - Very Stable +2. 0 < A T Stability Class 2.2 The two alternative methods for determining the dispersion factor (X/Q) are:
| |
| 2.2.1 Meteorological dispersion tables based on Pasquill stability class, wind speed and downwind distance. These tables are used as follows:
| |
| Select the desired downwind distance in miles for which the X/Q value is to be calculated:
| |
| Downwind distance = miles Select the appropriate'X/Q from the. tables given on pages 5-18 based on wind speed, desired downwind distance and stability class. If the wind speed and/or distance falls between two valves on the tables, use the distance with the higher X/Q value. Record below.
| |
| EP-2-050 Revision 3 51 Attachment 7.7 (2 of 18) m.u
| |
| | |
| (_
| |
| METEOROLOGICAL DATA Downwind Stability Wind 3
| |
| Time Distance Class Speed (mph) X/Q (sec/m )
| |
| To determine X/Q at loctions away from the center line of the plume, use the Emergency Plannier, Zone (EPZ) Isopleth Overlays described in step 2.2.2 below. -
| |
| 2.2.2 Estimates of atmospheric dispersion values can be obtained using isopleth overlays based on the atmospheric stability class and wind speed.
| |
| NOTE Isopleth overlays have been developed for Stability Class B (unstable), D (neu ral), and F (stable) only. Isopleth overlays are located with other emergency response-dose assessment equipment.
| |
| Using the stability index from section 2.2 above, select:
| |
| Isopleth for Class B for Stability Class A, B or C Isopleth for Class D for Stability Class D Isopleth for Class F for Stability Class E, F or G Select the appropriate overlay based on the atmospheric stability class (B, D, F).
| |
| Align the center axis of the isopleth plot with the centerpoint (plant) of the Emergency Planning map.
| |
| EP-2-050 Revision 3 52 Attachment 7.7 (3 of 18)
| |
| L , ,. . - - - _ - - . . .
| |
| | |
| METEOROLOGICAL DATA Orient the overlay such that the projection occurs in the downwind direction. (Wind direction recorded as from 270 West should orient the overlay in a 90 East Direction.)
| |
| Once. aligned, locate all critical locations. Choose the nearest X/Q line toward the centerline from each critical location.
| |
| From the table'on the overlay use the appropriate wind apeed (from section 2.1) and Xu/Q line number to obtain X/Q and record below. Repeat for all critical locations.
| |
| Location Wind Speed X/Q The above X/Q values can be used for calculating dose projections.in procedure Attachment 7.3 (Dose Projections Based on Field Monitoring Data),
| |
| 7.4 (Dose Projections Based on Known Isotopic Release Data) and 7.5 (Dose Projections Based on FSAR Accident Data).
| |
| t l
| |
| l
| |
| )
| |
| I EP-2-050 Revision 3 53 Attachment 7.7 (4 of 18)
| |
| L
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| EP-2-050 Revision 3 62 Attachment 7e 7 (13 of 18)
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| l EP-2-050 Revision 3 63 Attachment 7 7 (14 of 18)
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| I E 0 0 6 0 8 8 9 5 4 8 .
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| EP-2-050 Revision 3 . 65 Attach:nenc 7. 7 (16 of 18)
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| | |
| s WS ee eo ee e e e ee ee ee ee A eo e ee eo e e e de e e e e e oe e e M N m e e M e r m O e M M M N m 30 e e e A m m 4-8 M e 6 el m e
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| EP-2-050 Revision 3 66 Attachment 7,7 (17 of 18)
| |
| | |
| e i
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| |
| EP-2-050 Revision 3 67 Attachmanc 7.7 (18 of IS)
| |
| L. 1
| |
| | |
| WATERFORD 3 SES PLANT OPERATING MANUAL
| |
| ~
| |
| M,,_3
| |
| ''' Louis.' Ana .
| |
| ~~ '
| |
| POWER & LIGHT U$NN POM VOLUME J EP-2-051 POM SECTION 2 REVISION 1 Emergency Plan Implementing Procedure Off-Site Dose Assessment (Computerized)
| |
| LP&L W-3 RECORDS UNCONTROLLED DO NOT USE IN ANY SAFETY-RELATED TESTING, COPY MAINTENANCE, OR OPERATIONAL ACTIVITY PORC Meeting No. 84-01 Reviewed: %, _
| |
| /PORC, Chairman Approved: s 'bu V ' 1 I Y
| |
| ! Plant Manager-Nuclear Approval Date mel Load Effective Date
| |
| | |
| l WATERFORD 3 SES PLANT OPERATING MANUAL i CHANGE / REVISION / DELETION REQUEST Prcoedure No. ' '''-
| |
| Title Ih 2-r ihd ( u - 4 E .., gy
| |
| <- '' '" q Effective Data -
| |
| (if different from approval date) l t'am ni a ta 1. B. er C A. Change No. #ld ~
| |
| B. Revision No. /
| |
| C. . Deletion NlA neannu ren enawar_ arvTmTns on nrt m ns -
| |
| 7 ,wi , t _,. rJr, ,L :( r!
| |
| REOUIREDSIGNATUqER'].- --
| |
| Originator I#7MN Date
| |
| ~
| |
| 3 Tcchnical Review' # # '' Date / ~6 N SAFETT ETALUATION
| |
| , Does this change,. revision, or deletion: ,
| |
| TE3 NO
| |
| : 1. Change the facility as described in the FSAR7 '
| |
| : 2. Change the procedures as described in the FSAR7- <'
| |
| : 3. Conduct testa / experiments not described in the FSAR? '/
| |
| 4 Create a condition or conduct an operation which ex- #
| |
| coeda, or could result in exceeding, the limits in l Technical Specifications?
| |
| 1' l If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 ty Evaluation checklist.
| |
| 3:fety Evaluation,__ - a d Date /-I~I Group /Dep't. Need Review ? Y A ar< br- ) Date I-C W
| |
| /
| |
| Temporary Approval
| |
| * Date (NO3)
| |
| Temporary Approval
| |
| * Date QC Review 4A 9<Y'Mu Date - r - #-
| |
| * PORC Review I2hYY$- Date ' FU Meeting No. i PlantMana[edNuclearApproE '
| |
| Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
| |
| . ~ . _ . _ - - . _ __._..._.__._ _._.. _ __ . _ _ - _ - - - - _ . - - _ - -
| |
| | |
| Emergency Plan ~ Implementing Procedure EP-2-051 Off-Site Dose Assessment (Computerized)- Reyision 1 TABLE OF CORTENTS
| |
| - 1~,0 PURPOSE-
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 3.0 RESPONSIBILITIF.S 14.0- INITIATING CONDITIONS
| |
| ~'
| |
| 5.0 PROCEDURE
| |
| ' 6.0- FINAL CONDITIONS 7.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 1 1-7 Revision 1 b
| |
| T i 1
| |
| ^
| |
| L _ _ .
| |
| | |
| Emergency Plan Implementing Precedure EP-2-051
| |
| , 0ff-Site Dose Assessment (Computerized) - Revision L 1.0 PURPOSE
| |
| ; To provide a method- for projecting off-site doses following a major accidental. release of1 radioactive material, for recommending off-site protective actions, and for long-term continuous updating of the off-site doses using the coaputer program CEPADAS.
| |
| I t
| |
| Control Room personnel may use Attachment 7.1 of EP-2-050, Nonogram Procedure to estimate off-site dose's.
| |
| CAUTION This is a very conservative method and should only be used by Control Room personnel in-the initial stages of an event. Refer to EP-2-051 Attachment 7.1.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| ~ 2.1 EP-2-050,'Offsite Dose Assessment (Manual) 2.2 CEPADAS User's Manual, Volume I, Technical Description
| |
| ' 2.3 'CEPADAS User's Manual, Volume II, User's Guide ,
| |
| 2.4 Waterford 3 Final Safety Analysis Report (FSAR) 2.5. Waterford 3 Environmental Report (ER) 3.0 RESPONSIBILITIES The Radiological Assessment Coordinator, Dose Assessment Coordinator, Field Team Controller, or Health Physics Coordinator is responsible
| |
| -for implementing this procedure, i 2
| |
| - , , - - , - -w, ,-,--,r-, ---,.-,,,w. --- - ---m- - - . -- -, , ,~p
| |
| | |
| . Emergency Plan Implementing Procedure EP-2-051 Off-Site Dose Assessment (Computerized) Reyision 1 4.0 INITIATING CONDITIONS 4.1 Any of :the following emergencies has been declared:
| |
| 4.1.1 ~. Alert 4.1.2 Site Area Emergency 4.1.3 General Emergency
| |
| -4.1.4 A release of radioactive material to the atmosphere has occurred or has the potential to occur
| |
| ~
| |
| 4.2 As determined by the Radiological Assessment Coordinator, Dose Assessment Coordinator, EOF Director or the Health Physics Coordinator or the Emergency Coordinator. !
| |
| 4.3 Any time CEPADAS goes into an Emergency Mode 5.0 PROCEDURE
| |
| ~
| |
| NOTE A weather forecast should be obtained for the next 12 hours in accordance with the methods in Attachment 7.7 of EP-2'-050. Obtain forecasts l periodically thereafter on a frequency determined by the Health Physics Coordinator / Radiological Assessment Coordinator.
| |
| 5.1' Go to any HERC0 terminal with the following display:
| |
| 1 MAIN MENU SAFETY PARAMETER DISPLAY l
| |
| HISTORICAL DATA COLLECTION I
| |
| REPORT GENERATION ,
| |
| ;. CEPADAS f'
| |
| i I
| |
| i i
| |
| 3 l
| |
| . - _. . ... . __ . _. . . . _ ~ _ _ _ _ . _ . __. .
| |
| | |
| s Emergency Plan. Implementing Procedure EP-2-051
| |
| -Off-Site Dose Assessment.(Computerized) Revision 1 NOTE
| |
| : 1. HERCO terminals with AYDIN displays and Texas Instruments loggers that are dedicated
| |
| -to CEPADAS use are located in the EOF Dose
| |
| ~
| |
| Projection area, TSC Dose Assessment area and Backup EOF.
| |
| .2. If the equipment is not energized, notify the Emergency Coordinator or E0F Director and perform calculations by backup means in accordance with EP-2-050.
| |
| : 3. If the equipment is energized but the screen has no display (step 5.1 above), press T
| |
| . If the l proper display still does not appear, perform calculations by backup means in accordance with EP-2-050 and notify the Emergency Coordinator or EOF Director.
| |
| : 4. The same equipment is provided for the SPDS program in the Control Room, TSC and EOF.
| |
| CEPADAS dose projections may be displayed on this equipment. Any changes to be made using OPER.".IOR INPUT should be made on the equipment listed in item 1 above.
| |
| ; 5.2 Move the cursor to the CEPADAS line and' press to begin running the CEPADAS program.
| |
| 4 u
| |
| | |
| Emergency Plan Implementing Procedure EP-2-051 Off-Site Dose Assessment (Computerized) Reyision 1 5.3 NOTES ON PROGRAM CPERATIONS 5.3.1 Whenever the program requests a CRT number with an activity the operator desires to perform, such as OPERATOR INPUT, CRT # or EMERGENCY DISPLAY, CRT #, move the cursor to the "C" of CRT and enter [Ik then ' space to the end of the line and press .
| |
| 5.3.2 Wait for the program to prompt for response by the cursor
| |
| ~
| |
| returning to bottom of page prior to each entry.
| |
| 5.3.3 All responses must be followed by pressing 122000 5.3. 4 '' ' To ensure all desired activities are printed, always select print option ("P") first whenever the menu containing this option is displayed.
| |
| 5.3.5 Numbers in scientific notation should be entered using the following format:
| |
| 9.2 X 10-3 = l9. 2E-3l 4.0 X 10-4 = l4.0E-d 5.3.6 CEPADAS will allow only one operator to use the OPERATOR INPUT program. Operators in satellite locations (i.e., at TSC when EOF e
| |
| 5 m
| |
| | |
| Emergency Plan Implementing Procedure EP-2-051 Off-Site Dose Assessment (Compaterized) Revision 1 has taken turnover and is doing dose assessment or at SPDS HERCO terminals) shall not use the OPERATOR INPUT subroutine.
| |
| NOTE If a second operator attempts to use OPERATOR INFUT. the following message will appear:
| |
| UNABLE TO USE OPERATOR INPUT, SINGLE COPY TASK
| |
| .ALREADY IN USE AT ANOTHER HERC0 CONSOLE PLEASE SELECT ANOTHER ITEM.
| |
| The second operator should presslXMIIjto return to the Main Menu to make another selection (Emergency Display).
| |
| 5.3.7 When selecting effluent release points, do not select release point RLSS.
| |
| 5.3.8 Enter @]to exit any menu and return to the previous menu.
| |
| 5.3.9 If CEPADAS displays an error message, press to return to
| |
| . previous menu for correct entry.
| |
| 5.3.10 CEPADAS is not designed for field monitoring team calculations.
| |
| Use EP-2-050, Attachment 7.3, for calculations involving field team data.
| |
| 5.3.11 When real time meteorological data is not available and the CEPADAS meteorological data substitution program is to be used, procure data for entry in accordance with EP-2-050, Attachment 7.7. 1 5.3.12 Once an Emergency Mode is entered, the only way to exit it is to enter another Emergency Mode, or specify return to normal operations by running the OPERATOR INPUT subroutine and selecting NORMAL OPERATIONS.
| |
| 6
| |
| | |
| Emergency. Plan Implementing Procedure EP-2-051
| |
| 'Off-Site Dose Assessment (Computerized) Revision 1 6.0 FINAL CONDITIONS 6.1 Releases-of radioactive material to the atmosphere have been terminated or decreased below the Emergency Action Level (EAL) for an ALERT category or:
| |
| 6.2 Releases are controlled and a long-term monitoring program has been
| |
| - established.
| |
| 6.3 .CEPADt.s has been returned to normal operations.
| |
| 7.8 ATTAClefENTS i-t l-I-
| |
| i.
| |
| 7 i-i_
| |
| | |
| WATERFORD 3 SES
| |
| _ PLANT OPERATING MANDAL
| |
| . 55 y
| |
| l'
| |
| # l CUISIANA POWER & LIGHT
| |
| $ bh?.Ya EP-2-052 REVISION 3 POM VOLUME _ 18 POM SECTION 2 APPROVAL DATE:
| |
| 0CT 171983 EFFECTIVE DATE: Fuel Load EMERGENCY PLAN HIPLEMENTING PROCEDURE PROTECTIVE ACTION GUIDELINES LP&L W-3 RECORDS UNCONTROLLED COPY DO No1 09 tr.i ANY SAFETY -Mt.A TEo : fist.:NG, MAINTENANCE, OR OPERATIONAL ACTIVITY l*
| |
| PORC Meerd g No. 53 3T .
| |
| Reviewed: \ w mr-(ywa I ' NA t 'NN -
| |
| Approved:
| |
| Plant Manager-l Nuclear i
| |
| | |
| i l
| |
| 1 l
| |
| WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 'N''1' 61 Titie hdMR M?~ 6-A/ec Effective Date Sd L-I (if different from approval date) t* nan ni sta 1. B. ar C A. Change No. 'M B. Revision No. 3 C. Deletion A/f l
| |
| arannN FOR CHAMdF_ RETTMTON. OR DEL FTTO M T l r-%, c;- o & 4 A G .- ;7l.>,e ,.-
| |
| ~
| |
| [ ASC- "/Dr% :3 4 aranTurn sicMatun . g-Originator d Date b DT7 Technical ReviM M h U N n- -
| |
| e~ ~
| |
| Dato 7 '- t 23 SAFETT EVALUATION
| |
| ;. Does this change, revision, or deletion: YES NO
| |
| : 1. Change the facility as described in the FSAR7 K
| |
| : 2. Change the procedures as described in the FSAR7- X
| |
| : 3. Conduct tests / experiments not described in the FSAR7 ,. I
| |
| : 4. Create a condition or conduct an operation which ex- _. '/,
| |
| coeds, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
| |
| Safety Evaluation bMIh' -
| |
| Date Group /Dep't. Head Review M8Md* Mate
| |
| /
| |
| P- Et M Temporary Approvale Date - (NCS)
| |
| Temporary Approvale Date QC Review - #AdebM- Date t - M -M PORC Review A IMd Date C) - 2 3- 3 3 Meeting No. "3 - '' E PlantManageh-NuclearAppr oval A'' -
| |
| , Date 1 i
| |
| * Temporary approval must be followed by Plant Manager-Nuclear approval within-14 days.
| |
| -UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
| |
| - - ._ __.___._______..__.____..._.__._...-._....-___.___..._____.a_-.._-
| |
| | |
| Em rgoncy Plcn Impicmsnting Proceduro EP-2-052 Protective Action Guidelines Revision 3 l
| |
| TABLE OF CONTENTS 1.0 PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 30 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 50 PROCEDURE
| |
| ~
| |
| 51 . TAB A - Uncontrolled Release of Radioactivity 52 TAB B - Loss of RCS Inventory 53 TAB C - DNB/ Degraded Core Sequence 5.4 TAB D - Loss of Safety Functions 5.5 TAB E - Hazard to Station Operations 5.6' TAB F --Natural Phenomena 57 TAB'G - Security Compromise -
| |
| 5.8 TAB H - Miscellaneous .
| |
| _. 4 6.0 FINAL CONDITIONS 70 ATTACHMENTS 71 Protective Action Guidelines Worksheet (1 page) 72 Affected Sectors / Protective Response Areas Chart (1 page) 73 Evacuation Time Estimate Table (1 page) l 74 Protective Response Areas (1 page) 75 Flow Chart for Protective Action Decision-Making Based on Core Conditions (1 page) l LIST OF EFFECTIVE PAGES Title Revision 3 1-22 Revision 3 1
| |
| | |
| E2 rgcnay-Plan Implcmsnting Procadure EP-2-052 Protective Action Guidelines Revision 3 1.0 PURPOSE To provide guidance for protective action decision-making with 1 respect to the EPA Protective Action Guidelines (PAG's) and tnose severe conditions where potential hazards exist but dose projections are not required.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| l 2.1 Waterford 3 SES Emergency Plan 2.2 Waterford 3 SES Evacuation Time Study 23 EPA-520, Manual of Protective Action Guides 2.4 EP-1-001, Recognition and Classification of Emergency Conditions 2.5 EP-1-010, Notifications and Communications 2.6 EP-2-050, Offsite Dose Assessment (Manual) 27 EP-2-051, Offsite Dose Assessment (Computerized) 2.8 NUREG-0654 Appendix 1 - Example Initiating Conditions - General Emergency 30 RESPONS1BILITIES 31 The Emergency Coordinator or EOF Director (upon activation of the EOF) is responsible for making protective action recommendations to off-site agencies. This responsibility shall not be delegated.
| |
| 32 The Emergency Coordinator or designee is responsible for the implementation of this procedure. 1 3 2.1 Upon activation of the Emergency Operations Facility (EOF), this responsibility may be transferred to the EOF Director or his designee.
| |
| l 2
| |
| U
| |
| | |
| -Em:rgancy Plcn ImplGasnting Procedure EP-2-052 Protective Action Guidelines Revision 3 4.0 INITIATING CONDITIONS This procedure shall be initiated upon reaching any of the following ;
| |
| conditions:
| |
| 4.2 An emergency condition requiring dose assessment / projections has been declared at Waterford 3 SES.
| |
| 4.2 An emergency condition which has the potential of breaching any one of the three fission product barriers and challenging the two remaining barriers has.been declared at Waterford 3 SES.
| |
| 4.3 As instructed by other implementing procedures, especially EP-1-001, Recognition and Classification of Emergency Conditions.
| |
| 4.4 At the direction of the Emergency Coordinator (or EOF Director).
| |
| 50 PROCEDURE This procedure relates directly to TABS A through H of EP-1-001, Recognition and Classification of Emergency Conditions. The appropriate protective action guidelines for each class of emergency are referenced in the corresponding Tabs of this procedure.
| |
| TAB A deals with releases of radioactivity known to be occurring.
| |
| i l
| |
| TABS B through H deal with situations wherein releases of l radioactivity are not occurring, but where there is a potential for l
| |
| such a release due to the nature of the emergency.
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| l t
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| ~'
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| l l
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| l l
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| t 3 l
| |
| | |
| Eecrgsncy Plan Impicmonting Procedure EP-2-052 Protective Action Guidelines Revision 3 NOTE For any situation where there is a ootential for the uncontrolled release of radioactive material, calculations should be done in accordance with EP-2-051 or EP-2-050 based on the radioactive material available for release.
| |
| These calculations provide early consideration for protective actions based on a presumed rcdiologi- -
| |
| cal release using TAB A.
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| e l
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| 4
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| | |
| Emsrgency Plen Implcmonting Procedure EP-2-052 Protective Action Guidelines Revision 3 51 TAB A - UNCONTROLLED RELEASE OF RADIOACTIVITY NOTE This portion of the procedure provides the in-structions for using the Protective Action Guide-lines Worksheet, Attachment 7 1, to determine the need for off-site protective actions with respect to dose projections. This worksheet is also the record of decisions made.
| |
| 5 1.1 Ensure that off-site dose calculations are performed in accordance with EP-2-051 or EP-2-050. Obtain the whole body and child thyroid dose rates for the locations of interest from the Health .
| |
| Physics Coordinator (for the Emergency Coordinator), the Radiological Assessment Coordinator (for the Emergency Operations Facility Director.), or on-shift personnel performing calculations if the TSC and EOF are not staffed.
| |
| 5 1.2 If the duration of the release is known, perform section 5 1.2.
| |
| If the duration is unknown, proceed to section 5.1 3 and do not perform section 5.1.2.
| |
| 5.1.2.1 Calculate the projected whole body and child thyroid doses by multiplying the dose rates by 'the release duration.
| |
| 5 1.2.2 If the calculated dose is less -than 1 rem whole body or 5 rems child thyroid, no protective actions are necessary at this time. Continue updating doze projections for protective actions determination.
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| 5.1.2.3 If the calculated dose is less than 5 rems whole body or 5 to less than 25 rems child thyroid, recommend sheltering and access l control to the affected areas as protective actions.
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| 5
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| Eccrgsncy Plan Impicnenting Proceduro EP-2-052 Protective Action Guidelines Revision 3 1
| |
| NOTE Affected sectors are first identified as the plume centerline sector and the two adjacent sectors. Then, the affected area will be identified by relating the sectors to areas using Attachments 7 2 and 7 4. If a major portion of the plume lies in any given pro-tective response area, protective action --
| |
| recommendations are given for that entire area.
| |
| i 5 1.2.4 If the projected dose is greate. than 5 rems whole body or 25 rems child thyroid, determine the protective actions based on the duration of the release.
| |
| A. If the release duration is greater than two (2) hours, recommend evacuation and access control of the affected areas as protective actions.
| |
| B. If the release duration is less than two (2) hours, determine Plume Travel Time (PTT) and Estimated Evacuation Time (EET).
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| l 6
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| | |
| Encrg0ncy Plcn Irplc3cnting Procodure EP-2-052 Protective Action Guidelines Revision 3 NOTE Determine the Estimated Evacuation Time by com-paring the affected sectors with the protective response areas as shown in Attachment 7 2 and correlating these protective response areas with Attachment 7 3, Estimated Evacuation Time Table.
| |
| In estimating evacuation times, local constraints
| |
| .uch as severe weather, road conditions, etc. .
| |
| should be taken into consideration. Determine the Plume Travel Time by dividing the distance from the plant to the affected area (s) (or approximate distance to population of interest) by the wind speed.
| |
| C. If the Plume Travel Time is less than Estimated Evacuation Time, recommend sheltering and access con. trol.to the affected areas as _'
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| protective actions.
| |
| D. If the Plume Travel Time is greater than the Estimated Evacuation Time, recommend evacuation and access control to the affected areas as protective actions.
| |
| I r
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| I 7
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| | |
| Excrg0ncy Plcn Impicm:nting Proceduro EP-2-052 Protective Action Guidelines Revision 3 513 Duration of Release is Unknown i NOTE Affected sectors are first identified as the plume centerline sector and the two adjacent sectors. Then, the affect'ed area will be identified by relating the sectors to areas using Attachments 7 2 and 7 4. If a major
| |
| ~
| |
| portion of the plume lies in any given protective response area, protective action recommendations are to be given for the entire area.
| |
| 5.1 3 1 If the whole body dose rate is less than 250 mrem /hr and the child thyroid dose rate is less than 1250 mrem /hr, no immediate protective actions are needed.
| |
| 5.1 3 2 If the whole body dose rate is greater than 250 mrem /hr but less than 1250 mrem /hr, or if the child thyroid dose rate is greater than 1250 mrem /hr but less than 6250 mrem /hr, recommend sheltering and access control to the affected protective response areas.
| |
| l l 5.1 3 3 If the whole body dose rate is greater than 1250 mrem /hr or if the child thyroid dose rate is greater than 6250 mrem /hr, recom-mend evacuation and access control to the affected protective response areas.
| |
| 8
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| | |
| i Em:rg0ncy Plcn ISpicasnting Proccduro EP-2-052 Protective Action Guidelines Revision 3 52 TAB B - LOSS OF RCS INVENTORY g 5.2.1 Under the ALERT classification, there is a potential for uncontrolled release of radioactive materials. Calculations of potential off-site doses should be made using the procedure referenced in TAB A.
| |
| 5.2.2 Under the SITE AREA EMERGENCY classification, Condition 1, refer to decision-making flow chart, Attachment 7 5. Note that the flow chart pertains to general emergencies. However, this situation is -
| |
| serious enough so that consideration should be given to the protective actions specified in the flow chart.
| |
| 5.2 2.1 Under the SITE AREA EMERGENCY classification, Conditions 2 or 3, use the procedure referenced in 5 2.1 above.
| |
| 5.2 3 GENERAL EMERGENCY. Refer to Attachment 7 5. Note 2-mile and 5-mile sheltering requirements. For core melt sequences where significant releases from containment are not yet taking place and large amounts of fission products are not yet in the containment atmosphere, consider 2-mile precautionary evacuation. Consider 5-mile downwind evacuation (45- to 90- degree sector) if large amounts of fission products (greater than gap activity) are in the l containment atmosphere. Recommend sheltering in other parts of the plume exposure Emergency Planning Zone under this circumstance.
| |
| 5.2 3 1 For core melt sequences where significant releases from containment are not yet taking place, where containment failure leading to a direct atmosphere release is likely in the sequence but not imminent, and where large amounts of fission products in addition to noble gases are in the containment atmosphere, consider precautionary evacuation to the 5-mile radius and 10-mile downwind evacuation (45- to 90-degree sector).
| |
| 5.2 3 2 For core melt sequences where large amounts or fission products other than noble gases are in the containment atmosphere and containment failure is judged imminent, recommend shelter for 9
| |
| | |
| . Eastgency.Plcn Inplcranting Procedure EP-2-052 Protective. Action Guidelines Revision 3 those areas where evacuation cannot be completed before J i
| |
| transport of activity to that location.
| |
| t I
| |
| E e
| |
| e d-1 1
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| i i
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| : r. , _ . _ - . _
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| | |
| l Excrg;ncy Plcn Impicmsnting Proceduro EP-2-052 Protective Action Guidelines Revision 3 1
| |
| , l 53 TAB C - DNB/ DEGRADED CORE SEQUENCE 531 Under the ALERI classification there is a potential for uncontrolled release of radioactive materials. Calculations of potential off-site doses should be made using the procedure referenced in TAB A.
| |
| 532 Under the SITE AREA EMERGENCY classification, refer to decision-making flow chart, Attachment 7 5. Note that the flow chart pertains to General Emergencies. However, this situation is -
| |
| serious enough so that consideration should be given to the protective actions specified in the flow chart. l 533 GENERAL EMERGENCY., Refer to Attachment 7 5 Note 2-mile and 5-mile sheltering requirements. For core melt sequences where significant releases from containment are not yet taking place and large amounts of fission products are not yet'in the containment atmosphere, consider 2-mile precautionary evacuation. Consider 5-mile downwind evacuation (45- to 90-degree sector) if large amounts of fission products (greater than gap activity) are in the containment atmosphere. Recommend sheltering in other parts or the plume exposure Emergency Planning Zone under this circumstance.
| |
| 5,3 3 1 For core melt sequences where significant releases from containment are not yet taking place, where containment failure l leading to a direct atmosphere release is likely in the sequence but not imminent, and where large amounts-of fission products in addition to noble gases are in the containment atmosphere, consider precautionary evacuation to the 5-mile radius and 10-mile downwind evacuation (45- to 90-degree sector) .
| |
| 5332 For core melt sequences where large amounts of fisaion products other than noble gases are in the containment atmosphere and i containment failure is judged imminent, recommend shelter for those areas where evacuation cannot be completed before transport of activity to that location.
| |
| 11
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| | |
| Eucrgoney Plcn Impicmsnting Proceduro EP-2-052 Protective Action Guidelines Revision 3 5.4 TAB D - LOSS OF SAFETY FUNCTIONS 5.4.1 Under Conditions 3, 4, and 5 of the SITE AREA EMERGENCY classification, there is a potential for core degradation. Refer to the decision-making flow chart, Attachment 7 5.
| |
| 5.4.2 . GENERAL EMERGENCY. Refer to Attachment 7 5. Note 2-mile and 5-mile sheltering requirements. For core melt sequences where significant releases from containment are not yet taking place and large amounts of fission products are not yet in the containment _
| |
| atmosphere, consider 2-mile precautionary evacuation. Consider 5-m11e downwind evacuation (45- to 90-degree sector) if large amounts of fission products (greater than gap activity) are in the containment atmosphere. Recommend sheltering in other parts of the plume exposure Emergency Planning Zone under this
| |
| - circumstance.
| |
| 5.4.2.1 For core melt sequences where significant releases from containment are not yet taking place, where contaiment failure leading to a direct atmosphere release is likely in the sequence but not imminent, and where large amounts of fission products in addition to noble gases are in the containment atmosphere, consider precautionary evacuation to the 5-mile radius and 10-mile downwind evacuation (45- to 90-degree sector).
| |
| l 5.4.2.2 For core melt sequences where large amounts of fission products
| |
| ~
| |
| other than noble gases are in the containment atmosphere and containment failure is judged imminent, recommend shelter for those areas where evacuation cannot be completed before transport of activity to that location.
| |
| 12
| |
| | |
| Encrgonoy Plcn Inplcacnting Procedure EP-2-052 Protective Action Guidelines Revisior. 3 55 TAB E - HAZARDS TO STATION OPERATION 5 5.1 GENERAL EMERGENCY. Refer to Attachment 7 5. Note 2-mile and 5-mile sheltering requirements. For core melt sequences where significant releases from containment are not yet taking place and large amounts of fission products are not yet in the containment atr.osphere, consider 2-mile precautionary evacution. Consider 5-mile downwind evacuation (45- to 90-degree sector) if large amounts of fission products -(greater than gap activity) are in the
| |
| ~
| |
| containment atmosphere. Recommend sheltering in other parts of the plume exposure Emergency Planning Zone under this :
| |
| circumstance.
| |
| 5.5.1.1 For core melt sequences where significant releases from
| |
| ; containment are not yet taking place, where containment failure leading to a direct atmosphere release is likely in the sequence but not imminent, and where large amounts of fission products in addition to noble gases are in the containment atmosphere, consider precautionary evacuation to the 5-mile radius an'd i 10-mile downwind evacuation (45- to 90-degree sector) .
| |
| l 5.5.2 For core melt sequences where large 2 mounts of fission products other than noble gaces are in the containment atmosphere and containment failure is judged imminent, recommend shelter for L those areas where evacuation cannot be completed before transport of activity to that location.
| |
| *4
| |
| * l [
| |
| 13
| |
| | |
| i . Ensrgency Plcn Impismenting Procedure EP-2-052
| |
| : . Protective Action: Guidelines Revision 3 5J6_. TAB F.- NATURAL PHENOMENA.
| |
| 5.6.1 GENERAL EMERGENCY. Refer to Attachment 7 5. Note 2-mile and 5-mile sheltering requirements. For core melt sequences where significant releases from containment are not yet taking place and large amounts of fission products are not yet in the containment atmosphere, consider 2-mile precautionary evacuation. Consider 5-mile downwind evacuation (45- to 90-degree sector) if large.
| |
| amounts of fission products (greater than gap activity) are in the
| |
| . containment atmosphere. Recommend sheltering in other parts of the plume exposure Emergency Planning Zone under this circumstance.
| |
| . 5.6.1.1 For core melt sequences where significant releases from containment are not yet taking place y whers containment failure leading to a direct atmosphere release is likely in,the sequence but not imminent, and where large amounts of fission products in
| |
| . addition to noble gases are in the. cont'ainment atmosphere, consider precautionary evacuation to'the 5-mile radius and 10-mile downwind evacuation (45- to. 90-degree sector) .
| |
| 5.6.2 For core melt sequences where large amounts of fission products other than noble gases are in the containment atmosphere and containment failure is' judged imminent, recommend shelter for those areas where evacuation cannot be completed before transport of activity to that location.
| |
| 4 14
| |
| | |
| Escrgency Plan Impicmsnting Proceduro EP-2-052 Protective Action Guidelines Revision 3 57 TAB G - SECURITY COMPROMISE '
| |
| NOTE Imminent or actual loss of physical security
| |
| __ control of the plant requires that a precautionary evacuation out to 2 miles be recommended to LNED and parish officials.
| |
| 571 GENERAL EMERGENCY. Refer to Attachment 7 5 Note 2-mile and 5-mile sheltering requirements. For core melt sequences where significant releases from containment are not yet taking place and large amounts of fission products are not yet in the containment atmosphere, consider 2-mile precautionary evacuation. Consider 5-mile downwind evacuation (45- to 90-degree sector) if large amounts of fission products (greater than gap activity) are in the containment atmosphere. Recommend sheltering in other parts or the plume exposure Emergency Planning Zone under this circumstance.
| |
| l 5 7 1.1 For core melt sequences where significant releases from l containment are not yet taking place, where containment failure leading to a direct atmosphere release is likely in the sequence but not imminent, and where large amounts of fission products in addition to noble gases are in the containment atmosphere, consider precautionary evacuation to the 5-mile radius and 10-mile downwind evacuation (45- to 90-degree sector).
| |
| l 572 For core melt sequences where large amounts of fission products other than noble gases are in the containment atmosphere and containment failure is judged imminent, recommend shelter for those areas where evacuation cannot be completed before transport of activity to that location.
| |
| l l
| |
| 15
| |
| | |
| 'Ecarg0ncy Plan Impismanting Procedure EP-2-052 Protective Action Guidelines Revision 3 5.8 TAB H - MISCELLANEOUS -
| |
| ~
| |
| 5.8.1 GENERAL EMERGEllCY. Refer to Attachment 7 5 Note 2-mile and 5-mile sheltering requirements. For core melt sequences where significant releases from containment are not yet taking place and large amounts of fission products are not yet in the containment-atmosphere, consider 2-mile precautionary evacuation. Consider 5-mile- downwind evacuation (45- to 90-degree sector) if large amounts-of-fission products (greater than gap act ity) are in the containment atmosphere. Recommend sheltering in o: er parts of the plume exposure Emergency Planning Zone under th.s circumstance.
| |
| 5.8.1.1 For core melt sequences where significant releases from containment are not yet taking place, where containment failure leading to a direct atmosphere release is likely in the sequence but not imminent, and where large amounts of fission products in addition to noble gases are in the containment atmosphere, consider precautionary evacuation to the 5-mile radius and 10-mile downwind evacuation -(45- to 90-degree sector) .
| |
| 5.8.1.2 For core melt sequences where large amounts of fission products other_ than noble gases are in the containment atmosphere and containment failure is judged imminent, recommend shelter for those areas where evacuation cannot be completed before transport of activity to that location.
| |
| 5.8.2 To determine if the EPA thyroid or whole body dose guidelines could be exceeded, refer to TAB A of this procedure.
| |
| 16
| |
| | |
| ECrgency Plan Implssanting Procedure .EP-2-052 Protective Action. Guidelines Revision 3 0.0 FINAL CONDITIONS -
| |
| 6.1 .The radiological release has stopped or diminished and dose projections are b'elow Protective Action Guidelines.
| |
| ~
| |
| -6.2' The emergency condition has been closed out and recovery actions are under way.
| |
| 70 ATTACHNENTS 71 Protective Action Guidelines Worksheet _
| |
| 72 Affecteo Sectors / Protective Response Areas Chart ,
| |
| '73 Evacuation Time Estimate Table 7 4- Protective Response Areas 75 Flow Chart for Protective Action Decision-Making Based on Core Conditions l
| |
| I l-l l
| |
| l l 17
| |
| | |
| o
| |
| .. * '. D , . , ,
| |
| . 't - . . ...
| |
| PROTECTIVE ACTION .- ,p J GUI.DELINES .'.WORKSHEET
| |
| .s.a.., .. -
| |
| .- * '; PROT, RESR AREA
| |
| . DATE .
| |
| i .
| |
| ' , i . J'
| |
| ... ., DETERMINE ,; . .
| |
| ' . DISTANCE TIME . ,.. -J -..* DOS. E ' RATE, .. .''*
| |
| T*
| |
| ; USER , ,
| |
| mR/Is CHE.D TH1 ! '
| |
| ETT
| |
| .e ..
| |
| PROJECTED DOSE -?
| |
| fDURATIOl( OF-YES NO. .) 250 mR/lw. W S P NO NO IMMEDIATE R WHOLE BODY 7 .RIIEASE ~.KNOW p-
| |
| . ' e, 7 ~ g '..'
| |
| ,4 3 T PROTECTIVE ACTION R CHILD THY.
| |
| .A.
| |
| t; '.' " t .,
| |
| 5
| |
| .) .l250 mR/lw. TilY.?
| |
| . .., .f c '.. .ij. .'
| |
| 'i!.'
| |
| 'if. ... YES
| |
| ... . .. 4::% .1., . y;*.- .~. .. .
| |
| . - . .s L..
| |
| f NO PROTECTIVE NO ,> IR W W 800p?
| |
| * 7;s. ,Vj,,[ . [ ~ J' ' ', f . *h
| |
| '1850 mR/sw. W 8 P NO OR SHELTER
| |
| ..'s . .. . . . .
| |
| > 3R CilE.D THY ?~
| |
| , :. ' ; '.[. .'.5,2, r..,.
| |
| [ ' 3 ''.'. ,.,\,. -g 625Q mR/k THW YE S' * . Y' ** I .'
| |
| . ',-. ".']f.,.( _ . .,y
| |
| .s s
| |
| , YES ,
| |
| . 4 . 't ,
| |
| i NO > 5 R WHOLE 80DYi '
| |
| - c *. .. ., ''5 ^ '
| |
| ..r- ' . '
| |
| i SHELTER OR *
| |
| !a . - t -
| |
| . e.
| |
| EVACUATE
| |
| > 25 R CHILD. THY. ? * .;. '.p,. r.f.'
| |
| .. w l
| |
| . . ... . :. . . . .' .c YES' ' . . -
| |
| < .._. . ,. .., C. ,,.,
| |
| .' /.,*. , ... . .:
| |
| . 3 YES I .
| |
| DURATION Jic'.4'..' N '-i '' '
| |
| EVACUATION
| |
| ) 2 IlOURS .*,-
| |
| ?
| |
| a . .',
| |
| 8
| |
| +
| |
| , * - ?..; ,... ,:. ... .
| |
| NO e '.- "''-
| |
| i.. .
| |
| .. . . ~
| |
| * YES **. ' /*.'.- ?.
| |
| i, I SHELTER PTT ( EET- # ' '' ' .' I -
| |
| .'/}i.
| |
| a ;.. . . . ;. r:;;
| |
| ; .,.,, i. :. < .
| |
| ..s ' . ' ,i ,' .
| |
| s NO fr..-
| |
| . . ~ ' -*
| |
| - d ." -
| |
| -; (.
| |
| .' .
| |
| * r8*. ,6'-
| |
| , *. , o 1.', ,.g ; : *
| |
| :l; 1.,;
| |
| . .~,4.:. .s 3
| |
| EVACUATION
| |
| .o
| |
| ; t p: ; ' c i,.
| |
| : i. r I
| |
| . 4 'f.
| |
| . ..e . ; L ;, . . '.. . '- ..;
| |
| \ .. .- -I' *
| |
| :*l.
| |
| . .V
| |
| .: . l? -
| |
| l EP- 2 -052 ''!'"...-
| |
| RE V. 2-
| |
| * o e . .*..rp
| |
| .' i. '.:.,., , ...
| |
| ; ., b-.' c./ *. 'l'8 } - ; .'..'s.
| |
| 8
| |
| . .j
| |
| ' .e..-
| |
| . ' . f.., .
| |
| ATTAcilMENT 7.1 ( l OF I )=
| |
| ,,f.. .
| |
| l t
| |
| - = ~ . _ _ _ . .
| |
| | |
| AFFECTED SECTORS / PROTECTIVE RESPONSE AREAS CHART AFFECTED.
| |
| SECTCRS Q-2 miles 2-8 mil 31 E-10 milea .
| |
| A,B,C A1 A2, B2 A3, B4 '
| |
| B,C,D A1, B1 A2, B2 A3, B4 C,D,E B1, D 1 B2, D2 B3, S4 D,E,F B1, D1 B2, D2 B3, B4, D3 E,F,G D1 B2, D2 B3, B4, D 3 F,G,H D1 D2 B3, D3, D4 G,H,J D1 D2 D3, D4 H, J ,K. D1 D2 D4 J,K,L C 1, D 1 C2,D2 CD, D4 -
| |
| K,L,M C 1 , D 1, C2, D2 C4, D4 L,M,N C1 C2 C4 M,N,P C1 C2 A4, C3, C4 N,P,Q C1 C2 A4, C 3, C4 P,Q,R C1 A2, C2 A4, C3 Q,R,A A1, C1 A2, C2 A3, A4 R,A,B A1, C 1 A2, C2 A3, A4 Directions For Use:
| |
| Find the plume centerline sector and two adjacent sectors in the "Affectec Sectors" column. The corresponding Protective Response Areas in which protective cctions are to be implemented can then be found for
| |
| -downwind distances of interest by reading across the page.
| |
| l l
| |
| i .
| |
| l l
| |
| l l
| |
| l EP-2-052 Revision 3 '9 Attachment 7 2 (1 of 1) l L
| |
| | |
| EVACUATION TTME ESTIMATE TABLE (#1 Evccuation Time Estimate Protective Response Clear Weather Adverse Weather Comcass Cuadrant . Area Hours Minn11a Hours M i r.u te s 0-2 Miles SW c1 1 45 1 45 SE D1 2 15 2 30 NE B1 No Population No Population NW A1 1 45 1 45 Entire 2-Mile Area 2 15 2 30 0-5 Miles SW ct, C2 2 15 2 30 SE D 1, D 2 3 30 4 30 NE B1, B2 3 30 4 15 ,
| |
| NW A1, A2 5 15 7 30 Entire 5-Mile Area 5 15
| |
| { 30 0-10 Miles SW c1, c2, c3, c4 2 15 2 30 SE D1, D2, D3, D4 4 15 6 00 NE B1, B2, B3, B4 3 45 4 30 NW A1, A2, A3, A4 5 15 7 30
| |
| $ntire 10-Mile Area 5 15 7 30
| |
| * Time to completely evacuate an evacuation area measdred from the time of Eobilization.
| |
| EP-2-052 Revision 3 20 Attachment 7 3 (1 of 1)
| |
| | |
| i
| |
| \ . .
| |
| 'A3 0 A4 .
| |
| sans r us.au,
| |
| /
| |
| M8 * -A 2 j p as.
| |
| - ~
| |
| s s . y 4 *
| |
| '~~ ,
| |
| D2 C3 f .
| |
| ,s f
| |
| ~
| |
| f C4
| |
| ' l f$ : C2 Cf Di est
| |
| ~
| |
| e nsuss essasi i suas ' -
| |
| g l
| |
| p
| |
| [
| |
| soltam 7
| |
| ine Dee Allemands g
| |
| I
| |
| .o2 T D3 x
| |
| i.ssi a
| |
| f -
| |
| , 9-j i
| |
| e Msa asb
| |
| ' D4 -
| |
| souti.
| |
| Parnells PROTECTIVE .
| |
| RESRONSE AREAS -
| |
| 44 EP 2-052 Rev. 3 21
| |
| , I
| |
| | |
| I I
| |
| TL ' .h..RT ~i l ?ie!!C:*?! sCT '
| |
| :.!'.!!! 2:-MAK!"* M3 E- *-
| |
| J :?.I . T : ; :.3 THI .'LLcWING ACT* c::S W!L*. 3E 3A>C d' HCITEMtINC 03$217A2*_s
| |
| * MTR.'!INTa!!
| |
| * 2 ?LA::T 3!A!"3 INDICATt'R3 EALs Ce': TAI::C IN 3: OtER0E*:C** d'.x: . ;=A agg 3EEN RE"IEWC 3Y OFFS!!E :FFICIAL3 HOWEVER RESPONSI3L: CFFS!!! 'FF!4ALs : La.
| |
| DECIDE ON THE FCA3I3tLITY CF IMPLD'ENTING THE PROTEC*IVE ACTICNS A! iME T;ME vF *HE ACCCENT.
| |
| CONTRGL ROOM STAFF DETECT "ACT'J u '
| |
| l OR POSSIBLE" GENERAL DIERGENCY RECOMMEND $HELTER 2-MILE RADIUS -
| |
| 5-MILES Co*4:WI:0 "!F SECURIM CCMPROMISE . TA3 G . RECCFMC"D EVACUATION TO 2-MILE RADIUS .gg)
| |
| UN ASSESSMENT
| |
| ,r .
| |
| a ::o SUBSTANTIAL /g CORE DAMAGO .(IA3 A, IN PROGRESS PAGs YES OR PILOJECTED ? NO (ACTUAL OR PROJECTED TO y POT CTIAL FOR EE IICICC '
| |
| 20% FUEL DAMAGE )
| |
| F N *(2) YES PRODUCT
| |
| .0 INVENTORY TES IM l RECCMMENL PROTECTI'.*E CONTAiNMCT ACTIONS IN
| |
| ' I' MORE THAN ''
| |
| GAP ACCCRDANCE '.*ITH
| |
| ? " TAB A" PACJ DO:INCT PECOMMEND SHELTER IMMINENT FOR AREAS THAT PROJECTED oRO CONTAINMENT CAN'T BE E7ACUATD TES
| |
| #. ''^ '. JECTC e.~
| |
| 3EFORE PLUME ARRIVAL TES FAILURE FAIL'.'R . ' ' EVACUA!E OTHERS AND CORE 3R RELIASE WITHIN (2-5 MILES: UhEYfaSO 'e
| |
| *"NDERWAY
| |
| . UNDERWAY,?
| |
| , DEBS TH,gS E
| |
| ./3) ATTACHMENTS *(3) ,
| |
| V *n) InQp and 7.3 j No
| |
| 'f y NO RECOMMEND EVAC 0ATION RECOMMITJ EVACCATTrW
| |
| - JF 2-MIL: RADIUS OF 3-MILE RADIUS 5-MII/ DOW': WIND to.MTT Et N5': WIND
| |
| *t!> weei *(l) era)
| |
| 'I f
| |
| *ft) SITUATIONS REQUIRING URCENT ACTION 3Y OFFSITE OFFICIALS (SASED 05 CONTROL RCOM INDICATORS. NO DOSE PROJECTTONS REQUIRED) 15-MINUTE DECISION MAKI'G. ACTIVATION OF ALERTING SYSTDt & E35 MESSAGE.
| |
| *';< ACT"AL OR PROJECTED RELIASE OF 20*. CAP FRCM CCRE OR LCSS 0F PHYSICAL CertROL OF THE PLANT TO INTRUDERS.
| |
| *d) "P'.TT" RELEASE Fa!E MUCH CREATER *HAN DESIGNU LEAK RATE.
| |
| =s , FOR ALL E'.*ACUATIONS SHELIER THE RDtI:OER 0F THE PLUME EPZ & PROMPTLY RELi<. ATE THE POPULATION AFTECT C SY ANY GROUND CCNTAMINATICN FCLTOWT':t: M t'vE PASSAGE.
| |
| *'51 CONCINTRATE 05 WAC"AI!ON OF AREAS NEAR TME PLANT, MAY 3E tut! TO EVACUATE 2-MILE RADIUS 4 NOT THE 5-MILE RADIUS.
| |
| I?-2-.>51 REv.2 22 A c t ,c =,n t ,3 , ,y ;,
| |
| | |
| WATERFORD 3 SES
| |
| ~~
| |
| 9 PLANT OPERATING MANGAL ,
| |
| ,m -
| |
| LCUISIANA -
| |
| POWER & LIGHT YbS POM VOLUME 1n EP-2-060 POM SECTION 9 REVISION _
| |
| 3 Emergency Plan Implementing Procedure .
| |
| Radiological Field Monitoring LP&L Wl3 RECORDS l UN! CONTROLLED COPY DO NOT USE IN Mr( GAFETY-RELATED TESTING, fyAINTENANCE, OR CPERATIONAL ACTIVTTY PORC Meeting No., 84-01 l Raviewed: 'A @c -
| |
| ! / PORC Chair: nan N'
| |
| /g g [ k
| |
| /.
| |
| ; Approved: ' /"\,bA,U;I Plant Manager-Nuclear Approval Date Fuel Load Effective Date
| |
| | |
| ~
| |
| WATERFORD 3 SE3 .
| |
| , PLANT OPERATING MANUAL ,
| |
| CHANGE /RE7ISION/DELETIONREQUENT .
| |
| Title ? 4 . ' --
| |
| '' c'" '
| |
| Procedure No. ? '' ' "
| |
| ~..h. ,
| |
| Effective Date .E 3 ' -' '-
| |
| (if different from approval date) t - nista 1. n. ap C A. Change Eo. d4
| |
| : 5. Revision Be. 3 C. Deletion O '
| |
| semens ran ennwer_ arvTmTam. on ner.rTTom -
| |
| ?. n , _, ._ m .', ... .t .C C REonIRED stanTuntr'7] .O -
| |
| Originator '
| |
| ' / [ -[# " Date '
| |
| Tcchnical Revied' //M YN Date /" 6 ' N SAFETT ETALUATION
| |
| * Does this change, revision, or deletion: ,
| |
| TE3 NO 1.
| |
| Change the facility as described in the FSAR7 _ g 2.
| |
| Change the procedures as described in the F3AR7 v
| |
| : 3. Conduet testa /experimenta not described in the FSAR7 u-
| |
| : 4. Create a condition or conduct an operation which ex-coeda, or could result in exceeding, the limita in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50. 0 3 Evaluatiop checklist.
| |
| Safcty Evaluation ' - - M S -, ) _ Date / -/ -f !
| |
| Group /Dep't. Head Review MMdM Da te / Temporary Approval
| |
| * Date (NO3)
| |
| Temporary Approvals _. Da te -
| |
| QC Review M 'I^' 'd- -
| |
| - Date / ''
| |
| PORC Revi EMS $m. M - Date > M // & Meeting No.
| |
| Plant Manager-Nuclear Approval /_ Date -
| |
| 4
| |
| ' Temporary approval must' be followed by Plant Manager-Nuclear approval '
| |
| t:ithin 14 days.
| |
| UNT-1-003 Revision 6' Attachment 6.0 (1 of 1) 2G
| |
| | |
| Emergency Plta Implementing Procedure EP-2-060 Radiological Field Monitoring .- Revision 3 TABLE OF CONTENTS 1.0 PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS ,
| |
| 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Dose Rate and Air Sample Data Log (1 page) 7.2 Radiological Field Monitoring Kit Location and Contents (2 pages) 7.3 Ludlum 2218 Switch / Meter Locations (2 pages)
| |
| LIST OF EFFECTIVE PAGES Title Revision 3 1-18 Revision 3 LIST OF PAGES CONTAINING PROPRIETARY INFORMATION 5
| |
| 1
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring l Revision 3 1.0 PURPOSE To define the methods and techniques to be used when performing field '
| |
| monitoring following a suspected release of radioactive material.
| |
| This procedure is designed to be used in conjunction with EP-2-061, Emergency Environmental Monitoring.
| |
| | |
| ==2.0 REFERENCES==
| |
| 2.1 EP-2-050, Offsite Dose Assessment (Manual) 2.2 EP-2-051, Offsite Dose Assessment (Computerized) ,
| |
| 2.3 EP-2-061, Emergency Environmental Monitoring 2.4 EP-2-033, Administration of Iodine Blocking Agents 2.5 OP-2-101, Operational Support Center (OSC) Activation, Operation and Deactivation 3.0 RESP'NSIBILITIES O
| |
| The OSC Supervisor an'd Radiological Field Monitoring Teams are responsible for Laplementing this procedure.
| |
| 4.0 INITIATING CONDITIONS 4.1 This procedure is to be initiated upon any of the following c'onditions:
| |
| 4.1.1 Declaration of any of the following emergency classifications in which the event includes an actual or potential release of radioactive material to the atmosphere:
| |
| 4.1.1.1 Alert 4.1.1.2 Site Area Emergency 4.1.1.3 General Emergency 4.1.2 At the discretion of the Emergency Coordinator, EOF Director, l Haalth Physics Coordinator (HPC) or the Radiological Assessment Coordinator (RAC).
| |
| 2
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring / Revision 3 4
| |
| 5.0 PROCEDURE 5.1 ASSIGNMENT OF RADIOLOGICAL FIELD MONITORING TEAMS 5.1.1 The assignment of persennel to Radiological Field Monitoring Teams will be made by the Radiological Controls Coordinator at the direction of the Health Physics Coordinator or Emergency Coordinator.
| |
| 5.1.2 Each Radiological Field Monitoring Team should comprise two individuals, at least one qualified in the operation of the field .
| |
| monitoring equipment.
| |
| 5.2 Radiological Field Monitoring Teams will normally be dispatched from the Operational Support Center (OSC); however, the HPC may prescribe monitoring assignments upon initial notification of certain team members. The Radiological Field Monitoring Teams, as assigned, will proceed to the OSC.
| |
| 5.3 The team shall obtain a field monitoring kit. Kits with broken seals should be. avoided unless necessary.
| |
| 5.4 Each kit will be opened and quickly inventori~ed. Inventory lists are shown in Attachment 7.2 5.5 In addition to the inventory, the following equipment checks shall be performed:
| |
| 5.5.1 R0 Visual Check and Battery Check 5.5.2 Ludlum 2218 and Detector - Visual Check and Source Check with Barium-133 Source.
| |
| 3
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring ,
| |
| Revision 3 NOTE
| |
| : 1. This check is not to determine instrument efficiency. Once a response is noted (counts being accumulated), the instrument can be considered operational.
| |
| : 2. The Radiological Field Monitoring Teams
| |
| ~
| |
| will be directed by the Health Physics Coordinator (HPC) or, if activated by the HPC, the Dose Assessment Coordinator (DAC)
| |
| Once the EOF has been activated, the teams will be directed by the Radiological Assessment Coordinator or Field Team Controller. Onsite monitoring teams remain under the direction of the HPC.
| |
| 5.5.3 Radio Communications NOTE Installed radios are provided in the following vehicles: Health Physics pickup, Storeroom pickup, Metrology Lab pickup and Duty Plant Manager car.
| |
| 5.5.3.1 Radio Communications Check NOTE Communications must be established prior to leaving site.
| |
| 4 i
| |
| (
| |
| | |
| _ _ - . - . - .= - --- - . _ _ -_- - . . . -
| |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring .
| |
| Revision 3 A. For Alert emergencies (Technical Support Center activation),
| |
| establis'n communications with the TSC Dose Assessment l Communicator. ~
| |
| B. For Site Area and General Emergencies (EOF activation),'
| |
| establish communications with the TSC Dose Assecsment Communicator or with EOF Field Team Communicator at such time that responsibility for dose assessment has .
| |
| ~
| |
| ; been transferred to the EOF.
| |
| 5.5.3.2 Backup Communications ,.
| |
| NOTE
| |
| ' Portable radios are available in the OSC Health Physics equipment locker. A roll of dimes is provided in each field monitoring kit for coin-operated telephones.
| |
| l A. Establish communications with the TSC Dose Assessment Communicator or EOF Field Team Communicator via portable radio prior to leaving the OSC and establishing communications I with installed vehicle radios. Carry the portable radio, as a backup, in vehicles with installed radios. Portable radios will serve as the primary means of communication for vehicles l
| |
| I without' installed radios.
| |
| B. If radio communications are lost in the field, contact the TSC Dose Assessment Communicator or EOF Field Team Communicator via coin-operated telephone on the PABX line for further instructions:
| |
| TSC Dose Assessment Communicator:
| |
| EOF Field Team Communicator:
| |
| C. If communications cannot be established or maintained using any method, return to the OSC and report to the Radiological l Controls Coordinator for further instructions.
| |
| THE MATERIAL CONT'AINED WITHIN THE SYMBOLS ( ) IS PROPRIETARY OR PRIVATE INFORMATION l 5
| |
| - .,.-m.,,,,a .,r.., n-,-v, re, ,.,m.,---e---,,w---, -~~er-_ a-..,,,-w. . , , . . _ , , --_,-
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring ,
| |
| . Revision 3 5.6 During initial communications check, each item will receive a team designation (Alpha, Bravo, etc.) from the HPC/DAC or RAC/ Field Team Controller and initial instructions.
| |
| 5.7 Each team shall leave the OSC and obtain their designated vehicle.
| |
| NOTE -
| |
| : 1. The OSC Supervisor assigns, and makes available for use, vehicles in accordance with EP-2-101.
| |
| : 2. Vehicles are selected and assigned from the list below, which identifies vehicles and their parking locations.
| |
| 5.7.1 Teams shall obtain keys to assigned vehicles from the OSC Supervisor and pick up vehicles at the following designated parking locations: _ ,
| |
| ' Vehicle Parkins Location Health Physics pickup Health Physics trailer Duty Plant Manager car Duty Manager's Assigned Parking Location in Administration Parking Lot Metrolosy Lab pickup Service Building Storeroom pickup Service Building NOTE
| |
| : 1. As soon as teams leave the OSC, the dose rate instrument should be turned on and monitored continuously. The HPC/DAC or RAC should be updated on dose rates and location frequently.
| |
| ~ 2. Guidelines on radiological protection of field teams are in section 5.8 6
| |
| | |
| i Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring ,
| |
| . Revision 3
| |
| ;. 5.8 RADIOLOGICAL PROTECTION PRECAUTIONS 5.8.1 ~ During sampling and/or surveying in an affected area, good Health Physics practice should be used at all times. Some precautions are listed below.
| |
| 5.8.1.1 Maintain exposures ALARA..
| |
| 5.8.1.2 Prevent cross-contamination of samples and instruments.
| |
| 5.8.1.3 Count samples in as low a background area as possible.
| |
| 5.8.1.4 Make use of protective clothing, plastic bags, and other 3
| |
| equipment provided as necessary to minimize spread of contamination.
| |
| 5.8.1.5 Keep the HPC/DAC or RAC/ Field Team Controller informed of radiation l levels and remain aware of individual total exposures. ,
| |
| 1 5.8.2 The KI provided in tte kits-is to be used only as directed by the HPC or RAC as authorized by the Emergency Coordinator in accordance with EP-2-033.
| |
| 5.9 Proceed to the_ location as identified by the HPC/DAC or RAC/ Field Team Controller. At that location, perform tha following:
| |
| NOTE Survey locations used are normally those listed I
| |
| in the attachments to EP-2-061.
| |
| l 5.9.1 Gamma survey with R0-2 l
| |
| 5.9.2 Beta survey (open-window) with R0-2
| |
| , NOTE l
| |
| l.
| |
| Surveys should be performed with R0-2 held i vertically at one (1) meter above ground level.
| |
| The monitor should slowly rotate 360 degrees and determine the maximum dose rate.
| |
| 7 i
| |
| | |
| Emergency Plan Implementing Procedure EP-2-Ooo Radiological Field Monitoring . Revision 3 5.,10 Notify the HPC/DAC or RAC/ Field Team Controller of the levels monitored. I 5.10.1 If levels are below the minimum sensitivity of the instrument, report results as "less than" the minimum scale deflection.
| |
| 5.10.2~~ Report gamma levels only, unless otherwise requested. Beta readings (open-window) should be recorded but not reported.
| |
| 5.11 Record all data on Attachment 7.1.
| |
| . 5.12 Unless otherwise directed by the HPC/DAC or RAC/ Field Team Controller, j ,
| |
| obtain an air sample at this location as follows: -<
| |
| 5.12.1 Install particulate filter and silver zeolite cartridge in the air sampler cartridge holder. Air drawn into sampler must pass through particulate filter first, then through the silver zeolite cartridge. Silver zeolite cartridge must'be inserted so that air passes through in the direction of the arrow on the side of the cartridge.
| |
| 5.12.2 Turn on sampler and stopwatch. Note flow rate.
| |
| CAUTION Monitor flow rate frequently. If air sampler is powered by car. battery with the car running and the engine is then stopped, the flow rate will decrease.
| |
| 5.12.3 Run air sampler to obtain an air sample volume of at least 10 cubic feet.
| |
| CAUTION Air sampler should not be placed with the nozzle near any surface which is potentially contaminated.
| |
| 8
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring .' Revision 3 1
| |
| 5.12.4 While Air sampler is running, prepare two envelopes, labeling each with the following information:
| |
| 5.12.4.1 Date and Time 5.12.4.2 Sample Number 5.12.4.3 Location .
| |
| 5.12.4.4 Flow Rate (CFM) '
| |
| 5.12.4.5 Sampling Duration (minutes) -
| |
| NOTE I
| |
| Samples will be given a sequential number preceded ,
| |
| l by the team designation; i.e., A1, A2, A3, or Bi I
| |
| and so on.
| |
| 5.12.5 After appropriate volume is collected, stop air sampler, remove particulate filter and silver zeolite cartridge and place into envelopes. ,
| |
| 5.12.6 Record all sample data on Attachment 7.1.
| |
| 5.13 Unless otherwise directed by the KPC/DAC or RAC/ Field Team Controller, l analyze the air sample for iodine activity using the Ludlum 2218 as indicated below. Samples obtained on-site will normally be returned to the Health Physics Lab for analysis.
| |
| NOTE Background radiation levels may interfere with counting equipment. Field teams should always attempt to get out of the plume to count air samples. If dose rates exceed 5 mR/hr, do not attempt to count filters; proceed to low background area.
| |
| 9
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring ,- Revision 3 5.13.1 Verify (or set) the following settings on the Ludlum 2218 (see Attachment 7.3 for location of switches):
| |
| Switch Position A. Stabilizr.r Toggle Switch On B. Channel 1 Toggle Switch s In C. Channel 2 Toggle Switch Out D. Channel 1 Window As per calibration _
| |
| Sticker E. Channel 1 Threshold As per calibration Sticker :
| |
| F. Channel 1 Multiplier Bypass G. Channel 2 Multiplier Bypass H. Add-Off-Subtract Switch Channel 1 Add I. Add-0ff-Subtract Switch Channel 2 Off
| |
| ' J. -Live-Clock Toggle Switch Live K. Time-Multiplier Switch XI L. F-S Toggle Switch S M. Chl-Ch2-Sealer Switch CH1 N. Range XIK (Initially)
| |
| O. Recycle Toggle Switch (on back) Off NOTE Range setting should be reduced during counting to give on-scale reading.
| |
| = ,
| |
| 10
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 .
| |
| Radiological Field Monitoring ,
| |
| Revision 3 5.13.2 Detector Operation and Setup 5.13.2.1 Verify that the NaI detector is connected to the Ludlum 2218.
| |
| 5.13.2.2 Insert detector into shielded sample holder.
| |
| 5.13.2.3 Place power switch to "BATT." Allow approximately 5 minutes for equipment to stabilize.
| |
| 5.13.2.4 Set count timer to 2 minutes. Start the background count by pushing the COUNT RESET button. Run background count for 2 minutes. .
| |
| ~
| |
| .Use Attachment 7.1 for recording analysis data.
| |
| 5.13.2.5- Place silver zeolite cartridge in shielded sample holder with the inlet side of the cartridge facing the detector.
| |
| 5.13.2.6 Reset count timer to 5 minutes and push the COUNT RESET button.
| |
| Count sample for 5 minutes. Record on Attachment 7.1.
| |
| 5.14 Notify the KPC/DAC or RAC/ Field Team Controller of the results of l sampling and analysis for I-131 including:
| |
| ~
| |
| 5.14.1 Team Designstion ,
| |
| 5.14.2 Sample Number' 5.14.3 Sample Location 5.14.4 Sample Duration 5.14.5 Sample Flow Rate 5.14.6- Total Sample Counts (5-minute count)
| |
| ( 5.14.7 Total Background Counts (2-minute count)
| |
| ~
| |
| 5.15 Proceed as directed by the HPC/DAC or RAC/ Field Team Controller to l additional monitoring points. Continue performing surveys and air sampling / analysis as directed.
| |
| 5.16 While in transit to monitoring points, maintain continuous dose rate monitoring and notify the HPC/DAC or RAC/ Field Team Controller l of any significant findings, paying particular attention to the location of.the highest measured dose rates. ,
| |
| 11
| |
| - > ~ , _ ,_v_,.. _ -, .- , _ _ . , ,y r , - - , _ _ _ , . , , ,
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring ,' Revision 3 5.17 Retain all air samples in plastic bags for further analysis.
| |
| NOTE
| |
| -Coordination of all field monitoring data, including further analysis, is accomplished through the EOF organization (RAC). Samples will normally be returned to the OSC and
| |
| ~
| |
| analyzed on-site or at off-site facilities in accordance with existing agreements. The KPC/DAC or RAC/ Field Team Controller will l designate a specified location where all samples and data sheets will be returned if f
| |
| the OSC is not to be used.
| |
| 5.18 Field teams shall refer to EP-2-061 if instructed to perform
| |
| . environmental sampling (water, soil, TLD changeout, etc.) by the KPC/DAC or RAC/ Field Team Controller. l 6.0 FINAL CONDITIONS -
| |
| 6.1 Releases have been terminated or reduced to levels below the EAL's for an Alert emergency classification.
| |
| 6.2 All surveys and air samples requested have been completed.
| |
| 6.3 Vehicles and team members have been surveyed for contamination in a low background area and HPC/DAC or RAC/ Field Team Controller notified of l l
| |
| the results. Personnel have been scheduled for initial bioassay analysis.
| |
| I Vehicles have been returned to designated parking locations, the keys returned to the OSC Supervisor, or vehicles have been detained for further monitoring and decontamination.
| |
| 6.4 All data sheets, particulate filters and silver zeolite cartridges have been returned to the OSC or other locations defined by the KPC/DAC or RAC/ Field Team Controller. l 12
| |
| .-- ~, . ~, ,-
| |
| ,. n- . , , . . -- . . , , , - ~ . - . . . - ~ - , - , - , , ~ . .e, ,-... - , . , -, ,
| |
| | |
| Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring .' Revision 3 7.0 ATTACHMENTS 7 .1 - Dose Rate and Air Sample Data Log.
| |
| 7.2 Radiological Field Monitoring Kit I.ocation and Contents 7.3~ Ludlum 2218 Switch / Meter Locations D
| |
| .e 4
| |
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| RADIOLOGICAL FIELD MONITORING KIT LOCATION AND CONTENTS-Kit Locations Operational Support Center 4 Kits Kit Contents Ites Number R02 1 Air Sampler (battery) 1 CS-137 Button Check Source 1 Ba-133 Cartridge Check Source 1 Ludlum 2218 w/NaI Detector 1 Detector Cable 1 Sample Holder 1 Potassium Iodide (KI) (Bottles) 2 l EP-2-060 1 EP-2-061 1 Survey Location Maps 1 -
| |
| Writing Tablets 2 Clipboards 2 Pens 6 Marks-a-lot 1 Flashlights 2 Air Sample Filters inch (box) 1 Air Sample Envelopes 30
| |
| , Silver Zeolite Cartridges 10 l
| |
| Sample Bags 30 Tape inch-(roll) 1 "D" Cell Batteries 12 Stopwatch 1
| |
| . Screwdriver 1 9-Volt Battery 3 Shovel 1 EP-2-060 Revision 3 15 Attachment 7.2 (1 of 2) l
| |
| | |
| 7-
| |
| . RADIOLOGICAL FIELD MONITCRING KIT LOCATION AND C0h"IENTS-
| |
| -ITEM NUMBER Smears 50 1-Liter Container 1 Scissors 1 Roll of Dimes 1 Paper Coveralls (set) 3 Cotton Insert Gloves (sets) 3 Rubber Gloves (sets) 3 Log Sheets 10 Ludlum 177 w/ pancake proble 1 l EP-2-060 Revision 3 16 Attachment 7.2 (2 of 2) l
| |
| | |
| . CCC1JMENT REVIEW COMMENTS q i
| |
| &.s? '' ~- 1~ af.{.c
| |
| ?
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| CCO:JWENT NC.
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| t i, 1 !
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| l J i i 1 e I
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| i
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| ? 1 ?
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| 4 i 1
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| l 1 1 1 -
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| i I
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| ! 1
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| : 1. Reviewed Sy. t L.mc. -v* 4as::vce 3y:
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| 3 I. / t. t*)
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| Revsewer [y 'ets .h t *.cr :a
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| ,(, v s h*ts*$47 3. .%sciut'4n of ::mments Ac: art: g--
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| R evis->.- Oor I
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| l
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| ? 1069 81 C0 SU
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| WATERFORD 3 SES PLANT OPERATING MANUAL 72vv=b
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| ~~
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| ~
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| LOUISIANA
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| ' ~)M . POWER & LIGHT UEJSNN POM VOLUME 18 EP-2-061 POM SECTION 2 REVISION i Emergency Plan Implementing Procedures Emergency Environmental Monitoring LP&L W-3 RECORDS U NICO-NTROLLED COPY DO NOT UT: tN AN'/ SAFETY-RELATED TESTING, MAINTeiNANCE, OR OPERATIONAL ACTIVITY PORC Meeting No. 03-3Z Raviewed: y [ M M h _ '
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| PORC Chairman Approved: A L U Plant Manager-Nuclear Approval Date Fuel Load Effective Date
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| ~
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| WATERFORD 3 SE3 -
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| PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Precedure No. ff? N Title E-~-e-- '
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| ~ ~ ~ ~ , _. % 4: ,
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| Effective Date d' 5 " ~
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| (if different fria approval date) emniata 1. B. ap C A. Change No. d'Y
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| : 3. Eevision No. /
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| "id -
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| C. Deletion wrannu ron enant:r_ arvTsTom. on art mom ~
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| To .: +.,m la ,%- .GU o
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| f, D . /*
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| REQUIRED SIGNATURES ', [ . dN L6-fu - , ; ,
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| ' ' . , Mm . SM / L ln A Originator Date l Tcchnical Review N h M.wd/L de* Date < 7 h 7 47 -
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| SAFETT ETALUATION Does this change, revision, or deletion: TES NC
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| : 1. Change the facility as described in the FSAR7 Y
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| */
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| : 2. Change the procedures as described in the FSAR7- _ l l 3. Conduct tests / experiments not described in the FSAR7 l
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| : 4. Create & condition or esaduct an operation which ex- "
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| oeeds, or could result in exceeding, the limits in Technical Specifications?
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| r If the answer to any of the above is yes, complete and at-g tach a 10 CFR 50.59 Safety lustion checklist.
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| I Safety Evaluat, ion OM ! Dete /Z -27O Grcup/Dep't. Head Review Ns' N Md Date /2-27 W Temporary Approval
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| * Date (NO3)
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| Temporary Approvale Date QC Eeview A ll Off k J Date b 6 I ''
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| PORC Review- N f A 8I u - Date /-6 -F 7 Meeting No.
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| Pirnt Manager-Nuclear Approval Date -
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| ' Temporary approval auais be followed by Plant Manager-Nuclear approval l within 14 days.
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| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
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| I
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| . Emergency Plan Implementing Procedure EP-2-061 Emergency Environmental Monitoring' Revision 1 TABLE OF CONTENTS 1.0 PURPOSE .,
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| ==2.0 REFERENCES==
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| 3.0 RESPONSIBILITIES
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| ^
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| '4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Sample Location Table 7.2 Emergency Radiological Environmental Monitoring Points (7 pages) l 7.3 Emergency Survey Points - 914 Meter Exclusion Area Boundary (1 page) 7.4 Emergency-Survey Points - 10 Miles (1 page) 7.5 REMP Sample Location Table (4 pages) 7.6 REMP Sample I,ocations Within 2 Miles of Waterford 3 (1 page) 7.7 REMP Sample Locations Within 10 Miles of Waterford 3 (1 page) 7.8 REMP Sample Locations Within 50 Miles of Waterford 3 (1 page)
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| LIST OF EFFECTIVE PAGES Title Revision 1 1-33 Revision 1 i
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| i l
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| Emergency Plan Implementing Procedure EP-2-061 Emergency Environmental-Monitoring ,
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| Revision i 1.0 PURPOSE This procedure provides the instructions for environmental monitoring during and after.a radiological emergency at Waterford 3. It is designed to be used in conjunction with EP-2-060, Radiological Field Monitoring.
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| ==2.0 REFERENCES==
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| 2.1 - HP-2-900, Collection and Preparation of Water Samples 2.2 HP-2-902, Collection and Preparation of Milk Samples 2.3 HP-2-904, Collection and Preparation of Sediment Samples 2.4 HP-2-905, Collection and Preparation of Vegetation Samples
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| .2.5 HP-2-907, Collection and Preparation of Fish Samples 2.6 HP-2-908, Collection and Preparation of Environmental Air Samples 2.7 HP-2-909, Preparation and Distribution of Environmental Thermoluminescent Dosimeters 2.8 HP-2-911, Environmental Sample Shipment 2.9 HP-2-912, REMP Sample Recording 2.10 HP-1-230, Offsite Dose Calculation Manual
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| ~2.11'EP-2-050, Offsite Dose Assessment (Manual) 2.12 EP-2-060, Radiological Field Monitoring 2.13 General Services Agreement between Teledyne Isotopes and Louisiana Power and Light Company 2.14 HP-2-351, Operation of the Panasonic Automatic TLD Reader UD-710A l
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| ~2.15 HP-2-353, Operation of the Panasonic Manual TLD Reader UD-702E 3.0 RESPONSIBILITIES 3 .1. The Health Physics Coordinator (HPC)/ Radiological Assessment Coordinator (RAC) are responsible for ensuring the implementation of this. procedure.
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| 2
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| - Emergency Plan Implementing Procedure EP-2-061 Emergency Environmental Monitoring -
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| Revision 1 3.2'.The TSC Dose' Assessment. Coordinator (DAC)/ EOF Field Team Controller l and field monitoring teams are responsible for implementing this procedure.
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| ' 4.0 INITIATING CONDITIONS 4.1 This procedure is initiated upon any of the following conditions:
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| 4 4.1.1 Declaration of'any of the following. emergency classifications in which the event includes an actual or potential release of _
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| radioactive material to the environment:
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| 4.1.1.1 ^ Alert .
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| 4.1.1.2 Site Area Emergency 4.1.1.3 ' General Emergency 421'.2 At the discretion of the Health Physics Coordinator or Radiological Assessment Coordinator.
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| 4.1.3 As directed by the Emergency Coordinator or EOF Director.
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| ~
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| 5.0- PROCEDURE NOTE ~
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| Collection of environmental samples during emergency situations should be performed in conjunction with location and evaluation of the liquid and/or gaseous effluent. Samples should normally be collected after the initial radiological i effluent evaluation and should be collected for purposes of further evaluation of the release.
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| 5.1 Environmenta'l sampling in an emergency situation as outlined in section 5.7 of this procedure will be performed as directed by either the Health Physics Coordinator / Radiological Assessment Coordinator 3
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| . _ _ __ . , _ . _ , _ . - _ - . __ . _ _ _ _ . . _ . ~ _ . , _ - ,_ _
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| -Emergency Plan Implementing Procedure EP-2-061 Emergency Environmental _ Monitoring-Revision 1
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| .or the Dose Assessmen ' Coordinator / Field Team Controller and in l accordance with routine Ra'iological d Environmental' Monitoring Program-(REMP) sampling procedures (see References section) and instructions:provided in this procedure.
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| 5.2. Sampling equipment (with the exception of environmental TLD's) to be used in emergency situations is made available to field monitoring team personnel in the field monitoring kits specified in EP-2-060. ,
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| Additional equipment is available onsite. !
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| 5.3 All' samples shall be labeled with date and time the sample was taken, the ~ location, type of sample and name of ~ person taking the sample, as a' minimum. Samples shall be labeled in accordance with'the HP 900
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| . series 'of procedures (see References section) and instructions provided in this procedure.
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| ~
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| 5.4 -All samples collected in emergency situations should be1 returned to-the OSC as directed by the Dose Assessment Coordinator / Field Team Contro11er'and' prepared.for analysis in accordance with routine REMP procedures. The-Dose Assessment Coordinator / Field Team Controller-shall direct the type (s) of analysis t'o be performed in accordance -
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| with the parameters of the effluent release (type of release, type of sample and suspected contaminants).
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| Samples collected in emergency situations via section 5.7 of this 15.4.1 procedure.shall be initially analyzed by LP&L and then prepared for !
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| shipment to the REMP anlysis contractor (Teledyne Isotopes) in
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| :accordance with HP-2-911. .
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| & 9 4
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| i F i- - .- . i.- I- i i
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| . Emergency Plan Implementing Procedure EP-2-061 Emergency Environnental Monitoring . Revision 1 NOTE
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| ~Upon notification that an emergency exists at Waterford 3 SES, Teledyne will perform analysi:
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| in accordance with Reference 2.13 and results wil'be supplied within 24 hours of sample receipt.
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| 5.4.2 Samples may also be prepared and analyzed using Arkansas Pcuer and Light Company, Gulf States Utilities or Mississippi Power and Light Company facilities and equipment as necessary in accordance with existing agreements.
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| 5.5 DISPATCHING OF TEAMS 5.5.1 Teams are dispatched in accordance with EP-2-060 and the activities in this procedure should coincide with activities perfocmed l under EP-2-060.
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| - 5.5.2 Teams should normally be dispatched to locations selected from those listed in Attachments 7.1, Emergency Radiological Environmental Monitoring Points; and 7.4, REMP Sample Location Table. Attach:sents -
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| 7.2, 7.3, 7.5, 7.6 and 7.7 are maps to aid in finding these locations.
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| 5.6 Emergency environmental sampling activities shall be coordinated with l the Louisiana Nuclear Energy Division and the NRC, as appropriate.
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| 5.7 The following sar.ples will be collected in accordance with the impact of the radiological effluent release (s) and at the discretion of, and as directed by, either the Health Physics Coodinator/ Radiological Assessment Coordinator or the Dose Assessment Coordinator / Field Team Controller.
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| 5 i
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| it e
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| t
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| _ Emergency Plan Implementing Procedure EP-2-051 Emergency Environmental Monitoring . Revision 1 5.7.1 Airborne Release 5.7.1.1 Air Sampling A. Change out-routine (REMP) air samples in affected areas in accordance with HP-2-908.
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| B. untain air samples-in affected areas with portable air samplers in accordance with EP-2-060.
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| 5.7.1.2 Direct Radiation Readings (TLD) .
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| A. Change out routine (REMP) TLD's in affected areas in accordance with the appropriate.section of HP-2-909.
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| B. Set out additional TLD's at locations of interest in*accordance with HP-2-909.
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| C. TLD's~ collected in emergency situations wi1I be analyzed in accord-ance with the appropriate sections of HP-2-351 or HP-2-353.
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| 5.7.1.3 Vegetation Sampling A. REMP vegetation samples.(grass, brord-leafed vegetation and food products) should be collected in emergency situations in accordance with HP-2-905.
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| B. Additional vegetation samples should be collected at locations of interest in accordance with HP-2-905.
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| 5.7.1.4 Milk Sampling A. REMP milk samples should be collected in emergency situations in accordance with HP-2-902.
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| B. Additional milk samples may be collected at locations of interest in accordance with HP-2-902.
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| C. In situations where radioiodines have been assumed to constitute a percentage of the accidental gaseous effluent release, additional milk and grass sampling should be performed at least once every two 6
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| Emergency Plan Implementing Procedure EP-2-061 Emergency Environmental Monitoring . Revision 1 days following the initial release until radiciodine activity reaches an acceptable level.
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| ..5.7.1.5 Soil Sampling A. Soil sampling is not a REMP routine sample, but in emergency situations HP-2-904 will be used to co1Iect soil samples at locations of interest.
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| 5.7.1.6 Contamination Surveys .
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| A. Contamination surveys may be performed on selected surfaces by 2
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| smearing the swipe paper over an approximate 100 cm area.
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| B. Place the swipes in the provided envelopes and label in accordance with step _5.3.
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| 5.7.1.7 Water Sampling A. Obtain surface and potable water samples in accordance with HP-2-900 at locations of interest, as necessary.
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| 5.7.2 Liquid Release
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| ~
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| 5.7.2.1 Obtain REMP liquid samples in accordance with HP-2-900.
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| 5.7.2.2 Depending on the magnitude of liquid effluent released, REMP sediment and fish samples should be collected in accordance with HP-2-904 and HP-2-907, respectively.
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| 5.7.2.3 - Additional waterborne sampling may be performed at locations of interest in accordance with HP-2-900, HP-2-904 and HP-2-907.
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| '5.8 Field monitoring kits are equipped with sampling equipment. In some cases, it may be necessary for teacs to return to the site for additional supplies.
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| S'. 9 Frequency of sampling and number of sampling locations may be increased or decreased as necessary for both REMP and emergency sampling. The emergency environmental monitoring program will be 7
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| Emergency Plan Implementing Procedure EP-2-061 Emergency Environmental Monitoring . Revision 1 established by either the Health Physics Coordinator / Radiological Assesement Coordinator or the Dose Assessment Coordinator / Field Team Controller.
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| 6.0 FINAL CONDITIONS Emergency condition is terminated and all samples have beaa collected.
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| l 7.0 ATTACHMENT
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| -7.1 Sample-Location Table j 7.2 Emergency Radiological Environmental Monitoring Points 7.3 Emergency Survey Points - 914 Meter Exclusion Area Boundary 7.4 Emergency Survey Points - 10 Miles -
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| 7.5 REMP Sample Location Table 7.6 _REMP Sample Locations Within 2 Miles of Waterford 3 l
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| ;7.7 REMP Sample Locations Within 10 Miles of Waterford 3 i 7.8 REMP Sample Locations Within_50 Miles of Waterford 3 l l
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| 8
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| l SAMPLE LOCATION TABLE LOCATION LOOATION MILES FRon SECTOR HUMBER DESCRIPTION PLANT DIRECTION Direct Radiation (TLD)
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| A-2 ( Eastbank ) On fence enclosure 1.1 H surrounding water tower west of Little Gypsy opposite Etienne St.
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| Access from River Road (LA 629).
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| The TLD's are located on the fence .
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| dpposite (S) tne entrance gate to .
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| the water tower.
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| B-1 ( Eastbank ) On fence enclosing the 0.0 HNE transmission tower 0.3 miles west (up-river) from Little Gypsy.
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| Access from River Road (LA 628).
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| TLD's are located at SW corner of fence. enclosure.
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| C-1 .(Eastbank-) On fence enclosing the 0.8 NE Little Gypsy Cooling Water Intake.
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| Access is from River Road (LA 62S) across from Little Gypsy Power Station entrance. TLD's are on the south side (inside) of the Cooling Water Intake fence enclosure, directly opposite the entrance gate.
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| D-2 ( Eastbank ) Located at USGS Witness 1.1 EHE Post Survey Marker approximately 0.3 miles east of Little Gypsy Power Station. Access from River Road (LA 629) near the west end of the Bonne Carre Spillway. TLD's are on the back of the Survey Marker Sign (icerted on levee). ,
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| E-1 (Westbank) Located on utility pole 0,2 E along River Road (LA 19) approxi-mately C.3 miles east of Waterford 3 plant entrance. Access from LA 18.
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| TLD's are on the third utility pole east of the construction entrance road.
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| EP-2-461 Revision 1 9 pttacnment 7.1 41 of 9)
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| LOOaTIch LOCATION MILES FROM SEO~OE HUMBER DESCRIPTION ,
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| PLANT DIRECTION F-2 ( Westbank ) Located on fence enclos- 1.1 ESE ~~
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| ure surrounding the LP&L substation on LA 3142. Access from LR 3142 approximately 0.2 miles south of LA 19. TLD's are on the southeast corner-of the fence enclosure, G-2 ( Westbank ) Located on-utility pole 1.2 SE-on east side of LA 3142 near Witec ,
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| entrance gate (Hext to Union ,
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| Carbide Star Plant Cate 3). Access
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| - from LA 3142 approximately 0.2 miles north of railroad overpass.
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| H-2 ( Westbank ) Located on fence en- 1.2 SSE closure to shell road off of LA 3142. Access from LA 3142 south of railroad overpass on east side of LA 3142. TLD's are on the south side of the gate for shell road. (Just south of' Texaco pipeline station)
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| J-2' < Westbank ) Located on northeast 1.3 S corner of fence enclosing Texaco valve station south of LA 3127.
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| Access from LA 3127, approximately 0.6 miles west of LA 3127/3142 intersection.
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| '*1 ( Westbank ) Located behind " Private 1.0 SSW Road" sign at Gate 9 entrance off of LA 3127. Access from LA'3127, approximately 1.3 miles west of LA 3127/3142 intersection. (Gate 8 is the access to the Waterford 3 '
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| switchyard station) ,
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| L-1 (Westbank) Located behind " Private 1.0 SW Road" sign at LP&L Cate 9 entrance off of LA 3127. Access from LA 3127, approximately 1.6 miles west of LA 3127/3142 intersection.
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| (Gate 9 is an access road for Waterford 3)
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| EJ-2-061 Revision i 10 4ttachment 7.1 (2 of 9)
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| LOCATION LOCATION MILE 5 .:RGt1 SECTOR HUMBER DESCRIPTION PLANT DIRECTION i
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| M-1 (Westbank) Located on south gate 0.7 WSW into ths Waterford 1 and 2 fuel oil storage tank enclosure. -
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| - Access is either thru LP&L Cate 9, I Gate 9 o#P of LA 3127, the shell access road from LA is between Waterford 3, or thru the Waterford 1 and 2 access road. ,
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| H-1 ( Westbank ) Located behind the "Ho 0.9 W Trespassing" sign on Short Street, in Killona, just north of the entrance to Killona Elementary t School.
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| P-1 ( Westbank ) Located behind "No 0.6 WNW l Trespassing" sign on Short Street, l in Killona, approximately 0.1 miles south of air sample station.
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| l Q-1 ( Westbank ) Located on fence 0.8 HW enclosing air sample station approximately 0.5 miles west of Waterford 1 and 2 on River Road (LA 18).
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| i R-1 < Westbank ) Located on fence 0.5 NHW enclosure for Waterford 1 anc 2 Cooling Water Intake Structure.
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| Access is free River Road (LA 18) opposite Waterford 1 and 2. TLD's are on the southwest corner of fence.
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| 4-5 ( Eastbank ) Located on utility 4.5 H pole just east of the Shady Hook .
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| Trailer Park on Hwy 61 in La Place.
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| TLD's are on second utility pole east of trailer park on north side of Hwy 61 (eastern end of La Place).
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| Attacnment (3 of 9)
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| EP-2-461 Revision i 11 7,1
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| - , ,y - --,--w ,. --p -- ,
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| LOCATION LOCATIGH MILES FROM GEOTGR HUMSER DESCRIPTION PLANT DIRECT:0N
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| ^-
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| B-4 ( Eastbank ) Located on utility. pole 3.S HNE just east of snell access road to i South
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| * Central Bell transmission '
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| tower on south side of Hwy 61.
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| Transmission tower is just east of I Weigh Scation at St. John's/
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| l St. Charles Parish line. TLD's
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| ; are on first utility pole east of access road. .
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| D-5 ( Eastbank ) Located on utility 4.2 EHE pole on shell access road to Big 3 Chemical Plant. Shell access road is approximately 0.1 miles west of l Hwy 61/48 intersection (at black and yellow gate). TLD's are on l utility pole 0.1 miles north on l
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| shall access road from Hw/ 61.
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| j E-5 ( Eastbank) Located on the Norco 4.2 E l Substation fence enclosure.
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| l Access from River Road (LA 40)
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| ( ' onto Wesco St. (adjacent to Horco Shell_ Chemical Plant), take Wesco l '
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| St. to the dead end. TLD's are
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| ! located on sixth fence post south-of the north substation gate.
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| F-4 < Westbank ) Located on utility pole 3.5 ESE behind blonde brick house on Aquarius St. in Hahnville. Access from River Road (LA 18) and turn onto Oak St. Follow Gak St. to .
| |
| Hickory St., turn right on Hickor's St. and follow to Aquarius St. and -
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| turn left. Blonde crick house is -
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| second house on right < west) side of Aquarius St. heading south.
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| G-4 ( Westbank ) Located on utility pole 3.2 SE northwest side of LA 3160/ railroad track intersection. Access from .
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| either LA 3127 or River Road
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| <LA 18) onto LA 3160.
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| FS-2-061 Revision 1 12 Attachment 7.1 (4 of 9)
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| | |
| LOCATION LOCATION h:LES FROM SECTCR HUMBER DESCRIPTION PL4NT DIRECTIGH H-6 (Westbank) Located on a tree.near 5.7 SSE the soutneast reflector pole for second canal bridge east of LA 3160 along.LA 3127.
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| P-6 ( Westbank ) Located on utility cole 5.5 WHW at southuest corner of LA 640/ -
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| railroad track intersection.
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| " Utility pole is just west of ,
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| LA 640 and east of radio trans-mission tower.
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| T Q-5 ( Westbank ) Located on fence post 5.0 NW surrounding (green) river marker on levee just east of Edgard.
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| Fence post is located along River Road (LA 18) across from the ,
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| Webre's house. -
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| R-6 ( Eastbank ) ~ Located on f ence 5.3 HHW enclosing LPeL Laydown Yard on LA 3223 in La Place. Access from Hwy 61 onto Elm St. (LA 3223),
| |
| take Elm St. to the northeast corner of LA 3223/ railroad inter-section. TLD's are located on the southeast corner of fence enclosure.
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| F-9 ( Eastbank ) Located on entrance S.2 ESE gate to Destrehan Substation.
| |
| Access from River Road (LA 46),
| |
| approximate 0.3 miles east of Luling-Destrehan Ferry, onto Destrehan Road (west of Bunge Corp. Grain Elevator), and proceed to substation gate.
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| C-9 (Westbank) Located on back fence S.1 SE of LP&L District Office in Luling.
| |
| Access via Ellington St. from either River Road (LA 16 ); or Second or Third St. from Paul Mallard Rd. (LA 52) to Ellington St.
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| EP-2-061 Revision 1' 13 4ttachment 7,1 ( 5 of i) l
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| | |
| MILE 5' FROM SECTOR
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| ~
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| %CCATION LOCATICH DIRECTION
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| .WMBER DESCRIPTION FLANT E-15 ( Eastbank ) Located on Kenner 11.8 E Substation fence enclosuae.
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| Access from either River Road (La 48) or Hwy 61, twin onto Alliance Ave. TLD's are located on the north side of the fence enclosure, near a -
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| light pole. ,
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| J-15 ( Westbank ) Located on fence 12.0 E enclosure surrounding LP&L switchyard at LA 631/ Hwy 90 intersection in Des Allemands.
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| TLD's arae on the northwest corner of fence. Access from LA 631 via shell road.
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| E-30 <WestbankJ Located on fence at 27.0 E LP&L General Office.on Delarende St. in Algiers. TLD's are on the fence, facing the Mississippi River, in the passageway to the transformer shop, airborne APP-1 ( Westbank ) Located in soybean 0.8 WNW field at northwest corner of Short St. in Killona.
| |
| APQ-1 ( Westbank ) Located at northwest 0.8 HW corner of soybean field on east side of Killona. Access from River Road (LA 18) approximately 0.6 eiles east of LA 18/3141 intersection.
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| APG-1 ( Westbank ) Located at the north 0.5 SE side of the Secondary Metrology Tower.
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| ET-2-061 Revision 1 14 Attachment 7.1 (6 of 9) 9
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| LOCATION LOCATION n1LES FROM SECTOR HUMBER DESCRIPTION PLANT DIRECTICH APC-1 ( Eastbank ) Located inside the 0.8 NE Little Gypsy Cooling Water Intake Structure fence enclosure.
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| APE-30 < Westbank ) Located on the roof of 27.0 E the LP&L General Office building on Delaronde St. in Algiers. .
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| . Food Products FPC-1 ( Westbank ) Located southeast of 0.6 SE the secondary Metrology Tower in soybean field.
| |
| FPP-1 <Westbank) Located in soybean 0.5 WH9 field on eastern edge of Killona, between air saeple stations APP-1 and APQ-1.
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| FPQ-1 < Westbank ) Located between LA 19 0.9 HU and soybean field on eastern edge Killona, near air saeple station APQ-1.
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| EPC-10 < Westbank ) Located along the peri- 9.5 SE seter of LP&L Monsanto Substation.
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| Incteziion M
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| ~
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| MKP-1 < Westbank ) Located at 1.0 UHW Mr. Vicknair's in Killona. House is opposite the Post Office on Post St.
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| EP.-2-461 Revision 1 15 at tachraent 7.1 (7 of 9)
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| | |
| LOCATION MILE 5 FROM SECTOR LCCATION HUMBER DESCRIPTION PLANT DIRECTICN
| |
| ~~
| |
| MKC-2 (Eastbanx) Located at .
| |
| 1.3 NE Mrs. Calcagno's, just east of of Little Gypsy, off of LA 628.
| |
| MKQ-5 ( Westbank ) Located at the Webre's 5.0 - HW house, just across LA 18 from river marker, at the castern end of Edgard. .
| |
| NKQ-50 ( Eastbank ) Located at the LSU 52 HW .
| |
| Dairy in Baton Rouge.
| |
| Fisn FH-1 Upstream of the plant intake structure, FH-2 Downstream of the plant intake structure.
| |
| Waterborne GWJ-1 ( Westbank ) Located at 40 Arpent 0.3 S Canal south of the plant. Access from LA 3127 through LPLL Cate 6.
| |
| The canal is northwest of the shall access road / railroad track intersection.
| |
| DWG-2 (Westbank ) Located at the Union 2.0 ESE SWG-2 Carbide drinking water canal.
| |
| Access from LA 3142 through Gate 28.
| |
| SHWE-3 < Westbank ) Located at the Foot 3.0 E Ferry Landing off of LA 18 in Taft.
| |
| EP-2-061 Revisioni 16 Attachment 7.1 46 of 9)
| |
| \. _ _ - - _ - _ - _ _ _ - - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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| LOCATION LO0aTION MILES FROM SECTOR-HUMBER DESCRIPTION . PLANT DIRECTIGH DWE-5 ( Eastaank ) Locatec at the 4.5 E SWE-5 St. Charles Parish Waterworks 1
| |
| off of River Road (LA 48) near New Sarpy.
| |
| DWP-7 (Westbank ) located at the A.5 HW SWP-7 St. John Parish Waterwork s of f of LA 18 in Edgard.
| |
| l i
| |
| EP-2-061 A'Vi8i*'l 17 4ttachment 7,1 (9 of 9) 1
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| ( - -
| |
| | |
| ATTACIINENT 7.2 EMERCENCY RADI0lDCICAL ENVIRONHFETAL MONITORING POINTS The f,ollowing table lists and describes the location of each of the Emergency Survey.(monitorf ng) Points. During omergencies, the appropriate survey (monitoring) points will be used to key the Field Monitoring Teams to specific locations downwind from the site. At the monitoring point, the team (s) will obtain dose rates, air samples and any additional aamples as requested by the llealth Physics Coordinator or Radiological Assessment Coordinator.
| |
| CORRESPONDING
| |
| , LOCATION 'RDIP 1ACATION DESCRIPTION DIETANCE FROM WATERFORD-3 REACTOR Shell road on west bank levee, hairway 0.2 Hiles l A-lE (N) NONE i Setween Waterford 3 intake structure and trnnemission tower A-1 (N) NONE East Bank levee approximately 0.25 miles , 1.0 Miles west of Dixieland Monts Subdivision off of Ilwy. 628 '
| |
| A-2 (H) NONE Idn Vicknair's Croce/y Store located off 1.7 Miles of Ilwy. 628 (East Bank)
| |
| ; A-3 (N) NONE Immediately north of St. John the Baptist / 2.6 Hiles i
| |
| St. Charles Parish line on East Bank off -
| |
| of Ilwy. 628 j A-4 (H) NONE Dn levee off Ilwy. 628 at sign " Laplace 3.7 Miles Hartne Service - H11e 132" on East Bank
| |
| ! A-5 (N) NONE East Bank in I.aPlace at northeast corner 4.9 Miles (triangle) of US 51 & US 61
| |
| ! (Airline liwy.) Intersection l
| |
| A-6 (N) NONE North of Laplace on US 51 at "Welcome To 5.8 Miles l La? lace" sign (also has Lions Club Emblem.
| |
| l etc.) and "Riverlands Cable" sign (signs on l
| |
| l west side of US 51)
| |
| EP-2-061 H'e vision 1 Ig Attachment 7.t2 (1 of 7) l o a a
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| | |
| COLiESPONDING 1AX:ATION REM / LOCATION DESchlFTION _
| |
| DISTANCE FROM MATERfDED-3 REACTOR B-lE (NNE) NONE Cate for Waterford 3 intake structure 0.1 Miles on leves (West Bank)
| |
| B-1 (NNE) NONE On levee of f Huy. 628 just west of 1.0 Miles Evangeline hond (East . Bank)
| |
| B-2 (NNE) NONE On Evangeline Road between US 61 and 1.9 Miles Itwy. 628 at north edge of housing development.(where street lights end) and south of tallroad tracks B-3 (NNE) NONE On Evangeline Road between two sets of 2.7 Miles railroad tracks, at gas pipeline on west side of road B-4 (NNE) NONE At weigh station on US 61 just west of St. 3.7 Miles John the Baptist Ps'rish line (Eastern
| |
| , Border) :
| |
| C-lE (NE) NOME On levee (West Bank) midway between 0.2 Miles intake and discharge structures C-1 (NE) C-1, APC-1 NE of plant at Little Gypsy Plant cooling 0.8 Miles water intake (river side of levee)
| |
| C-2 (NE) NONE On Bonnet Carre' Floodway western levee 1.8 Miles off Ilwy. 628 at large "No Dumping" sign (near gas tank on floodway side of levee)
| |
| C-4 (NE) NONE On dirt road in Bonnet Carre' Floodway 3.7 Miles which runs east to west. Access to road j on either side of US 61 bridge over ,
| |
| ; floodway
| |
| ) Il-lE (ENE) NONE Post numbered 2500 on levee (West Bank) 0.2 Milea East of Waterford 3 discharge structure
| |
| ]
| |
| I i
| |
| i EP-2-061 Revision I 10 Attachment 72 (2 of 7) i 4
| |
| | |
| CORRESPONDING 1.DCAT10N REMF LOCATION DESCRIFTieMi DISTANCE FBDH WATERFORD-3 REACTOR Recreational park at intersection of 1.0 Miles D-1 (ENE) NONE Hwy. 628 and Calcagno Road. Between Little Cyg ay Generating Station and Bonnet Carre' Floodway ,
| |
| On Hwy. 48 (across Bonnet Carre' Floodway) 1.6 Miles l U-2 (ENE) NOME at first dirt road opposite third depth marker (counting from western levee of floodway) '
| |
| NONE On Hwy. 48 (across Bonnet Carre' Floodway) 2.3 Miles D-3 (ENE) at first dirt road (from eastern levee) l in floodway On dirt road at seqth (eastern) end of US 61 3.9 Miles D-4 (ENE) NONE l
| |
| bridge over Bonnet Carre' Floodway Fost numbered 2510 on levee (Nest Bank) east 0.4 Miles E-lE (E) NONE of Waterford 3 discharge structure On levee off Hwy. 48 opposite Shell Norco Plant 2.8 Miles l E-3 (E) NOME (just east of Bonnet Carre' Floodway) where pipeline crosses levee Intersection of Good Nope Street and Nwy. 48 3.7 Miles E-4 (E) NONE .
| |
| Intersection of Hwy.' 627.(Frospect Avenue) and 4.1 Miled E-5 (E) NONE Hwy. 48 NONE Intersection of Harding F,oad and US 61 . 5.6 Miles i E-6 (G)
| |
| Cate to LFEL Substation west of Beker Industries 0.6 Miles F-lE (ESE) NOME Flant and east of Texaco Valve Station Intersection of Hwy. 18 and Nwy. 3142 1.1 Hiles F-2 (ESE) NOME Attachment 7 3 (3 of 7)
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| SP-2-061 Revision 1 20
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| | |
| . 4 CORRESPONDtNC I.0 CATION RElf LOCATiM DESCAIPTION DISTANCE FROM WATERFORD-3 REACTOR F-4 (ESE) NONE Post Of fice parking lot in Haluiville off 3.9 Miles liwy. 18 ,
| |
| F-5 (ESE) NONE Holy Rosary Church parking lot of f Ilwy.18 4.3 Miles (just west of St. Charles Farish Courthouse)
| |
| F-6 (ESE) NONE Inters ction of Ormond Estates Blvd. and 5.6 Miles Ilwy. 48 (East Bank) - Heat Jr. Food Mart F-7 (ESE) NONE On levee (East Bank) where Hwy. 48 Intersecta 6.8 Miles Destrehan - Luling Bridge F-9 (ESE) NOME on levee (East Bank) off Hwy. 48 across from 8.5 Miles Bunge Corporation Crain Elevator C-lE (SE) NOME Midway between prispry and secondary 0.6 Miles meteorological towers, approximately
| |
| * 200 yards east of secondary met. tower (In field - may be herd to reach during wet field conditions)
| |
| C-2 (SE) C-2 SE of plant on IA 3142 (0.6 miles south of 1.2 Miles intersection with LA 18 at Witco Employees lot entrance)
| |
| C-4 (SE) C-4 SE of plant near intersection of IA 3160 and 3.2 Miles [
| |
| Hissouri Pacific Railroad (located at utility i pole at NW side of intersection)
| |
| C-8 (SE) NONE First Pentacostal Church on west side of 7.8 Miles Hwy. 52 between Hwy. 18 and Boutte northern t town limits C-9 (SE) NONE Field behind brick wall to Coronado park 8.6 Miles t of f US 90 between Wes.t Store an.1 entrance to Monsanto Chemical Plant C-10 (SE) NOME St. Charles Parish library parking lot. 9.4 Miles Intersection of US 90 and Barton Avenue EP-2-061 Revision 1 21 AttacInnent 7.2 (4 of 1)
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| | |
| CORRESPONDING DESCR1FT10N DISTANCE FROM WATERFORD-3 REACTOR IAM:AT10N REMF LOCATION Primary meteorological tower gate, use 0.4 Miles ll-lE (SSE) NONE service road to concrete facility Intersection of Hwy. 3127 and Dwy. 3142 1.8 Miles
| |
| .11-2 (SSE) NONE St. Charles Parish Boat 1.aunch at bridge 7.9 Miles l 11-8 (SSE) NONE on Hwy. 631 (access from Hwy. 3127) south of Hwy. 3127
| |
| * i Cate to concrete facility south of plant 0.4 Miles l J-lE (S) NONE using concrete facility servica road On Hwy. 3127 0.5 miles west from intersection 1.4 Miles J-2 (S) NOME of Hwy. 3127 and Hwy. 3142 (no landmarks to reference)
| |
| Northwest of 230 kV switchy'ard south of 0.6 Miles K-1E (SSW) NONE
| |
| * Waterford 3 :
| |
| ! On Huy. 3127 1.0 alles west from inter- 1.1 Miles
| |
| ! K-2 (SSW) NOME section of Hwy. 3127 and Hwy. 3142, opposite 4 culverts in drainage ditch 0.5 Miles I,-lE (SW) NOME Just south of railroad tracks on service
| |
| ' road located west of Waterford 3 (which runs past firing range).
| |
| on Hwy. 3127 1.5 miles west from inter- 1.1 Miles I.-2 (SW) NONE section of Hwy. 3127 and Hwy. 3142. near transmission tower ,
| |
| WSW of plant near Waterford I & 2 0.7 Miles H-lE (WSW) M-1 fuel oil storage tanks (in NE corner of .
| |
| tank area)
| |
| Attachment 7.2 (5 of 7)
| |
| EP-2-061 Revision g 22.
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| | |
| CORRESPONDING IJX'ATION REHF IDCATION DESCRIPTION ,
| |
| DISTANCE FRON WATERFORD-3 REACTOR Il-2 (WSW) NONE On they. 3127 2 elles west from Jnter- 1.2 Miles j section of they. 3127 and thay. 3142,
| |
| * opposite ditch with'4 culverts II-lE (W) NONE Waterford 1 & 2 road, north at railroad and 0.6 Miles
| |
| ! close to Waterfcrd I & 2 fuel oil day tank (SW corner of tank area)
| |
| Il-2 (W) N-1 W of plant at east end of K111ona Elementary 0.9 Miles (east of ditch, behind LF&L no trespassing sign)
| |
| P-lC (WNW) NONE Service road on Waterford I & 2 Complex 0.5 Miles 1
| |
| - at fifth* pipe rise in fuel transfer piping
| |
| (* counting from north gate headed south) l l'-l (WNW) NONE Northeast corner of flhort Street. Take Post 0.8 Miles Street (in Killona) to Short Street (first
| |
| . left), to right turn,.on Short Street P-2 (WNW) NONE Ihiy. 3142 between thay.18 and thry. 3127, at 1.1 Miles baseball fields, between backstops P-6 (WNW) NONE IIwy. 640 hetween thay.18 and they. 3127 at 5.8 Miles dirt road heading east (at point of tree line) 1 P-9 (WNW) NONE On levee (East Bank) of f thry. 44 near 5.8 Miles Garyville, across from Shell Station.
| |
| Use levee access rced with gate holding I
| |
| "F & S" sign
| |
| ; ()-lE (HW) NONE Main gate entrance to Waterford 1 & 2 0.5 Miles l
| |
| Complex of f thay. I8 i
| |
| j ()-2 (NW) NONE On levee (West Bank) at intersection of 1.1 Miles i
| |
| lhay.18 and Ihry. 3142 (Killona)
| |
| )
| |
| 4 EP-2-061 Revision 1 23 Attachment 7.2 (6 of 7) i
| |
| | |
| ! CORRESPONDING LOCATION RDIF LOCATION DESCRIFTION DISTANCE FROM WATERFORD-3 REAt7t0E
| |
| \
| |
| Q-3 (NW) NONE On levee (West Bank) at levee sign 2380. 2.3 Miles l
| |
| off Ilwy. 18 at sina11 village between K111ona and I,ucy n
| |
| Q-5 (IIW) NONE Intersection of Ilwy.18 and Cold Mine 4.8 Miles Plantation Road (entrance to plantation),
| |
| on south side of Ilwy. 18 between Lucy and
| |
| 'Edgard Q-6 (NW) NOME Intersection of Ilwy. 44 and 12th Street in Reserve 5.7 Miles R-lE (NNW) R-1 NNW of plant near Waterford I & 2 intake dock 0.5 Miles R-4 (NNW) NONE Ictersection of Nwy. 18 and 16th Street. 3.4 Miles at south eastern end of I.ucy e
| |
| R-5 (NNW) NOME I)n levee (East Bank) of f Ilwy. 636 In I,aPlace.
| |
| 4.8 Miles
| |
| ' opposite two story house bordered by rocks with fire hydrant on corner 4
| |
| I l
| |
| l l
| |
| l EP-2-061 Revision 1 24
| |
| | |
| A Lavus Arm oximat:
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| * usesween sunTenTAme Q l000 2000 240SSTA?!05 FEET EMERGENCY SURVEY POINTS 914 METER EXCLUSION AREA BOUNDARY (EMERGENCY PLANNING SITE BOUNDARY 1 EP-2 061 Revision 1 25 Attach =ent 7 3-(1 of 1)
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| |
| W " F2cM temmr PLANT DI2ECTION a_
| |
| r- LOCATION DiresE tadistics
| |
| .1 E of plant an east beak of h4--d==4 pi I A-.1 -
| |
| . Eiver at base of water tseer (0.8 mi upsiver om Eiver land from Littia Gypsy - ''
| |
| Flaat amaramas)
| |
| NEE of plaat om east baalt of *==4==4ppi 0.8 INE 3-1 -
| |
| liver insida -*v fassa -._. - Ad7 trammaias;Las tsour (0.3 mi upriver on .
| |
| River Band from Little Gypsy Plant entrance).
| |
| EE of plant at Littla Gypsy plant cooling 0.8 II2 C-1
| |
| - water intaka (river side of laves)
| |
| EEE D-2 ZIE of plant of east bank of Mississippi liver. 1.1 at. west and of Bonna Carra Spillway (located as river laves and west guida laves of ==d"M at USGE wimmons post.for survey asskar) 3-1 E' of plant as west beak of wi==4==4ppi River 0.1 E (0.3 mL demariver om 418 from Waterised 3 Adminiertasian 31ds. ,3rd naility pela past Ebasse coastzussian astramme) y-1 EXE of plans in 23tTat substation for Bookar 1.1 ESE C"wmisal (.,,.-- h aly 0.1 at from u 18 an u 3142) r. .
| |
| G-1 SE of plant on u 3142 (0.6 mi south of 1.2 SE inii:sssentiam iith M 18 at
| |
| * Witmo Employees 1st entzumes) .
| |
| E=2 SSE of plaar., south and of M 3142 railroad 1.1 382
| |
| - overpass inside LFEL assess road to Unism
| |
| - Carbida substation (1.1 mL $ of M 18 & M 3142 internestian-enderneath 138 & 113 K7 tr====*==4a=
| |
| lines) .
| |
| 5 of plant on south side of M 3127 amar Tazase 1.3 S J-2 valve station. (0.7 mi W of M 3142 & u 3127 intarsection) .
| |
| ?
| |
| \
| |
| EP-2-061 Revision 1 27 Accachamat 7. 5 (1 of 4) e
| |
| | |
| /
| |
| . nrve SMJ LCCr'IC5 n2L2 MILES TRCE i
| |
| m- -QR
| |
| * FLANT DI2ECTIttf_
| |
| --... --- LaeiPION i .
| |
| E-1 SSW si plant near atrines fa ma to Waterford. 1.0 SSW suitakyard station (1.4 mL W of n 3142 & M 3127 intersestism) . __
| |
| SW of plant inside fanaa that irrattises ---h- t 1.0 SW L-1 abell ==*=== road (1.7 mi W of n 3142'A u 3127 ,
| |
| < - - : ws
| |
| * M-1 . W55 af plant near Waterford 1 & 1 fuel oil 0.7 -
| |
| W5W storage tanks (in IE sorsar of tank area) , ,
| |
| 3-1 W of plans at east and of Eillona ut - tary 0.9 -
| |
| W.
| |
| (east of ditsk. behind L74L no i ;---d-- sign)
| |
| ~
| |
| p-1 .
| |
| WNW of plant naar L78L no trespassing,sigm 0.3 UNE
| |
| ( 0.3 mL 3 af E11h E1ammutary) ,
| |
| NE of plant beesent asybeam field and. LL 18 0.8 -
| |
| NR
| |
| ' Q-1 (0.6 mL E of LL 18.4 3141 4-*----- r h )
| |
| E-1 E55 of plans aner Wa;wford 14. I intake deslL 0.5 ,
| |
| NNW '
| |
| N of plant naar Shady Book Trailer park on US 4.5 N A-5 61 (0.6 at E of US 31 & 61 intersectisa) -
| |
| f ENE of plant near u D'OT weight statism on 3. 8' 33E
| |
| , 3-4 l ,
| |
| US 61 (1.0 mL W of Bommet Carra spillusy)
| |
| D-5 INE of.plaat inside Claytonia , substation . 4.2 III due grounds E ofon7;UE ames 61 )Carre S;411==y naar camp-E-5 I of plant 1asida Berno South substation 4.2 I ISE of plant in Bahavilla (A11amma's yard) 3.5 ISE i- '7-4 G-4 SE of plant near intarsessi m of M 3160 3.2 SE and Missouri pasifia 3ailroad (located at l
| |
| ! utility pela at NW side of intersection) 3-6 SSE of plant on u 3127 at Byzaal Canal 5.7 SSE (approzinstaly 2.1 mi E.of u 3160) 7-4 WNW of plant W of.u 640 at 31 intar=ection 5.5 . f.9W near utility pela at radiatower Attachment 7. 5 (2 of 4)
| |
| EP-2-051 Revision 1 28 I
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| . - - - - . _ - , . . _ _ _ _ _ _ _ _ _ _ . - _ . - _ ~ _ - _ _ . _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . - - _ - - . - - - - -- - - - - -
| |
| | |
| RWP SAM 1".I LOC 1 TIC 7; TX3LZ symme us t m ICCATION ?!.ufT DI3ECTICN r-r-W of plant in Edgard across from ah - 1 5 *. 0 .
| |
| W 0-5 marker Ofebrs's yard) i m as plant near LaFlaas in L7E laydosa 5.3 358 3-4 yard E-15 E of plant at LFE Eenaar substation 11.8 E
| |
| ; F.9 ISE of plant at Destraban substation near 8.2 ESE
| |
| . grain alavator 8.1 SE
| |
| . G-9 SE of plant at t=H- District offica s of plant at Den A11.amade switahyard 12.0 s
| |
| J-u 27.0 E E-30 E of plant at d E Gameral Officas Ti .
| |
| . M .
| |
| 0.8 -
| |
| ICnr AFF-1 1rW of plant in soybeam field off of~ Short St.
| |
| i .
| |
| in- E111 ass.-
| |
| NE of plane between seybeam fih14 and IA 11 0.8 W
| |
| , A2tt=1 l (0.6 mL E of M 15 4. M 3141 interse=)
| |
| A3th-L SE of ytant nest to sat tever 0.5 5E ~
| |
| l f APC-1 NE of plant at Lit:1a Gypsy plant cooling 'O.8 NE
| |
| : l. water intaka strustare.,
| |
| AF5-30 I of plant at LFE General CEfissa - 27.0 I l Food Prodnats FFP-1 W of plant at soybean field 3 of u 18 0.6 m*
| |
| FPQ-1 W of plant between soybeam fiald and u 18 0.8 W (0.6 mi E of M 18 & M 3141 intersection) 77G-1 SE of plant nazz to see tower 0.6 . sr FFF-10 E5E of pJant off River Road, naar Luling 9.5 ESE' city limits EP-2-061 Revision-1 29 Attr. .hment 7.5. (3 of 4)
| |
| -n-- - , - - . , , , , , , - , . , - . - - . _ _ _ , -
| |
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| | |
| i l
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| L. . IL".fP SAF Z LCCA!!CN T.13L2 I
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| ~
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| MT??t 73CM gg -- - 7LANT D UICTICN g _- ?SWIc5 .
| |
| Jasassism . .
| |
| 15 3
| |
| .NW side of Post St. E111ona, Mr. Yickmair's. 1.D 1ENT l NEP-L 1.3 NE MEC-2 NE of plant, north of Monts Park at -
| |
| Mrs. Calpagne's .
| |
| : 5. 0 , NU MEQ-5 MW of plant in Edgard across from channel ,
| |
| marker Ofebre's yard) . .
| |
| i 52. NW MEQ-50 NW of plant at LSU Dairy in Baton Rouge l _ ,
| |
| .58ER. .
| |
| t FR-L U; -
| |
| fase plarte insaka struseura FE=1 Domestresar fraurplant disab7.rge-strussure
| |
| ~
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| GW-1 5 of plant at 40 Arpent Canal d.3 , S 555-3 E of plant in Taft at the Foot Ferry '3.0 ,
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| E 2-a.g .
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| EW of plant as th St. Jeha Parish Water- 6.5 NW 55-1
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| ~
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| 55-1 6
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| 'ASE of plans at the Union Carbide Mnking 2.0 ESE IN-1 55-2 wazar insaka -
| |
| I of pin t at the St. Charles Pariah 4.3 * .E l DW-5 SW unservorks .
| |
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| EP-2-061 Revision 1 30 Aze=eh===t 7. 5 (4 of 4)
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| i :[ u==^=* REMP SAMPLE LOCATIONS R
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| "E *,4E" WITHIN :10 MILES OF.WATERFORD 3 . -
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| ; ,EP-2-061 Revision 1 33 t*C nt 7 8 e
| |
| 4
| |
| ,....--------..,,,.,y -
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| : r. .-. m,, _ , , - - - - - _ . - - - - - - - - , , - - - - - -
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| | |
| i Ep' '' ''.-:. ; QCCUMENT REVIEW COM MENTS
| |
| ' l CCCUMENT NC. REv./ CRAFT !
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| /c As,W
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| !. Revi,ewed Sy; 2. Comments Resolved ay:
| |
| t '&J *n( /=] ) 1- f3 Reviewer /
| |
| [l Ost's Author =cre
| |
| : 3. Reseaution of co mments Act.asted !y
| |
| 'emww : ara
| |
| ? 1069 al 00 SU
| |
| | |
| 7 o
| |
| WATERFORD 3 5" dS
| |
| = 3s - PLANT OPERATING MANDAL LOUISIANA POWER & LIGHT
| |
| $N POM VOLUME 18 EP-2-071 POK SECTION 2
| |
| ~
| |
| REVISION 4 Emergency Plan Implementing Procedures Site Protective Measures LP&L W-3 RECORDS UNCONTROLLED COPY l DO NOT USE IN ANY SAFETY-RELATED TEOT:NG, MAINTENANCE, OR OPERATIONAL ACTIVITY PORC Meeting No. 83-52A haviewed: hd2[f-%
| |
| PORC Chairman Approved: 'l W Plant Manager-Nuclear Approval Date Fuel Lead Effective Date i
| |
| 1
| |
| | |
| ~
| |
| WATERFORD 3 SES PLANT OP!3ATING MANUAL CHANGE /RE7I3 ION / DELETION REQUE3T Precedure No. M '
| |
| -C I Title 4,7- < 's - '/ h - "'
| |
| Effective Data M '~~ (if different from approval date) t' anni s ta 1. R. er d A. Change No. */A
| |
| : 5. Revision No. M M '
| |
| C. Deletion M/A ernes ran enawar. arvtMTan_ on furtrTTom -
| |
| T.: 5.1:% L1., s .%2% u--v.wiL REQUIRED SIGNATiggg . , ,
| |
| '2b'ih Originator /)" N Date l
| |
| Tcchnical Review 'NA Data l
| |
| SAFETT ETALUATION Does this change, revision, or deletion: TES NO
| |
| : 1. Change the .faeility as described in the FSAR7 _ <d
| |
| : 2. Change the procedures as described in the FSAR7- , d
| |
| : 3. Conduet testa /experimenta not described in the F3AR7 f j 4._ Create a conditica or conduct an operation which ex- #
| |
| l oeeds, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yea, complete and at-l tach a 10 CFR 50.59 3 y Evaluation checklist.
| |
| i Satcty Evaluation MMM Da te _ /7 93 M[MM Group /Dep't. Head Rev1ew Da to 7S/2783 Temporary Approvale Date (NO3) '
| |
| Temporary Approvale Date i
| |
| QC Review AA ut!' A- Date /- 6. re FORC Review M [ @ - ,
| |
| Date /IW Meeting No.
| |
| Plant Manager-Nuclear Approval Date -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days,
| |
| 'UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
| |
| ZG
| |
| | |
| Emergency Plan Implementing Procedure EP-2-071 Site Protective Measures .' Revision 4 !
| |
| TABLE OF CONTENTS 1.0 PURPOSE 2.0- REFERENCES 3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS ,
| |
| 5.0 PROCEDURE 6.0 FINAL CONDITIONS
| |
| ^* 7.0 ATTACHMENTS 7.1 On-Site Evacuation Routes (1 page) l 7.2 Assembly Area Muster Sheet (1 page) 7.3 Site Evacuation Route (1 page) 7.4 Assembly Area Supervisor Actions and Checklist (1 page) -
| |
| LIST OF EFFECTIVE PAGES Title Revision 4 1-5 Revision 4 6-8 Revision 3 LIST _OF PAGES CONTAINING l PROPRIETARY INFORMATION 8
| |
| l I
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| 1 ,
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| | |
| p Emergency Plan Implemencing Procedure E?-2-071 Site Protective Measures -
| |
| Revision 4 l 1.0 PURPOSE This procedure prcvides a method with which the Emergency Coordinator can ensure that appropriate site protective measures are taken.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 Waterford 3 SES Emergency Plan 2.2 EP-1-020, Alert ;
| |
| 2.3 EP-1-030, Site Area Emergency 2.4 EP-1-040, General Emergency 2.5 PS-16-103, Accountability of Personnel During Emergencies 2.6 EP-2-190, Personnel Accountability 2.7 EP-2-032, Monitoring and Decontamination 3.0 RESPONSIBILITIES The Emergency Coordinator is responsible for implementing this procedure.
| |
| 4.0 INITIATING CONDIT ONS -
| |
| 4.1 Declaration of an Alert 4.2 Declaration of a Site Area Emergency 4.3 Declaration of a General Emergency 4.4 As directed by the Emergency Coordinator 5.0 PROCEDURE 5.1 Site protective measures consist of immediate evacuation of the site.
| |
| 2
| |
| : i. .__ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ . _ _ _
| |
| | |
| , - .- - - .. __- . . . _ = . - . .
| |
| l Emergency Plan Implementing Procedure' EP-2-071 Site Protective Measures .' Revision 4 l 5.2 SITE EVACUATION 5.2.1 Select the.off-site assembly _ area to be used (Monsanto Park,
| |
| ; Luling or St. John the Baptist Catholic Church, Edgard).
| |
| 5.2.2 Notify the Security Shift Supersisor to prepare for the evacuation of the site.
| |
| 5.2.3 Dispatch the off-site Assembly Area Supervisor. .
| |
| 5.2.4 Ensure that a Health Physics technician is dispatched to the off-site assembly area.
| |
| ** 5.2.5 Sound the station alare and make the following announcement (see note below):
| |
| " Attention all personnel; attention all parsonnel: A site evacuation has been implemented. All personnel not assigned to ,
| |
| the emergency response organization proceed immediately to (state-one of the locations). Upon arrival, log in with the Assembly A~rea Supervisor. Personnel in radiation controlled i areas proceed to the Health Physics Control Point. There will be no smoking, eating or drinking until further notice. The maintenance radio frequency is now dedicated for emergency use I 'only."
| |
| NOTE For Site Area and General Emergencies, this t
| |
| l announcement may have been made previously L (when emergency was declared) in accordance j with EP-1-030 or EP-1-040.
| |
| i i
| |
| l 3 l'
| |
| | |
| Emergency Plan Implementing Procedure EP-2-071 Site Protective Measures ,- Revision 4 l 5.2.6 Repeat the announcement.
| |
| 5.2.7 Ensure accountability in accordance with EP-2-190 and PS-16-103.
| |
| 6.0 FINAL CONDITIONS This procedure shall be considered complete when muster has been completed and results forwarded to the Emergency Coordinator and the Emergency Coordinator disbands the mustered personnel.
| |
| 7.0 ATTACHEENTS ,
| |
| 7.1 Onsite Evacuation Routes ,
| |
| 7.2 Assembly Area Muster Sheet 7.3 Site Evacuation Route -
| |
| 7.4 Assembly Area Supervisor Actions and Checklist l
| |
| l
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| -.- . - -. . . . _._- . - = .
| |
| ASSEMBLY AREA MUSTER SHEET Assembly Area Name of Individual Completing 4
| |
| Supervisor's Name: Must.er Sheet:
| |
| Location:
| |
| Date: Time:
| |
| Print the names.of personnel that have assembled. Pres'ent completed form (s)_
| |
| immediately to LP&L Assembly Area Supe nisor.
| |
| 1 i
| |
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| .EP-2-071 . Revision 3 6 Attachment 7.2 (1 of 1) l r . . - - - - - - - - , - , - - - . - - - . . . - - - - . . . - - - , , - , , - - - . , - . . , , - . , - . - . . - - . -
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| \ssOmbly Areas ;1l - 8' . -Mit uk O MONSANTO' PARK .,.
| |
| I '
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| loulle .
| |
| 1
| |
| @ ST. JOllN Tile HAPTIST .- .
| |
| PARISil CATilOLIC C1100C11 .
| |
| j ) I aradle .
| |
| ilTE EVACUATION ROUTE EP-2-071 17av talon 3 Y=g,3 ,
| |
| /'
| |
| __ .f . ,__ _ ___
| |
| At t neliniesit 7,1 (ty[y ;
| |
| i 7
| |
| | |
| . - - - _ - _ - = _. - _ - = - - _.
| |
| ASSEMBLY AREA SUPERVISOR ACTIONS AND CHECKLIST
| |
| : 1. Procure. Assembly Area Kit and verify operation of communications ,
| |
| equipment.
| |
| : 2. Proceed to the proper assembly area.
| |
| : 3. Upon arrival at the assembly area:
| |
| : a. Establish communcations with the OSC.
| |
| NOTE .
| |
| If communications cannot be established with the portable radio, relay messages by dispatching an individual to the nearest coin-operated telephone. The PABX number for the OSC Supervisor is a
| |
| : b. E6sure that all personnel are logged in on the Assembly Area 9
| |
| Muster Sheet (Attachment 7.2). Assign individuals to assist with this task, as'necessary.
| |
| : c. Ensure that Health Physics technicians (or trained personnel selected by the Health Physics Coordinator)~are assigned to survey all personnel, vehicles and equipment for contamination.
| |
| i.
| |
| ~
| |
| Report any. requirements for decontamination to the OSC Supervisor.
| |
| : d. Coordinat?. the operations of personnel and vehicles at the assembly area.
| |
| l' l
| |
| THE MATERIAL CONTAINED WITHIN THE SYMBOLS [ ] IS PROPRIETARY OR PRIVATE
| |
| ! INFORMATION.
| |
| ~
| |
| L l
| |
| EP-2-071 Revision 3 8 Attachment 7.4 ( 1 of 1) i I
| |
| w w9- M y-p.- + * = = ' * *WW 'em-g'u'-- t"~"* *~4" ' " "-**vw -':- * * - =v-'' 'e*T S Wr-"'T""W
| |
| | |
| WATERFORD 3 SES
| |
| ;;.M, L PLANT OPERATING MANDAL
| |
| +
| |
| " $ LCUIS1AMA am POWE A & LIGHT NEAM!AG POM VOLUME ig EP-2-081 ,
| |
| ?OM SECTION 2 REVISION 3 Emergency Plan Implementing ~ Procedures Search and Rescue LP&L W-3 RECORDS UN! CONTROLLED COPY CO NO r USE IM ANY SAFETY-RF. LATED TESTING, MAlihudANCE, Oa OPERATIONAL ACTIVITY PORC Meeting No. 83-52 Reviewed: 2((#-
| |
| PORC Chairman Approved: L & II I Plant Manager-Nuclear Approval Date fuel Load Effective Date
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| - - _=_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __________J
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| | |
| / < .
| |
| '4ATERFORD 3 313 ,
| |
| PLMT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Precedure No. @- 2 w.T Title L' n " ' - >-h-Effective Date 2 3 '- ~ (if different from approval date)
| |
| % et.e. 1. n a, e A. " Change Eo. ^YA
| |
| : 3. Revision No. 7 -
| |
| -C. Deletion NAI REASDM FOR CHANCE. RETISION. OR DELETIDM -
| |
| - l, nn .s m cio/0 REQUIRED SIGNATURES Griginator I ~~~ 0"E W -
| |
| Date '? **' '
| |
| Tcohnical Review AO Date SAFETT ETALUATION Does this change, revision, or deletion: TES. NO
| |
| : 1. Change the facility as described in the FSAR7 ''''
| |
| : 2. Change the procedures as described in the FSART- V
| |
| : 3. Conduct tests / experiments not described in the FSAR7 <'
| |
| 4 Create a conditica or conduct an operation which ex- '
| |
| coeds, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 set y Eva'uat on checklist.
| |
| Safety Evaluation ^/ '
| |
| a d Date / 7 O 4 Group /Dep't. Head Review M e z2d _ Date '
| |
| 2/?*/D Temporary Approval
| |
| * Date (NO3)
| |
| Temporary Approvale Date 1, QC Review /4 N8de- Date /-6 #"
| |
| PORC Review [ N 82 b w Date /--6 W Y Meetin5 No.
| |
| Plant Manager-Nuclear-Approval Date -
| |
| ' Temporary approval aunt be followed by Plant Manager-Nuclear approval
| |
| .within 14 days.
| |
| UNT-1-003 Revieton 6' Attachment 6.9 (1 of 1)
| |
| : 2. G
| |
| | |
| r m
| |
| +a
| |
| - Emergency Plan _ Implementing Procedure EP-2-081 Search and Rescue ,
| |
| Revision 3 TABLE OF CONTENTS p.
| |
| 1.0' PUR, POSE-
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 3.0 RESPONSIBILITIES-
| |
| ' 4.0- INITIATING CONDITIONS
| |
| -5.0. PROCEDURE 5.1 OSC . g rvisor Actions
| |
| .5.2
| |
| =
| |
| Search and Rescue Team Leader Emergency Actions 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS LIST OF EFFECTIVE PAGES E
| |
| Resision 3 Title' 1-6 Revision 3 L
| |
| h 1
| |
| @5 + y- --- <- er - e e-.e-,=iw a +ve -
| |
| +wo-+--yw--ww--- -
| |
| -r ='m-'-''T y-- - ---" --e wwy
| |
| | |
| Emergency Plan Implementing Procedure EP-2-OS; Search and Rescue ,
| |
| Revision 3 1.0 PURPOSE To provide guidance to the Operational Support Center Supervisor and Search:and Rescue Team Leaders for the search and rescue of personnel who may. be missing, trapped, or injured.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 EP-2-031, In-Plant Radiological Controls and Surveys During Emergencies
| |
| ~
| |
| 2.2 EP-2-020. Contaminated Injured /Ill Personnel 2.3 EP-2-150, Emergency Plan Implementing Records 2.4 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation 2.5 EP-2-032, Monitoring and-Decontamination 2.6- EP-2-190, Personnel Accountability 2.7 EP-2-030, Emergency Radiation Exposure Guidelines and Controls 2.8' EP-2-130, Emergency Team Assignments 2.9 _UNT-7-018, First Aid and Medical Care
| |
| ]
| |
| 3.0 RESPONSIBILITIES The Operational Support Center (OSC) Supervisor and the Search and Rescue Team Leader are responsible for implementing the appropriate steps-of this procedure.
| |
| g%
| |
| o e
| |
| 2
| |
| _ _ ___________-.______ _______ __--____ _ _ _ _ _ _ b
| |
| | |
| r-. .
| |
| s Emergency Plan Implementing Procedure EP-2-08' Search and Rescue Revision 3 NOTE Search and Rescue-Team (s) should consist of at least two individuals from Operations, Maintenance, Health Physics, Chemistry and/or Security.
| |
| i
| |
| ~
| |
| - 4.0 INITIATING CONDITIONS
| |
| - 4.1 - This procedure shall be implemented when:
| |
| 4.1.1 Personnel have not been accounted for in accordance with l EP-2-190, Personnel Accountability, for accountability during a Site Area or General Emergency and cannot
| |
| ~
| |
| be contacted.
| |
| 4.1.2 Personnel are unable to exit an area without assistance.
| |
| 4.1.3 .As directed by the Emergency Coordinator or OSC Supervisor. l 5.0 PROCEDURE. .
| |
| 5.1 OSC SUPERVISOR ACTIONS 5.1.1 Select two individuals at a minimum. Assign one individual as l team leader.
| |
| 5.1.2 . Ensure the team is briefed in accordance with EP-2-130, Attachment 7.3. Ensure that the team is briefed on radiological
| |
| ~
| |
| hazards in'eccordance with EP-2-031, In-Plant Radiological Controls and Surveys During Emergencies. Ensure that dose limits specified in 10CFR20 are not exceeded without the Emergency Coordinator's permission, in accordance with EP-2-030.
| |
| 5.1.3~ Maintain continuous personnel accountability in accordance with EP-2-190,, Personnel Accountability.
| |
| 3
| |
| | |
| t Emergency Plan Implementing Procedure EP-2-081 Search and Rescue Revision 3 5.1.4 Notify the Emergency Coordinator when the team has been dispatched.
| |
| 5.1.5' If. persons are. injured and contaminated and offsite medical assistance is requested, refer to EP-2-020, Contaminated Injured /Ill Personnel. If injured personnel are not contaminated refer to UNT-7-018.
| |
| 4 5.1.6 Provide assistance to team as necessary.
| |
| ~
| |
| 5.1.7 After the search and rescue operation is complete, ensure team members are debriefed in accordance with EP-2-130, Attachment 7.3.
| |
| I*nform the TSC of the results of search and rescue operations.
| |
| 5.2 SEARCH AND RESCUE TEAM LEADER EMERGENCY ACTIONS
| |
| :5.2.1 Designate a team member as communicator and to obtain a portable radio.
| |
| 5.2.2 Direct a team member to obtain any cafety equipment that may be -
| |
| required.
| |
| 5.2.3 Ensure that all equipment' to be used.by the team is functional. j Perform a radio check between the Search and Rescue Team and the OSC Communicator.
| |
| 5.2.4 Ensure dose rate meters are turned on before the team leaves the OSC.
| |
| 5.2.5 Conduct search and rescue operations.
| |
| 5,2.5.1 Proceed to the designated search area with the radiation survey meter turned on.
| |
| 5.2.5.2 Ensure that communications are maintained with the Operational Support Center at predetermined intervals.
| |
| 5.2.5.3 Ensure that the Operational Support Center is kept informed of l team's location, observations, and search results.
| |
| 4
| |
| | |
| Emergency Plan Implementing Procedure EP-2-081 Search and Rescue ,
| |
| Revision 3 5.2.5.4 'If the search and rescue is to be conducted within a Radiation' l Controlled Area or other radiological hazard area, the following should be considered:
| |
| A. The need to assign an HP Technician to the team.
| |
| B. That radiation levels are monitored and that any unanticipated radiation levels are reported to the Operations Support Center Supervisor and Radiological Controls Coordinator.
| |
| C. That team members check dosimeters regularly.
| |
| D. That stay times established by the Radiological Controls Coordinator are not exceeded.
| |
| .a.2.5.5 When the missing individual is located, determine if additional j assistance, First Aid or Health Physics, is required. l 5.2.5.6. Report the following findings to the Operational Support Center as soon as possible:
| |
| 'A. Location where the missing individual was found B. Extent of injuries, if applicable l C. Contamination levels, if applicable D. Radiation levels, if applicable S. First aid administered, if applicable 5.2.5.7 Request assistance from the Operational Support Center Supervisor for transport of any injured or contaminated individuals, if required. l 5.~ 2. 5. 8 Upon completion of search and rescue operations, report to the Operational Support Center for debriefing.
| |
| 5.2.6 After search and rescue is complete, debrief the Search and Rescue Team in accordance with EP-2-130, Attachment 7.3.
| |
| 5
| |
| | |
| b Emergency Plan-Implementing Procedure EP-2-081
| |
| . Search and Rescue , Revision 3 5
| |
| . 2.7 AfterLdebriefing, collect all logs and records pertaining to the search'and rescue operations. The OSC Supervisor shall direct-that they be controlled in accordance with EP-2-150, Emergency Plan' Implementing Records.
| |
| 5.2.8 .The OSC Supervisor shall direct the OSC Communicator to inform
| |
| ,the TSC of.the results of'the search and rescue task.
| |
| 6.0. FINAL CONDITIONS 6.1' Missing individual (s) located and removed from hazardous area.
| |
| - 6.2- Secured when directed by the Emergency Coordinator.
| |
| 7.0 ATTACHMENTS ~
| |
| r:
| |
| i E
| |
| i NS40060 6
| |
| e w . -- - . - y r, - , - , . v,.-.y-, y.,,,--.,.~.,_,,,4- , - .-.___,,,_m.-_.,7.. ,.. ,
| |
| | |
| 'NATERFORD 3 SES PLANT OPERATING MANDAL
| |
| # LOUISIANA POWER & LIGHT MM ~
| |
| l EP-2-090 id# A POM VOLUME 18 REVISION E2 j/ ,
| |
| POM SECTION 2 APPROVAL DATE:
| |
| EFFECTIVE DATE: Fuel Loatl EMERGENCY PLAN DIPLDIEliTING PROCEDURE CORE DAMAGE ASSESSMENT l
| |
| I LP&L W-3 RECORDS s
| |
| p,m uo pm/
| |
| l U N C O NTRO.L: U.-2o DO NOT U'if IN ANY SAFEU-pa.adE0 TEWG, l
| |
| MAINTENANCE, OR OPERATIONAL ACTIVITY PORC Meeting No. ?3 37 Reviewed,* [/dd n eds PORC App roved: r [ J l
| |
| ''=cw 7 igyc Nucleari i
| |
| l
| |
| | |
| r WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 6 P 2 - 09 Title O~e lhw-ks (1%h Y Effective Date E-A 6A (if different from approval date) cannista 1. B. er C A. Change No. I --
| |
| B. Revision No. _ 2 ---
| |
| C. Deletion A/A WFAMDM FOR CH AMC E. REVISION. OR DELETION
| |
| 'Tn e_,m dt m A ._ dm % eL w as 4bM -
| |
| REQUIRED SICNATURES Originator O Cd Date / / [d' Tcchnical Review N/A % Date DAFETT EVALUATION D:es this change, revision, or deletion: TES NO
| |
| : 1. Change the facility as described in the FSAR7 V
| |
| : 2. Change the procedures as described in the FSAR7- E
| |
| : 3. Conduct tests / experiments not described in the FSAR7 #
| |
| : 4. Create a condition or conduct e:; operation which ex- L coeda, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-toch a 10 CFR 50.59 Safety Evaluation checklist.
| |
| Snfety Evaluation CfJ ^ Date <</#b Group /Dep't. Head Review NM C>< Date e'/N J Temporary Approval' b Date it!8 3 (NCS)
| |
| Temporary Approvale f
| |
| ~
| |
| j
| |
| # Date /M
| |
| <t M
| |
| QC Review A# k tl A -
| |
| Date /' ~ - r ?
| |
| PORC Revie 8 N /d - Date // //IKf - Meeting No. E'M Plant Manager-Nuclear Approval ' Neb [ Date "I 8F/'M
| |
| * Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days, i
| |
| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
| |
| | |
| WATERFORD 3 SES :
| |
| PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST
| |
| ~'
| |
| Procedure No. -' 'L % Title
| |
| %~~- '' di Effective Date E -' (<'a (if different from approval date) cannlate 1 B. or C A. Change No. ''/'I B. Revision No. 7 C. Deletion ^ /A RFAMcN FOR CHAMcF. RETT.9 TO N . OR DFLRTTOM
| |
| ~7*~
| |
| 0- w N .. _;
| |
| a
| |
| ..i, x: -u r- -,.s*
| |
| l 's ( :~
| |
| c a cw.. wJ REQUIRED SIGNATURES t
| |
| Originator T M l%' O -
| |
| Date 'e /; "I Ci Technical Review C- 6 ll- Date P//w / *'I
| |
| ,.)
| |
| SAFETT EVALUATION Joes this change, revision, or deletion: TES NO
| |
| : 1. Change the facility da described in the FSAR7 v
| |
| : 2. Change'the procedures as described in the FSAR7 v
| |
| : 3. Conduct testa / experiments not described in the FSAR7 __
| |
| : 4. Create a condition or conduct an operation which ex- -
| |
| d coeda, or could result in exceeding, the limits in Technical Specifications?
| |
| If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
| |
| Safety Evaluation CADU ~
| |
| Dat;e / l' Group /Dep't. Head Review N e 8 h (M d Dato Y/dM3
| |
| /
| |
| Temporary Approvale Date (NCS)
| |
| Temporary Approval
| |
| * Date QC Review /A 'M ' -M Date '' - 1 - -
| |
| PORC Review M['NNbaw Date b/C'F2 Meeting No. UT Plant Manager-Nuclear Approval A Date - ' '
| |
| '( '' / -
| |
| ' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
| |
| UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
| |
| | |
| E2crgtney Plan Inplemsnting Procedure EP-2-090 Core Damage Assessment Revision 2 TABLE OF CONTENTS 1.0 PURPOSE
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 30 RESPONSIBILITIES ,
| |
| ~
| |
| 4 . 0 .' INITIATING' CONDITIONS 5.0 PROCEDURE -
| |
| -5.1 Ccre Damage Based on Radioisotopic Analysis
| |
| * 52 Core Damage Based on Hydrogen Analysis 53 Core Damage Based on Radiation Dose Rate in Con'tainment 5.4 Core Damage Based on the Core Exit Thermocouples 6.0 FINAL CONDITIONS
| |
| , 70 ATTACHMENTS 71 Plant Conditions:(1 page) 72 Radiological Characteristics of NRC Categories of Fuel Damage (Radioisotopic) (1 page) 73 Density Correction Factor for Reactor Coolant Temperature (1 page) _
| |
| l 74 Sample Temperature and Pressure Correction (1 page) 75 Sample Decay Correction (1 page) l 76 Fission Product Release Source Identification (1 page) 77 Release Quantity (1 page) 7 8- Containment Building Water Level vs. Volume (1 page) 79 Steady-State Power Correction (1 page) 7 10 Transient' Power-Correction (2 pages) l-7 11 Percent Release (1 page) 7 12. Clad Damage Characteristics of NRC Categories of Fuel Damage (1 page)
| |
| I' 7 13 Core Uncovery Conditions (1 page) 7 14 Sampling Conditions and Measured Hydrogen (1 page)
| |
| _7 15 Calculation Worksheet for Hydrogen G3nerated in Containment (1 page) 1
| |
| . ~ . _ , - _ . . _ _ . . , , . , _ . , _ _ . . _ . . . . . _ _ , , _ _ . - _ . , . . . . _ _ , _ , . ~ _ . - _ .
| |
| | |
| > Easrgency Plen Impiscenting Procedure EP-2-090 Core Damage Assessment Revision 2 7 16 Hydrogen Production Rate in Containment as a Function of Temperature (1 page) 7 17 Calculation Worksheet for Hydrogen Generated by Radiolysis (1 page) 7 18 Specific Radiolytic Hydrogen Production vs. Time (1 page) 7 19 Core Damage Assessment from Hydrogen Measurement (1 page) ,
| |
| 7 20' Percent of Fuel Rods with Ruptured Clad vs. Core Clad Oxida-tion (1 page) -
| |
| 7 21 Percent of the Fuel Rods with Oxidation Embrittlement vs.
| |
| Total Core Oxidation (1 page) 7 22 Estimation of the Amount of Hydrogen in a Reactor Vessel Head Void (4-pages) 7 23 Radiological Characteristics of NRC Categories of Fuel Damage (Dose Rate) (1 page) 7 24 Post Accident Dose Rate Inside the Containment Building (1 page) 7 25 Temperature,_ Pressure and Damage Estimate (1 page) 7 26 Percent of Fuel Rods with.. Ruptured Clad vs. Maximum Core Exit Thermocouple Temperature (1 page)
| |
| LIST OF EFFECTIVE PAGES Title Revision 2 1-53 Revision 2 I
| |
| e 2
| |
| | |
| Ebcrgsncy-Plan.ImplcmGnting Procedure EP-2-090
| |
| . Core Damage Assessment Revision 2 1.0 PURPOSE l 1.1 This procedure is to be followed under postaccident plant conditions to determine the type and degree of reactor core damage which may have occurred, using:
| |
| 1.1.1 Fission product. isotopes measured in samples obtained from the Post-Accident Sampling System (PASS)
| |
| ~
| |
| 1.1.2 Hydrogen measured in samples obtained with the PASS i 1.1 3 Radiation dose rates measured inside the Containment Building using the wide range radiation monitor
| |
| -- 1.1. 4 The core exit thermocouples, to determine the number or fuel rods with ruptured clad 1.2 The resulting estimate of core damage is described by one or more of
| |
| 'the 10 categories of core damage in Attachment 7 2.
| |
| | |
| ==2.0 REFERENCES==
| |
| | |
| 2.1 CE-NPSD-241, Development of the Comprehensive Procedure Guidelines for Core Damage Assessment, C.E. Owners Group Task 467, July 1983 !
| |
| 2.2 NUREG-0737, Item ~II.B.3 23 Regulatory Guide 1 97 i
| |
| 2.4 Post: Accident Sampling System Procedures l i
| |
| 2.4.1 CE-3-900, Operation of the Post Accident Sampling System i 2.4.2. CE-3-903, Post. Accident Gamma Spectroscopic Analysis L2.4 3' CE-3-904, Post Accident Analysis of Dissolved Hydrogen in the .
| |
| Reactor Coolant 2.4.4 ' CE-3-901, Post Accident Sampling of Containment Atmosphere :
| |
| 25 -EP-1-001, Recognition and Classification of Emergency Conditions 3
| |
| | |
| Ercrgoney Plen IOplementing Proc 2 dure EP-2-090 Core Damage Assessment Revision 2 30 RESPONSIBILITIES 31 The Technical Support Center (TSC) Supervisor shall be responsible }
| |
| I for the implementation of this procedure under the Emergency ;
| |
| Coordinator.
| |
| 32 The TSC Lead Engineer shall provide recommendations on technical assessment.to the TSC Supervisor.
| |
| I 33 The Technical Support Center Engineers shall provide recommendations to the TSC Lead Engineer involving problems affecting plant safety l or operation during an emergency, including all' areas related to design and operation of Waterford 3 which pertain to mechanical, j electrical, fluid systems, reactor physics, chemistry and metallurgy evaluations.
| |
| 4.0 INITIATING-CONDITIONS 14 . 1 Any of the following emergencies has been declared: Alert, Site _
| |
| Area Emergency, General Emergency or an event has occurred that has placed the reactor and/or its auxiliary systems in a degraded condition or in a situation with the potential for further degrada-tion as evidenced by the following:
| |
| 4.1.1 HIGH alarm on the Containment Radiation Monitor 4.2 As determined by the TSC Supervisor or the Emergency Coordinator.
| |
| 4
| |
| | |
| t Escrg0ncy Plcn Impicntnting Procadure EP-2-090 Core Damage Assessment Revision 2 5.0 PROCEDURE l NOTE The assessment of core damage obtained by using this procedure is only *an estimate.
| |
| The techniques employed in this procedure are accurate only to locate the core condition
| |
| ~
| |
| within one or more of the 10 categories of core damage described in Attachment 7 2.
| |
| i 5.1 CORE DAMAGE BASED ON RADI0 ISOTOPIC ANALYSIS 5.1.1 Section 5 1 relies upon samples taken from multiple locations inside the Containment Building to determine the total quantity of fission products available for release to the environment. The l amount of fission products present at each sample locatior may be !
| |
| changing rapidly due to transient plant conditions. Therefore, it is required that the samples should be obtained within a minimum !
| |
| time period and if possible under stabilized plant conditions.
| |
| Samples obtained during rapidly changing plant conditions snould not be weighed heavily into the assessment of core damage, j 5.1.2 Correct the measured sample specific activity to standard temperature and pressure.
| |
| 5.1.2.1 Reactor coolant liquid samples are corrected for RCS temperature and pressure using the factor for water density provided in At-tachment 7 3 The correction factor obtained from the at-tachment is divided into the measured value to obtain the density corrected value. i 5.1.2.2 Containment Building sump samples do not require correction for ,
| |
| I temperature and pressure within the accuracy of this procedure, i 5.1.2 3 Containment Building atmosphere gas samples are ccrrected using !
| |
| the following equation.
| |
| 5
| |
| | |
| t-Emsrgoney Plan Implcumenting Procaduro EP-2-090 Core Damage Assessment Revision 2 Specific Activity at (STP) =
| |
| Specific Activity x P2 x T, + D60 P, +P g T.2 + 460 Where:
| |
| Tj , P, = Measured sample temperature and pressure recorded in Attachment 7 1 i
| |
| T,P 2 = Standard temperature, 32' F and standard pressure 14 7 2 ~
| |
| psia i
| |
| 5 1.2.4 Attachment 7 4 is provided as a worksheet.
| |
| 5.1 3 Correct the sample specific activity at STP for decay back to the j time of reactor shutdown which is recorded in Attachment 7 1 using the following equation. Attachment 7 5 is provided as a worksheet.
| |
| Ao" ,- t where:
| |
| A = the specific activity of the sample corrected back to the cima of reactor shutdown, pC1/cc.
| |
| A = the measured specific activity, uC1/ce.
| |
| A = the radioactive decay constant, 1/hr.
| |
| t t = the etas period from reactor shutdown to sample analysis, hr.
| |
| 5.1.4 Identification of the Fission Product Release Source 5.1.4.1 Calculate the following ratios for each noble gas and iodine isotope only, using the specific activities obtained in At-tachment 7.5. Attachment 7 6 is provided as a workaneet.
| |
| Noble Gas Ratio = Noble Gas- IsotSDe. Spgeific Activity Xe-133 Specific Activity Ioditie Ratio = Iodine Isotooe Soecific Activitz ;
| |
| I-131 Specific Activity i 6 1
| |
| | |
| Emcrgoney Plan Impicacnting Proceduro EP-2-090 Core Damage _ Assessment Revision 2 5 1.4.2 Determine the source of release by comparing the results obtained to the predicted ratios provided in Attachment 7 6. An accurate comparison is not anticipated. Within the accuracy of this procedure, it is appropriate to select as the source that l ratio which is closest to the value obtained in step 5.1.4.1.
| |
| 5.1 5- Calculate the total' quantity of fission products available for release - to the . environment. Attachment 7 7 is provided as a
| |
| ~
| |
| worksheet.
| |
| 5.1 5.1 If RCS conditions indicate the reactor vessel is full, the quantity of fission products found in the reactor coolant is calculated by the following equation:
| |
| Total Activity (C1) = Ao (pCi/cc) x RCS Volume i where:
| |
| Ao =-the specific activity of.the reactor coolant sample l
| |
| j corrected to time of reactor shutdown obtained in step 5 1 3, pCi/cc
| |
| : RCS Volume = the full Reactor Coolant System water volume
| |
| = 3 1899 x 108cm 3 l
| |
| l I
| |
| i l
| |
| l 7 l .. ~._ . . _ _ _ , _ _ , _ _ _ __ . _ _ _ , __ . _
| |
| | |
| Eccrgsncy Plan Implcmenting Procedure EP-2-090 Core ~ Damage Assessment Revision 2 i
| |
| NOTE
| |
| : 1. If RCS conditions recorded in Attachment 7 1 indicate that a steam void is present in the reactor vessel, then the quantity of fission products found in the reactor coolant is again calculated by step 5.1 5 1. However, it must be recognized _
| |
| that the value obtained will overestimate the actual quantity released. Therefore, this sample should be repeated at such
| |
| , time w' hen the plant operators have removed the void from the reactor vessel.
| |
| 5152 The quantity of fission products found in the Safety Injection Sump is determined as follows:
| |
| A. The water volume in the Safety Injection Sump is determined from the sump level recorded in Attachment 7 1 and the curve provided in Attachment 7 8.
| |
| B. The quantity of fission products in the sump is calculated by the following equation:
| |
| Total Activity, C1 = Ao (pCi/cc) x Sump Volume l
| |
| l Where:
| |
| l Ao = the specific activity of the Safety Injection Sump sample corrected to the time of reactor shutdown obtained in. step 5.1 3,,pCi/cc 5.1.5.3 The quantity of fission products found in the Containment Building atmosphere is determined as follows:
| |
| Gas Volume (STP) = Gas Volume x (P4- + P, ) x (T4 + 460)
| |
| ; " P3 (T g + 460) l 8
| |
| | |
| E2Grgoney Plcn Impicacnting Procedure EP-2-090
| |
| . Core Damage Assessment Revision 2 i
| |
| i Where: i 3
| |
| Gas Volume = Containment net free volume = 2,680,000 ft T, , Pg = Containment atmosphere temperature and pressure ,_
| |
| recorded in Attachment 7 1 Ty ,Pg = Standard temperature, 32 F, and standard pressure 14 7 psia 5 1.5.4 The total quantity of fission products available for release to the environment is equal to the sum of the values obtained from each sample location.
| |
| 5.1.6 Plant' Power Correction The quantitative release of the fission products is expressed as the percent of the source inventory at the time of the accident.
| |
| The. equilibrium source inventories are to be corrected for plant power hi' story.
| |
| 5 '.1. 6 .1 To' correct the source inventory for the case in which plant power level has remained constant for a period greater than four radioactive half-lives of the longest lived isotope present in the sample, the following procedure is employed. Attachment 7 9 e is provided as a worksheet.
| |
| 5.1.6.1,.1 The fission products are divided into two groups based upon
| |
| (
| |
| the radioactive half-lives. Group 1 isotopes are to be employed in the case where core power had not changed greater than i 10 percent within the last 30 days prior to the reactor shutdown. Group 2 isotopes are to be employed in the case where core power had not changed greater than i 10 percent within the last 4 days prior to the reactor shutdown.
| |
| 5 1.6.1.2 The following equation may be applied to the fission product group which meets the criteria stated in 5 1.6.1.1 only.
| |
| 9
| |
| | |
| Encrgoney Plcn Impismaating Procedure EP-2-090
| |
| - Core Damage Assessment- Revision 2 Group 1 Power Correction Factor = Steady-State Power Level Prior 3D_ Days 100 Group'2. Power Correction Factor = Standv. State Power Level Prior a Days 4
| |
| 100 7
| |
| 5.1.6.2 To correct the source inventory for the case in which plant power level has not remained constant prior to reactor shutdown, the'fo11owing equation is employed. The entire 30-day power i .
| |
| history.should.be employed. ' Attachment 7 10 is provided as a worksheet. This calculation must be made for each isotope of
| |
| , interest.
| |
| ^ l
| |
| ' Power-Correction Factor = i!1 P i( 1-c ~Ai t 13e -A i r$ ;
| |
| 100 ;
| |
| i Pj.= steady reactor power in period j, 5 tj = duration ~of period j, hr.
| |
| o- .
| |
| tj.= time from end of period j to rea'c tor shutdown, hr.
| |
| 11 = the radioactive decay constant, 1/hr.
| |
| (from Attachment 7 5) 5.1 7 Comparison of Measured Data with Source Inventory l
| |
| The total quantity of fission products available for release to the environment obtained in step 5.1.5.4 is compared to the source inventory.correcteu for plant power history obtained in step 5.1.6.1 or 5.1.6.2.. This comparison is made by dividing the two values for each isotope and calculating the percent of the cor-rectec source inventory that is'now in the sampled fluid and therefore available for release to the environment. Attachment 7 11 is provided as a worksheet. ,
| |
| 10
| |
| - -.._.~.---._._:
| |
| | |
| Encrg:ncy Plcn Implcmanting Procedure EP-2-090 Core Damage Assessment
| |
| ~
| |
| Revision 2 5 1.8 Core Damage Assessment NOTE The type of core damage is described in terms of the 10 NRC categories defined in Attachment
| |
| : 72. The degree of core damage is described as the percent of the fission products in the source inventory at the time of the accident ,
| |
| which are now in the sampled fluid and therefore available for release to the environment.
| |
| 5 .1. 8 .1 The conclusion on core damage is made using the three parameters developed above. These are: .
| |
| 5 1.8.1.1 Identification of the fission product isotopes which most characterize a given sample,_ step 5 1.2 5.1.8.1.2 Identification of the source of the release, step 5.1.4 5.1.8.1 3 Quantity of the fission product available for release to the environment, expressed as a percent of source inventory, step 517 5.1.8.2 Knowledgeable judgement is used'to compare the above three parameters to the definitions of the 10 NRC categories of fuel damage found in Attachment 7 2. Core damage is not anticipated to take place uniformly. Therefore, when evaluating the three parameters listed above, anticipate the procedure to yield a combination of one or more of the 10 categories defined in At-tachment 7 2. These categories will exist simultaneously.
| |
| 5.1 9 If the performance of any portion of this section indicates that core damage exists, refer to EP-1-001.
| |
| 11
| |
| | |
| Emergency Plen'Implcmsnting Procedure EP-2-090 Core Damage Assessment Revision 2 52 . CORE DAMAGE BASED ON HYDROGEN ANALYSIS Section 5 2 relies upon hydrogen samples taken from the containment atmosphere and the Reactor-Coolant System Hot Leg. Those samples may contain a mixture of hydrogen generated within the core by clad.
| |
| oxidation and.also hydrogen from radiolytic dissociation of water and oxidation of aluminum and zinc in the containment. The estimate of. clad damage is influenced by the amount of hydrogen generated by
| |
| ~
| |
| - ex-core sources and by- the ability to identify plant conditions conducive to such hydrogen generation. Therefore, a hydrogen measurement is not a unique indicator of the amount of core clad ox-idation.
| |
| Section 5 2 yields estimates of the percentages of fuel rods with rupturea clad and embrittled clad. Simultaneous with embrittling of the clad, clad melting and pellet overheating may occur. Section 5 2 provides an estimate of only the percentage of rods which have progfessed to at least clad rupture or clad embrittlement and does not attempt to predict the physical configuration of those rods which have progressed beyond local clad fragmentation.
| |
| 5.2.1 Complete Attachment 7 13 i 5.2.1.1 The magnitude of Reactor Coolant System (RCS) pressure during the core uncovery period can influence the number of early clad ruptures. Interpret the data from QSPDS or the trending status I board to determine the best estimate for the time period of core uncovery and determine the range of RCS pressure during this time period. Record on Attachment 7 13 5 2.1.2 The presence of some subcooled inlet flow while the core is uncovering can slow the uncovery and cause greater local clad oxidation for a given total amount of core oxidation ~, thereby leading to a greater. underestimate of the number of damaged rods predicted by this procedure. Observe available instrument ,
| |
| records to determine if there was some reactor vessel inlet ficw l
| |
| during the rising temperature portion of the core uncovery 12 l
| |
| | |
| Escrgency Plen Impicmanting Procaduro EP-2-090 Core Damage Assessment Revision 2 period. Include net flow from charging and letdown systems, HPSI, LPSI, spray, etc. Record the data on Attachment 7 13 5.2.1 3 Record the conditions in the containment and the Reactor Coolant i System at the time the hydrogen samples are obtained in step ,
| |
| t 5 2.2 following. Enter on the worksheet of Attachment 7 14. ;
| |
| NOTE _
| |
| If RCS conditions indicate that a void exists in the RCS and the void cannot be removed, refer to Attachment 7 22.
| |
| 5.2.2 Obtain a liquid sample from the RCS Hot Leg and a gas sample from the containment atmosphere and analyze them for hydrogen concentration. Record the results on the worksheet of Attachment 7 14. Follow the instructions on Attachment 7 14 to obtain the total amount of hydrogen measured in units of cubic feet of hydrogen at standard temperature and pressure, l i 5.2 3 The total measured hyd-ogen in step 5.2.2 includes the hydrogen l I
| |
| generated by three processes: 1) core clad oxidation, 2) radiolysis of water, and 3) oxidation of containment materials such as aluminum and zinc. The amount of hydrogen generated by the last two processes is calculated and then subtracted from the total measured to yield the amount generated by core clad oxida-tion.
| |
| Attachment 7 15 is a worksheet for calculating the amount of hydrogen generated by oxidation of materials within the l containment. It utilizes measured data for the containment temperature as a function of time up to the sampling time and a plant specific curve of the rate of production as a function of containment temperature in Attachment 7 16. Record the data required on Attachment 7 15 and complete the indicated 13
| |
| | |
| t E22rg0ncy Plcn Implemsnting Procedure EP-2-090
| |
| -Core Damage Assessment Revision 2 calculations to obtain the cubic feet-of hydrogen at STP generated by containment materials oxidation.
| |
| 5.2.4 The hydrogen generated by radiolysis is a function-of operating power and decay time. Record the data required;on Attachment 7 17, and utilize the curve of Attachment 7 18 to obtain the cubic feet of hydrogen at STP generated by radiolysis. The appropriate power is determined as follows:
| |
| 5 2.4.1 For the case in which the operating power is constant or has not changed by more than i 10 percent for a period greater than 30 days, that power is used.
| |
| .5 2.4.2 For the case in which the power has not remained constant during the 30 days prior to the reactor shutdown, engineering judgement is used to determine.the most representative power level. The following guidelines should be considered in the determination.
| |
| 5.2.4.2.1 The average power during the 30-day time period is not necessarily-the most representative value for determining radiolysis by fission products.
| |
| 5 2.4.2.2 The last . power levels at which the reactor operated should weigh more heavily in the judgement than the earlier levels.
| |
| 5.2.4.2 3 Continued operation for an extended period should weigh more
| |
| . heavily in the judgement than brief transient levels.
| |
| 5.2.4.2.4 For the case in which the reactor has produced power for less
| |
| .than 30 days, the procedure may be employed. However, the estimate of hydrogen from radiolysis will be too high and, therefore, the calculated hydrogen by core oxidation will be too low. Hence, an underprediction of core damage may result.
| |
| 5.2.5 complete Attachment 7.19 to yield the cubic feet of hydrogen generated by core clad oxidation. Adjust with the constant shown on the worksheet to obtain the estimated percent of the core clad which is oxidized.
| |
| 14
| |
| | |
| L
| |
| ~
| |
| Encrgency' Plan Implementing Procedure EP-2-090 Core Damage Assessment Revision 2 5 2.6 -Enter _the abscissa of the curve on Attachment 7 20 with the percent of core clad oxidation from step 5.2.5. Use the curve labeled with the pressure closest to but greater than the RCS pressure during the core uncovery period'as obtained in step.
| |
| 5.2.1.1 and recorded on Attachment 7 13 Read on the ordinate of Attachment 7 20 the percent of fuel " rods with ruptured clad.
| |
| Record on the worksheet' of Attachment 7 19. Note that the sensitivity of measurement of hydrogen is comparable to the range .
| |
| of oxidation on Attachment 7 20. Hence, small amounts or clad l rupture are not reliably predicted by this procedure. l 527 Enter the abscissa of the curve on Attachment 7 21 with the j percent of core clad oxidized from step 5 2.5. Read on the !
| |
| ordinate the lower and upper values of the range indicated by the !
| |
| curve for the' percent of' fuel rods which have embrittled clad.
| |
| Record on the worksheet of Attachment 7 19,
| |
| ~
| |
| 5.2.8 For a given percent oxidation of the core clad, the lower limit of embrittled clad estimated in step 5 2 7 is, for most accident p scenarios, the least amount of potential fuel structural failure.
| |
| Actual values are probably greater. The upper limit of the range l in step 5 2 7 may be interpreted as follows:
| |
| 5 2.8.1 When the pressure during uncovery, from Attachment 7 1-and
| |
| ; recorded _ n Attachment 7 13, is less than about 100 psia, a rapid core uncovery by blowdown is concluded. Heatup 'itn w
| |
| minimum clad oxidation occurs. The extent of potential clad structural failure by melting may be greater than the upper limit of embrittlement from step 5 2 7 as determined by oxidation.' Hence, use the upper limit from step 5.2.7.
| |
| 5 2.8.2 When'there is inlet flow while the core is uncovering, the rate of uncovery is slower than assumed in the derivation of the h curves on Attachments 7 20 and 7 21. For a measured total amount of oxidation, the local percentage oxidation is probably 1
| |
| 15
| |
| | |
| EO;rgoney Plan Impicmsnting Procadure EP-2-090 Core P' mage Assessment. Revision 2 i
| |
| greater along a shorter length of the upper portions of the fuel. Hence, favor the upper limit from step 5 2 7 5.2.9 Cores Damage Assessment The' conclusion on core damage is made using the two results from above.
| |
| These are:
| |
| 5 '. 2 . 9 .1 Percentage of~ fuel rods with ruptured clad, step 5 2.6 _
| |
| '5292 Percentage.of fuel rods with embrittled or structurally damaged clad, step 5 2 7 l
| |
| 5 2.9 Knowledgeable judgement is used to compare the above two results ;
| |
| to the definitions of the seven NRC categories of fuel damage !
| |
| I found in Attachment 7 12'. Core damage does not take place ,
| |
| uniformly. Therefore, in evaluating damage using these results, Attachment'7 12 may yield a combination of-categories of damage which exist simultaneously.
| |
| 5.2.10 If'the performance of any portion of this section indicates that core damage exists, refer to EP-1-001.
| |
| 5 3 - CORE DAMAGE BASED ON RADIATION DOSE RATE IN CONTAINMENT Section 5 3 relies upon radiation dose rate measurements taken from one or more monitors located inside the Containment Building to determine the total quantity of fission products released from the core and therefore available for release to the environment. The amount of fission products present at the location of the monitors may be. changing rapidly due to transient plant conditions.
| |
| Therefore, multiple measurements should be obtained within a minimum time period and,-when possible, unde'r stabilized plant conditions.
| |
| Samples obtained during rapidly changing plant conditions should not be weighed heavily into the assessment of core damage.
| |
| Section 5 3 is limited to the interpretation of the dose rate
| |
| -measurement resulting from a mix of fission products. Section 53 cannot accurately distinguish between the conditions of fuel 16
| |
| | |
| E20rgency: Plen Implementing Procadure EP-2-090 Core Damage Assessment Revision 2 cladding failure and fuel overheat when the resulting dose rates are ,
| |
| the same. Section 5.3 does provide an upper limit estimate of the {
| |
| progressive core damage. Concurrent conditions of cladding failure and overheat should be anticipated due to the radial distribution of heat generation within the core. Distinction between the types of core damage requires the identification of the characteriste fission
| |
| -products. The procedure for core damage assessment using radiological analysis of fluid samp1~es is required to explicitly ,
| |
| distinguish.between the categories.
| |
| 531 Plant Power Correction .
| |
| The measured radiation dose rate inside the Containment Building is to be corrected for the plant power history. A correction factor is used to adjust the measured dose rate to the corresponding value had the plant been operating at 100 percent power.
| |
| 5 3 1.1 To correct the radiation dose rate for the case in which plant power level has remained constant for a period greater than 30 days, a simple ratio of the power may be employed. The reactor power is considered to be constant if it has not changed by i 10 percent within the last 30 days prior to the reactor shutdown.
| |
| 5 3 1.2 To ccrrect the radiation dose rate for the case in which reactor power level-has not remained constant during the 30 days prior to the reactor. shutdown, engineering judgement is used to determine the most representative power level. The following guidelines should be considered in the determinat' on.
| |
| 5 3 1.2.1 The average power during the 30-day time period ~ is not necessarily the most representative value for correction to equilibrium conditions.
| |
| 5 3 1.2.2 The last power levels at which the reactor operated should weigh more heavily in the judgement than the earlier levels.
| |
| 17
| |
| | |
| Emergency Plan Implementing Procedure EP-2-OoO Core Damage Assessment Revision 2 1
| |
| 5 3 1.2 3 Continued operation for an extended period should weigh more heavily in the judgement than brief transient levels.
| |
| 5313 In the case in which the reactor has produced power for less than 30 days, the procedure may be employed. However, the estimate of core damage obtained under this condition *may be an underprediction of the actual condition.
| |
| 5 3 1.4 The following equation is applied to determine the radiation -
| |
| dose rate corresponding to equilibrius full power source inventory conditions.
| |
| Equilibrium = Measured x 100 Dose Rate Dose Rate Reactor Power Level The reacter power level and the rest'lting dose rate correction factor used above will be the same foc all subsequent measurements of the dose rate. Record these values to reduce
| |
| . the work required to, evaluate the subsequent measurements. ,
| |
| Dose rate correction factor = 100 Reactor Power Level
| |
| =
| |
| 532 The decay correction for the radiation dose rate requires the determination of the time duration between the reactor shutdown
| |
| . and the measurement of the dose rate. This is done simply using c
| |
| the time of reactor shutdown recorded in Attachment 7 1.
| |
| 533 The conclusion on the extent of core damage is made using the a equilibrium dose rate, the duration of reactor shutdown, and the analyticall1 determined dose rates provided in Attachment 7 24.
| |
| [ The equilibrium dose rate is pletted on Attachment 7 2'4 as a
| |
| ~
| |
| $ function of time following reactor shutdown. Engineering I judgement is used to determine which category of core damage shown
| |
| -$ on Attachment 7 24 is most representative of the particular value that has been plotted. The following criteria should be
| |
| =
| |
| g considered in the determination.
| |
| 18 b
| |
| b 1
| |
| b- _
| |
| | |
| ' ' ' '' ~ " ' ' ~ ~ ' ~' ~'~
| |
| Emergency Plan Implementing Procedure EP-2-090 Core. Damage Assessment Revision 2 1
| |
| 5331 Dose rate measurements may have been recorded during periods or j transient conditions within the plant. Mensurements made during stable plant conditions should weigh more heavily in the assessment of core damage.
| |
| 5332 Dose rates significantly above the lower bound for the category of major fuel overheat may indicate concurrent fuel pellet melting. This section may not be employed to estimate the
| |
| ~
| |
| degree of fuel pellet melting.
| |
| 5333 Dose rates within any category of fuel overheating may be ,
| |
| anticipated to include cone"rrent fuel cladding failure. This section may not be used to distinguish tne relative i l
| |
| contributions of the two categories to the total dose rate.
| |
| l This section does give the ostimate of the highest category of damage.
| |
| 5334 Dose rates corresponding to the two categories of major cladding failure and initial fuel overheat are observed to overlap on At-tachment 7 24. The evaluation of other plant parameters may be required to distinguish between them. However, concurrent conditions may be anticipated.
| |
| 534 The type of core damage le described in terms of the seven NRC categories defined in Attachment 7 23 The degree or core damage is determined by the dose rate present in the containment and is read from Attachment 7 24.
| |
| 535 If the performance of any portion of this section indicates that core damage exists, refer to EP-1-001.
| |
| 19
| |
| | |
| Eccrgoney Plan Inplemanting Proccdure EP-2-0 90 i Core Damage Assessment Revision 2 l
| |
| 54 CORE' DAMAGE BASED ON THE CORE EXIT THERMOCOUPLES 1
| |
| 'The assessment of damage provided by section 5 4 extends up to the time of, clad rupture on most of the fuel rods. This time occurs j early in very severe core uncovery accidents. More severe core j damage'cannot be' quantified by this procedure.
| |
| The+ relationship between the core exit thermocouple temperature and-
| |
| !~ the clad temperature varies with the core uncovery scenario. Lec- ,
| |
| tion 5 4 applies to slow core uncovery by boiloff of the coolant.
| |
| i For other more' rapid uncovery scenarios, section 5.4 could yield a very-low estimate of the number of ruptured rods. In general, for core uncovery at pressures below about 1200 psia, there is high confidence.that at least the predicted estimate of rods is actually L rupturea.
| |
| 5.4.1 Obtain the following from the instrument recordings:
| |
| 5 4.1.1 'From the recording.of maximum core exit' thermocouple temperature as a function of time, obtain and record on Attachment 7 25 the l maximum temperature and the time it occurs.
| |
| l l
| |
| 5.4.1.2 From the recording of Reactor Coolant System pressure as a function of tin,e, obtain and record on Attachment 7 25 the <
| |
| ; e pressure during the period of maximum thermocouple temperature.
| |
| 5.4.2 Select the curve on Attachment 7 26 which is labeled with a pressure approximately equal to or greater than the pressure in step 5.4.1.2. Enter the abscissa at the maximum temperature from l . step 5.4.1.1 and read on the ordinate the percent of the fuel rods
| |
| ~ which'have ruptured clad. Record on Attachment 7 25.
| |
| 5.4 3 - The result in step 5.4.2 is probably' a lower limit estimate of damage. Some judgement on the bias is available as follows.
| |
| l l 5.4'.3 1 This procedure applies most directly for relatively slow core uncovery with a maximum temperature below the rapid oxidation temperatures at about 1800 F and above. A smooth core exit 20 i
| |
| - - - - y.-r4. -~.-e~- .,,,%. -
| |
| - -m ,-
| |
| .m.e - ., - , - . . ..,.._.,,.y_, ._,-.r, qy,-:.-,.._,e, ,_mem ,,-,.-.-.y, -m-
| |
| | |
| Emorgoney Plan Implementing Procedure EP-2-090 Core Damage Assessment Revision 2
| |
| =
| |
| Z thermocouple recording and an.uncovery duration of 20 minutes or ,
| |
| longer are indicators for a good prediction of clad ruptures. -
| |
| : i 5.4 3 2 If the pressure in step 5.4.1.2 drops to less than about 100 I .i i
| |
| psia within less than about two minutes of accident initiation, i a large break is indicated. This causes undetected core heatup .
| |
| followed by flashing during refill. Depending on the rate of refill, the thermocouple temperature may rise rapidly, then i d
| |
| I quench when the core is recovered. This procedure could yield a -
| |
| very low estimate for the p,ercent of rods ruptured. ;
| |
| i 1 5.4 3 3 If the pressure in step 5.4.1.2 is above about 1650 psia, it l ;
| |
| could exceed the rod internal gas pressure, depending on rod f f burnup, causing clad collapse onto the fuel pellet instead of j =
| |
| outward clad ballooning. The clad rupture criteria are less well defined for such conditions, but at temperatures above 1800 l F, where the highest pressure curve applies on Attachment 7 26, }
| |
| clad failure sufficient to release fission gas is likely and -
| |
| this procedure may be used to obtain estimates of damage.
| |
| 5 4.4 Core Damage Assessment Use the percent of rods ruptured from step 5.4.2 and the clad j damage characteristics of Attachment 7 2 to determine the NRC category of cladding failure. This procedure yields damage estimates in categories 2, 3 or 4.
| |
| 5.4.5 If the performance of any por*. ion of this section indicates that -
| |
| cere damage exists, refer to EP-1-001. i 6.0 FINAL CONDITIONS 6.1 Abnormal plant conditions have been terminated or decreased below Alert, and l
| |
| 6.2 Assessment or abnormal plant events or conditions has been completed or transferred to the Recovery Organization; or l -
| |
| i 21 I
| |
| | |
| - _ - - . - - . . _ _ - . _ _ _ _ _ = _ .
| |
| 1 En:rgancy Plan Irplcacnting Procoduro EP-2-0 90 :
| |
| Core Damage Assessment Revision 2 i
| |
| 63 The Technical Support Center is deactivated in accordance with .
| |
| I EP-2-100.
| |
| 70 ATTACHMENTS
| |
| ~~
| |
| 71 Plant Conditions 72 Radiological Characteristics of NRC Categories of Fuel Damage (Radioisotopic) i.
| |
| 7 3' Density Correction Factor for Reactor Coolant Temperature 8 l
| |
| I 74 Sample Temperature and Pressure Correction l
| |
| 75 Sample Decay Correction :
| |
| 1 i
| |
| 76 Fission Product Release Source Identification !
| |
| 77 Release Quantity 7~8
| |
| . Containment Building Water Level vs. Volume 79 Steady-State Power. Correction 7 10 Transient Power Correction 7 11- Percent Release 7 12 Clad Damage Characteristics of NRC Categories of Fuel Damage 7 13 Core Uncovery Conditions 7 14 Sampling Conditions and Measured Hyrdrogen
| |
| '7 15 Calculation Worksheet for Hydrogen Generated in Containment 7 16 Hydrogen Production-Rate in Containment as a Function of Temperature 7 17 Calculation Worksheet_for Hydrogen Generated by Radiolysis 7 18 Specific Radiolytic Hydrogen Production vs. Time 7 19 Core' Damage Assessment from Hydrogen Measurement 22
| |
| | |
| I EP-2-090
| |
| 'Em:rgency Plcn Inplcacnting Proccduro Ccre Damage Assessment Revision 2 7 20 Parcent of Fuel Rods with Ruptured Clad vs. Core Clad Oxidatien 7 21 Percent of the Fuel Rods with Oxidation Embrittlement vs. Total Core Oxidation 7 22 Estimation of the Amount of Hydrogen in a Reactor- Vessel Head Void 7 23 Radiological Characteristics of NRC Categories of Fuel Damage (Dose Rate) i 7 24 Post Accident Dose Rate Inside the Containment Building 7 25 Temperature, Pressure and Damage Estimate 7 26 Percent of Fuel Rods with Ruptured Clad vs. Maximum Core Exit Thermocouple Temperature 9
| |
| 23
| |
| | |
| PLANT CONDITIONS Rccord the following plant conditions. Because of transient conditions, the values should be recorded as closely as possible to the time at which the radiological samples are obtained from the Post Accident Sampling System.
| |
| Rcactor Coolant System:
| |
| Pressure psia Tcmperature #
| |
| F Pressurizer Level 5 Core Exit Thermocouple Temperature -
| |
| F -
| |
| Core Exit Thermocouple Saturation Margin -
| |
| 0 F subcooled t
| |
| Containment Building:
| |
| Atmospnere Pressure psia Atmosphere Temperature -
| |
| F
| |
| ^
| |
| S:fety Injection Sump Level -
| |
| feet R:diation Dose Rate rads /hr Time or Measurement Date -
| |
| Time _
| |
| Prior 30-day Power History: Power. Percent Duration. Days l
| |
| r Time of Reactor Shutdown Date Time l
| |
| l EP-2-090 Revision 2 24 Attachment 7 1 ( 1 of 1 )
| |
| | |
| r- _
| |
| 4 t x
| |
| RADIOI.OGICAL CilAR ACTERISTICS OF 'llRC CATEG0i!IES OF FUEL DAMAGE (RAblUIS0 TOPIC) helease of Characteristic
| |
| !!I.t; Cateciry of ' Mechanism of Source of Charnoteristic Isotope Expr essed as a -
| |
| ' F.uc].J)nm3Et ^ .ItCSSMt EL12.% C. 1591952 E. cts.tDL 95 LOMCSt liL12.CL9L1
| |
| : 1. He fuel Imunge llalogen Spiking Gar. Gap - I-131, Cs-137 Lesk than 1
| |
| -Tramp Uranium Rb-83
| |
| . Ini tial Clodding Gas Gap ' Less than 10 Fo11 pre 3 Intermediate Clad Burst and Gas Gas Gap Ke-131m. Ie-133 to to 50 C1roding Follure Gap Diffusion I-1'31. I-133 Belcase
| |
| '4. !?ajor C1ndding Gas Gap Greater than 50 l'ntlure
| |
| : 5. . Initial Fuel Pellet Fuel Pellet Cs-134. Eb-38, Less than 10 l overheating . Te-129. Te-132 Grain Boundary Diffusion t'. . Intt.rmedtote Fuel fuel Pellet to to 50 Pel.let Overheating Diffusional Release Greater tnan 50 7 4:3.inr Fuel Pellet Fuel Pellet
| |
| , overheatina From UO Groins Fuel Pellet Less than 10 1 C. For t Pelict Mnit 9 lutcrmertinte Fuel Escape from flo1 ten Fuel Pellet Ba-140, La-17.0 10 to 50 Pellet Helt Fuel La-142, Pr-144 l
| |
| l
| |
| : 10. thjor Fuct Pellet Fuel Pellet Greater than 50 tiel t l
| |
| l EI'-2-.090 Rev it: ion 2 25 Attachment 7 2 (1 of 1)
| |
| * DENSITY CORRECTION FACTOR FOR REACIOR COOLANT TEMPERATURE 700 -
| |
| 600 500 -
| |
| 400 -
| |
| G 300 _
| |
| i 200 -
| |
| t 100 --
| |
| i l
| |
| i- 0 I e i r O 0.25 0.50 0.75 1.0 ACT! STP DENSITY CORRECTION FACTOR t
| |
| E .a, i
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| i l- 1 I !
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| l EP-2-090 Revision 2 26 _ _ _
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| Attachment 7.3 . (1 of 1) ._ , _ _ _
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| y - - - . . ._ _
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| ll J v e e e i m r H e e I' z
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| 4 it '3 7'. 7 S. E 1 O I l I 6 1 1 t 1 ! l 1 1 r *- -a. 1_ -
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| r .
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| f F 0 1 C I
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| ! TcT . S t:
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| f l lI. I' I
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| 8 5 AMPLE l'ECL T COHliECTJefa Tiue er I:enrtor Eliistdown (see 4ttacsimetal 7 1):-
| |
| 5:.p.g Ir f ismtie r : _
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| I.rica t i on : .. ___
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| Tiene of Analy:st:::
| |
| Decay Specific Activity Decay Coreected Cont.t a nt .h) p STI' ( A tt actin''nt. 7 4) , T.pecific Activity, innru,e .11hr j PCiLcc pC1/ns
| |
| . . . f.; 5 . '.' ' ( - 1 ) _ . - . - ._
| |
| A r ~.1 41 m P.4 (-3) ___. -
| |
| x e- 13 t' 5. 't (-3) --
| |
| t-- 131 3 6 -(-3) .
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| I- 112 3 0 (-1) 3.-133 3 3 (-2) _
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| l-135 1.0 (-1) -
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| c:;- 13 4 4.0 (-5)
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| I'li. r.T; 23 (0) .
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| 9 - 1,') r, .1 (-1) ..
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| T -13? 9.0 (-3) r.r. h') 5.0 (-4) lui- I NO 2 3 (-3) -
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| I.si- 1 MO 1 7 (-2)
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| * 4 En-142 4 3 (-1)
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| I'r-144 2.4 ( 0) .-
| |
| EI'-?-090 Revision 2 p el Attacliment 7 5 (1 or l}
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| i
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| | |
| + ,
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| s' >
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| , , , 2''
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| ,f i ,
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| FITGiCN PRODUCT REl.F ASF SOURCE IDf.MTIFICATIOP
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| . se e; i c t!matcr: __
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| I.<.< n t i nn :
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| Decay Cormhted Spectric Activiti'- - Cal cul ated Fue1~rellet fet.1vity Ratio. .Identirted J:e.'A i r- .( Altacimst!1_.755L.fiC1/nc 'Isotnps:_J;plirl Inr.emi.ory . In_U3 r_(Dr Sovert
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| ~
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| af _ t:i - _ 0.2 ';.0.001--
| |
| Ta-131m _ _a 0.003 0.001-0.003 Xe- 1.11 6 _ . _ _
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| 1.0 - 1.0
| |
| * 1-131 . _ _ _ . - _. 1.0 1.0 l 1-13? ___
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| 1.4 0.01-0.05 J-113 _. _.
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| 2.0 0 5-1.0 1-1 m -
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| 1.8 c.1-0.5 ;
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| glQ%%AI
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| ~
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| site. file 'Gan Enti o = Dg Egggfl,cggD InditicRatio=Draag -[-ji{2, R[ "g-%S Q g 3Illl e
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| i I
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| EI' ."-O'jo Rev iol on 2 20 At ta climer:L 7 6 (1 of 1) a p.
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| | |
| s ret,EACE QUANTITY Snmi t e 11o. :
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| 1.w:a ti on : ._
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| Tiise of Asi.alysis:
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| r _ -
| |
| - - ~
| |
| Itcactor Coolant Coitais: ment Sump Co nta i ns&.t Total I Santl e , Atmosphere Sample, =
| |
| Sample, Quantity
| |
| .ir.n tsen si El El E1 Ki - 0? + __ + =
| |
| Xo-131m 4 4 =
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| Xc-133 p f :.
| |
| I-.131 + _ ., =
| |
| 1-13? 4 + =
| |
| J -.13 3 t 4 - "
| |
| 1-135 -
| |
| + + =
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| C n - 13 'l + + =
| |
| lib-08 -
| |
| + ..+ =
| |
| Te-1?9 + f To-137 + O
| |
| .l _ .-
| |
| 3:-e9 4 + - = -
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| Da- 1 M()
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| 4 .l %
| |
| I.a-lh0 t t =
| |
| 1.n- 1 M2 4 t =
| |
| l's lilli f .- f- O
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| , E f'- 2-.0 90 Revision 2 30 f.t techoent 7.7 (l ofI )
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| 1 e_
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| .)
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| Dw a e m
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| O N O C
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| -- O.
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| O O
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| CC CO e
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| I%
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| O &
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| rw a 4
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| O ik, O 5
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| > c la3 2 <= e.
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| C e O e M N . -
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| W
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| -i. . ;
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| t STE ADY-STATE POWER CORRECTION .
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| L ,- 4 Sartple Number:2_ __
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| Lohation: .
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| T4cn<ly-State Day Power I.evel: - -
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| Lt ,nly-State 4-Day Power Level: . _
| |
| Fuel Power ' Equilibrium corrected 111st ory Correction x Source' = Source-EU.Ctpr ' J'tYrAtpry Jnigmipry
| |
| .I ro.t "i).t fitCPFR.1DS J- . _ ..
| |
| 0:s fl.lb p_ID VSAt_or_X '
| |
| \
| |
| ~
| |
| Kr 87 - 2 x 9 5-(0) = -
| |
| x 6.6 (4) =
| |
| Xn-131m 1 ___
| |
| X c- 13,1 '1 x 1.8 (7) =
| |
| 't-111 1 x 9.0 (6) .=
| |
| T-132 2 x 9 9 -(3) =
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| 1-133 '2 x 8.9 (6) ,
| |
| s I - 13 r, 2 __
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| .x- 1.6 (6) =
| |
| l t ps_J .htls.t_Jnrentory .
| |
| t.r- Gi 2 x 4 7 (7) =
| |
| 7a-13im 1.
| |
| * x 70(5) =
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| t - 1.4 3 1 __
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| x 2.0 (8) =
| |
| t-111 1 x 9 9 (7) =
| |
| 1-13? 2 x 1.4 (8) =
| |
| 1-133 2 x 2.0 (8) =
| |
| t-145 2 x 1 9 (8) = _
| |
| ta-134 1 x 6.8 (7) =
| |
| x 94 (7) =
| |
| Ft. T8 2 x 31(7) =
| |
| Tc- 12') 2 ___
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| Te-13? 1 x 1.4 (8) =
| |
| Sr-09 1 x 1.8 (7) =
| |
| na-140 1 x f .7 ( 8) =
| |
| La-140 1 x 1.8 (8) :
| |
| La-142 2 x 2.2 ( 8) .=
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| x 1.2 . ( 8) =
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| Pr-144 2 l
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| 1 ~
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| l E!*-2-O')U kcylsten 2 72 Attachment 7 9 (1 of 1)
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| | |
| e- ,
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| -I t
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| TRANS1ENT POWFl! CORRECIl0N 4 t
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| ' Sample Number:_' -: _ . - -
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| ' Loca ti on s ' --
| |
| Duratism Jipyr; Prior 30-Day Power History: 'EnBr_3
| |
| , 'l-Equilibrium Source = Corrected Source Power Correction x EnSpr hasMars .InvenL9x1 Jp2.tprs EUA.NPPLJ91 SAL 9r1 .l x 9 5 (0) =
| |
| Kr Et _.
| |
| = -
| |
| -- x 6.6 (4) l Jc-131
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| - x 1.8 (7) =
| |
| Xe-133
| |
| ~
| |
| z 9 0 (6) = 1 l
| |
| I-131 =
| |
| - x 99(3) !
| |
| 1-132 l
| |
| - x 8.9 (6) =~
| |
| I-133 1.6 ( 6) =
| |
| - x I-135 Ehr) ts31_e1 Jo.YpMar_1 ..
| |
| x 4 7 (7) = . - - -
| |
| Kr 87 =
| |
| 7 0 (5)
| |
| -- - x l xe-131m
| |
| - x 2 0 (8) =
| |
| xe-133
| |
| ,x 9 9 (7) =
| |
| 1-131 '=
| |
| x 1.4 (8) l-132 2.0 (8) =
| |
| - x 1-133 1 9 (8) = --
| |
| l -
| |
| x 1
| |
| 1-135 -
| |
| - x 6.8 (7) =
| |
| cr.-13 4
| |
| - x 9.4 (7) =
| |
| Rb fin =
| |
| r 1 _x 3 1 (7)
| |
| Te-179
| |
| * x 1.4 (8) =
| |
| .Te-132 t.8 (7) ,= _ _
| |
| x Sr 89 x 17(8) = -
| |
| Da-140
| |
| - E 1.8 (8)
| |
| * I.n-140
| |
| - x 2.2 (8) = --
| |
| La 142 =
| |
| s 1.2 ( 8) - - -
| |
| P r.-14 4
| |
| :4 33 Attachment 7 10 (I or 2)
| |
| EP-7-090 Revision 2 -
| |
| | |
| ll)Il'
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| )
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| P ri e
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| l-(
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| . m
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| .n .
| |
| . PERCENT RELEASE Totni, Quantity, rower corrected-Source Inventory,,n.100- -=
| |
| Avalleble For' Release ESELLtDL C1
| |
| 'Jn:sttvn '-
| |
| LA1% Dst 48ss\% 1.3.) CA I .-.th%%Dsbn9D% L.93 9T T- 11Y . _
| |
| ~RO J"P.lnvr#$9t! =
| |
| i-Kr-117 =
| |
| Xe-131: "
| |
| E
| |
| 'xe-133 *
| |
| - - =
| |
| I-131 . -_._=__
| |
| J-112 - = =
| |
| t-133
| |
| ..r = _
| |
| $ - 1 b') . A- k Ev~3 VcUsLJ03sPt921
| |
| * gr-cy
| |
| + .. ,
| |
| xe - 1 !1m
| |
| '= -
| |
| xo-133 ,
| |
| z 1-131 _
| |
| x, I-IJP -
| |
| * 1-133 '~ " -
| |
| g _3 7 t; _
| |
| 4
| |
| * C . 1 T il 'g, .t. -
| |
| y --
| |
| lit 3 -C fi _
| |
| . =
| |
| Ta- 1 ;'?
| |
| - 4 -_ s
| |
| _1 Tar - 13,"
| |
| Or-09 =
| |
| . ~-
| |
| na-1 spi "
| |
| I,a- 1810 =
| |
| La 18t? . __
| |
| p r - t re ri - _ - . -- .-
| |
| 1 35 At taclimcnl 7.11 (1 of 1)
| |
| EP-2 090 Revinton 2-
| |
| | |
| Cl.AD DAllACE CitARACTERISTICS. OF NRC CATEGORIES OF FUEL DAMAGE Hechanisri- Characteristic' Measurement Percent on EPC'Caterp y. Temperature Rppu f E.1 v i-.Da m n e.. tLW9Lvn.cv.L E;'nuc. D.1natr-.Kun M-.E w.L tynygg
| |
| # -- Less tnan 1
| |
| . 1. ' t!" Funi lauaar,e 750 . f!one -
| |
| ~ .,
| |
| Nazimum core (1550 F8 Less than 10 P. Itiltini Cladding !!upture due to Gas gap exit-Failure Lverpressurization ' Thermocouple < 17 00"F " 10 to 50 3 Intermediate . 'N 1200-1800
| |
| 'tindding failure
| |
| . temperature
| |
| ' tl . .. Ih:Jor Cindding
| |
| *(2300 F
| |
| ^*( 25 Greater than 50 oxidation S. Initial Fuel Pellet overheating Amount or Equivalent Less than 10 h1800-3500 . Loss.o'r structural integrity due to hydro 6en gas core fuel clad oxida- pr odu ced oxidation tion (equivalent to <35 5 oxidation of <tas core)
| |
| .6. Intermedinte Fuel I'cIlet Overheating
| |
| ~<655 creater Lnen 50 7 flajor Fuct Pellet Overheating
| |
| *Dc3+nda on reactor pressure and fuel burnup. Valves given for pressure 31200 psia and bur sup 10.
| |
| t i
| |
| l 6 At tachicent. 7 12 ( 1 of 1)
| |
| EP-P-090 itevist m 2
| |
| | |
| 4 -
| |
| j CORE UNCOVEET C01DIT10fl3-
| |
| ~
| |
| 7 13 1 - Time period of core uncovery. . Complete the f ollowing table tising recorded instrument data.
| |
| Estimated- Estimated i ladr umsid ' DrfJinspyfrY 11F; .CrJJ. RecastLIjM Rrnet er Vessel Level Lower Limit Elevation Lower Limit Eleva-INui toring System Uncovers. ' tion Recovers.
| |
| ' Time Time
| |
| ' Core Exi t. Thernoccuple St5rt of Continueu. Rapid Temperature Temscrature ise 1me or Exceed 660 F.-'
| |
| prop to Saturation.
| |
| Time Temperature _;. Temperature _
| |
| Core Exit Thermocouple Start of Superheat. Return to Saturation Taturatton ttartin or Subcooling.
| |
| Time - Time 7 13 7 Toterpret above data to obtain best* cstimate for time period o1 core uncovery and obtain pressurizer pressure range during that period. The superheat derivco from the thermocouple temperature and corresponding system pressure is *c nsidered as the best indicator for core uncover
| |
| * durin boioffandshouldbe$seddenlify botshouldbecomparedwitfitheokher ndicators to help possitile anomalies. The ressure during uncovery is used later on curve Attachment 7 18 stepof tenumberofckcinetheappropriate for assessmedt .2.6 to dele ad ruptures.
| |
| D re Unssysry Core Rssm sr1 T J n3a Pressure 7133 Estimate vessel inlet flow rates during core uncovery heatup
| |
| * cried, up to approximately the time of peak core exst thermocou-ite temperature. Met inlet flow indicates that procedure may uve additional bias which underpredicts clad damage.
| |
| Charging Flow Rate i
| |
| I.etdown Flow Rate llPT.I Flow Rate I. PSI Flow Rate Other inlet Flows l
| |
| ' EP-?-C'JO Revision 2 37 Attachment 7 13 ( 1 of 1)
| |
| | |
| -+ , .
| |
| ? .
| |
| 9
| |
| :SAilpLillG CONDIT10fl0 Al:D HEAstlRED flTDEOGE!f T.14.1. ubtnin the RCS and containment conditions at II.c time of nampling for h p'r or,e n .
| |
| D' nnL yr_*ds9 .5stit.D3D11St 1
| |
| 50 n%.01992AL Simrifnc Time Atmosphere prersure psig Presnure psig Atmosphere temperisture F Tems,aratore F llan hydrogen recombiner- Yes/No
| |
| . operated?-'
| |
| Heactor Vessel Cools.nt Level 5 Does pressure or tempera-ture history indicate a hydrogen burn? Yes/No l'rernurizer f.evel 5 7 181.? Ilydrogen Sample Data Reduction.
| |
| Cont, Comple x Cont. Vol. z. (32 + 460) 4 (Normal T$mp.) = ft# liydrogen 1 *MD a3]IP LVrl...%L1M __L_ x Zb DH x 492 :
| |
| 1100 Ler, Onmple x RCS Vol. i Density Batio Y 1000 m ft flydrogen fA1.tagim3pt_J al._ HIE icp/M..f_STf.L_ 7_g ,
| |
| Total Alno record totn] on Attachment 7 1',.
| |
| 6 EP-2-Ur)0 Revision 2 j8 Attachment 7 184 (1 of 1)
| |
| | |
| + e
| |
| .y E
| |
| CALCUl.AT10N VORKSinEET Folt ~
| |
| " HYDROGEN Gi.flFR ATED !!! CONTAINI'ElIT .
| |
| ~
| |
| 7',.19 1 Recori' the cor.tainment temperate re at re1ceted time intervals (i.r.,
| |
| 5, .10 or 15 minuter as required) and calculate the hydrogen generated by oxidation of cont.ainment materials utilizing the' production rates frca4 At.tachments 7 16. r -
| |
| j q
| |
| 2 1 3 4 'S 1
| |
| Avg. Centainment I!
| |
| 7 Prod. Rate j (ft /hr, a Time at Start Interval Temp. During FI2 Produced l IvSst.13 L 1'E] .t M 1 f.9)
| |
| .O ki tst':T.YRLD . DutAL1DD 11nti .
| |
| AL.12&msch 2 16- - .
| |
| {
| |
| w 1 _
| |
| ~
| |
| 'l Accident Starts ;
| |
| l l
| |
| %.apling Time 39 Attachment 7 15 (1 or 1)
| |
| .. F.I'-a-040 frev ia ton 2
| |
| | |
| 1 HYDROGEN PRODUCTION RATE IN CONTAINMENT AS A FUNCTION OF TEMPERATURE 4600 -
| |
| 4400 -
| |
| 4200 -
| |
| 4000 .
| |
| 3800 --
| |
| 3600 .
| |
| 3400 -
| |
| 3200 -
| |
| g 3000 -
| |
| 2 8 2800 -
| |
| 2600 -
| |
| 2400 .
| |
| * 2200 -
| |
| 5
| |
| {2000 .
| |
| e
| |
| *, 1800 -
| |
| o g 1600 - -
| |
| a 1400 -
| |
| 1200 -
| |
| 1000 800 -
| |
| 600 -
| |
| 400 -
| |
| 200 _
| |
| '^ '
| |
| 0 i i i i e i e ,
| |
| 100 120 140 160 180 200 220 240 260 280 300 t TEMPERATURE, *F I
| |
| EP-2-090 Revision 2 40 Attachment 7.16 (1 of 1)
| |
| | |
| - y,. ; -
| |
| i.
| |
| cal'.CUI.ATICH WORbilLET FOR I 111DROGEN CEtiT.Lt.TEI) BY RAntoi.YSIr.
| |
| ~
| |
| 7 17 .I' Har'rd tiie'following' data and utilize the curve., of Attachment 7 10 to
| |
| .dete mint ,!he hydrogen gencrried by radiolyst s.
| |
| 7 1'(.l.1 prior 30-day power history fpvst._ftrcSp1 Ruts 1120uhaJA.
| |
| 7 17 1.2 rower to tue in evaluatint: long term hydrogen productten by
| |
| , radiolysis. = 3390 MWt x 5 ( f rom al>ov e )
| |
| 7 17 1 3 Reactor Trip Time -hr 7.17 1.4 Sampling Time (see Attachment 7 181) _ . - . hr 7 17 1 5 Decay Time (Snap 11ng Time - Trip Time) -
| |
| hr .
| |
| '7 17 2 Enter' abscissi on Attachment 7 18 with above ' decay time and read two valuen of hydrogen produced by radiolysis, one from each curve, in cubic feet of hydrogen at STP per HWt operating power. Multiply by above pnuer and record as follows:
| |
| Hydr ogen produced Operating a Total Hydrogen
| |
| * i 1.t:.: t t..c or v_c 1 ACE /M1j_411ashat:11_7..J f) fs!Ler_f.ftli.t3 frA99.cS.0_.iACE)
| |
| * i l
| |
| 1 ffpper - 3 s l 1.nver a a 7.17 3 Uning rcSJ1t3 f rom Section 5 1, estimate which results should be n icd, upper limit for major fuel overheat or lower limit for intermediate fuel overheat. Circle corresponding value of hydrogen above and also record on'ALL&chment 7 19 l =
| |
| 1
| |
| (
| |
| - EF-?-190 Revision 2 84 1 Att.achment 7 17 (1 of 1) t
| |
| | |
| 14 -
| |
| SPECIFIC RADIOLYTIC HYDROCEN PRODUCTION v2 TIME 13 _
| |
| 12 - ,
| |
| MAJOR FUEL OVEhHEAT 11
| |
| . !E
| |
| 'es
| |
| :n
| |
| : n. 10 8
| |
| z*9 -
| |
| S U
| |
| E8 -
| |
| a m
| |
| ,7 INTERMEDIATE FUEL OVERHEAT g .
| |
| 8 ce g6 _.
| |
| a p3 -
| |
| 8 s
| |
| h4 _
| |
| s D3 -
| |
| M 0;
| |
| 2 ..
| |
| g INITIAL FUEL OVERHEAT 0 e e a n , , , ,
| |
| 0 100 200 300 400 300 600 700 800 TIME, HOURS EP-2-090 Revision 2 /2 4
| |
| Attachment 7.18 (1 of 1)
| |
| . . , . . .I .
| |
| | |
| i a
| |
| e-CORE DAMAGE l"23ES311FilT FROH llTDROGEN li4A.".UI:EI ENT SCF
| |
| '7 13.'l llydrogen Measured, step'7 14.2, Attechr.ent 7 181
| |
| -[
| |
| . "i . I b ? Ilydrogen Produced in Containment, step 7 15 1, SCF Attachment 7 15 7193 flydror,en Produ'ced by Radiclynis, step 7 17 2, SCF Attachment 7 17 7.19.4 Subts act steps 7 19 2 and 7 19 3 from 7 19 1 to SCF
| |
| ' prt I.ydrogen produced by core clad oxidation -
| |
| 7 19.5 Divide by 5.04 x 10 3 SCF/1% clad oxidized = - 1
| |
| ; Cind Oxid ated 1 19.6 Enter abseissa on Attachment 7 20 with "5 Clad Oxidized" and rend ordinate from curve labeled with pressure during core uncovery as given on Attachment 7 13, step 713 2. Record here-Percent of Fuel Rods with Ruptured Clad 5 7197 Enter abscissa on' Attachment 7 21 with above "5 Clad Oxidized" '
| |
| nnd read range of values on ordinate. Record here:
| |
| rercent of fuel reIs embrittled Range - Upper -
| |
| 5 ,
| |
| *- - I.ower - 5 Review step 5 3.i to determine which of these limits is .1 tore 7190 Ilkely to be representative of the core damage.
| |
| 7199 From Attachment 7 12, select the core clad damage . categories b:ised on the above percentages of rods ruptured and rods embrit-tied.
| |
| 6 1
| |
| N arn r7 . _43 _
| |
| Attachment 7 19 (1 er 1) ----- - -_ - _ _ -
| |
| | |
| PERCENT OF FUEL RODS WITH RUPTURED CLAD vs CORE CLAD OXIDATION P c4 100 PSIA 100 -
| |
| RUPTURI: PRESSURE 80 -
| |
| P < 1200 PSIA
| |
| @ 60 .
| |
| 5 P < 1650 PSIA 2
| |
| E E
| |
| 5 40 , .
| |
| l m 8
| |
| as En.
| |
| C I
| |
| H l 20 "
| |
| i t
| |
| l l 0 i ,
| |
| 8 e
| |
| ! 0 0.5 1.0 1.5 2.0 l
| |
| l % OXIDATION OF CORE CLAD VOLUME l
| |
| l i
| |
| ?
| |
| 44 '.
| |
| EP-2-090 Revision 2 Attachment 7.20 (1 of 1) i p w __ _
| |
| y -. .m_ - - , - . - . .- - .e .- ..-. _g
| |
| | |
| PERCENT OF THE-FUEL RODS WITH OXIDATION EMBRITTLEMLVI vs _
| |
| TOTAL CORE OXIDATION FOR 1% TO 3% nECAY HEAT AND 300 PSIA TO 2500 PSIA WHEN COOLANT LEVEL DROPS SY BOILO N WITH NG INLTI FLOW IFf1L CORE IS RAPIDLY QUENCHED 100 -
| |
| 1
| |
| $ 80 -
| |
| E E
| |
| [<60 t
| |
| E o
| |
| 3
| |
| , 40 -
| |
| C.
| |
| 3 un 8
| |
| m g 20
| |
| * E B
| |
| M 0 ' # e i 1 0 20 40 60 80 100
| |
| % OXIDATION OF CORE CLAD VOLUME i
| |
| i \
| |
| EP-2-090 Revision 2 45 Attachttent 7.21 (1 of 1) [
| |
| t
| |
| | |
| a ESTIMATION OF Tite A: Mitt!T OF !!TOHOGE'; 188 A REACTOR VIIdEl. IIEAD VOID 7...'.f !?Ilt!"!?
| |
| 1h? p irpone of thi s attachn,nt la to prov 14-* an analy tical g ro.edure to calculate the nme,unt of hydroger. Fas contained in a void in the top of the reactor vessel. TI.is hydrogen is added j
| |
| to the measured amount in step 5 2.5 of the procedure to
| |
| <fetermine the total hydror.cn generated I,y all ecurces.
| |
| 7.??.? .IJ!!' DTIRffS 7 . ? r . ? ."1 The preferreo method of e termining the nuonnt or hydrogen in r the primary system is to nample liquid f rom the hot leg when l
| |
| the system is full. Ilowe 7 c e , if the systen cannot be filled, ihis attachment can be used to est nisate the hydrogen which is in the vessel void and which would not be evioent from the hot l ag liquid sample.
| |
| 7.?2.7.7 This guideline applies when the coolant level is above the hot i
| |
| Ic6 and the remainder of the primary system is filled.
| |
| Verification that the Steam Generator tories are filled can bc 3revided by the existence of natural convection fJow in the I grimar system. If the coolant level is below 1he hot leg, l
| |
| the guidelines cf this attachment do not arply.
| |
| i f
| |
| : 7. /.2 3 A Ikactor Vessel Level Monitoring Systen is required which can provide the coolant level. The volume of the void is obtained t>y relating the volume la the vessel at.ove the coolant level to the value of the level for each specific reactor vessel derign.
| |
| 7.?P.P.4 This guideline provides the analytical means for only an estimate of the hydrogen contalised in the void. The presence l
| |
| l of other gases, includinr. helium, nitro 6en, and fission product gases will add uncertainty to the result.
| |
| a hP-2-090 Revision 2 46 Attachment 7 22 (I cf 4)
| |
| | |
| _ O F.3TIliATION OF TIIE At:0UNT OF !!iDROGEN IH A REACTOR VESSEL. IIEAD VOID 7.??.3 utoS1;jdRE The following is a guideline for an analytical. procedure to be f ollowed to estimate the omrunt of hydrogen contained in a void in the top of the reactor versel,. Calculatio-nal details and plant specti'ic information munt be included to implement this guideline. .
| |
| 7 22.3 1 Determine the conditions of the void as follows:
| |
| V Void volume (f t ) derived from measurement et coolant-level Tg = Temperature of 11guld at coolant surf aces ("F)
| |
| P.; ,1 = Water saturation pressure at temperature T P : Reactor coolant system pressure (psla) g4 .
| |
| 7 22 3 2 A first approximation is made assuming the followings y
| |
| A. The pirtial pressure of vapor in the void is assumed equal to enturatinn pressure at the liquid temperature. T., This implies no beating of the void gna by the reactor vessel walls and head. They nre normally at reactor outlet temperature and could remain above the temperature of the void causing the vapor to 'se superhested.
| |
| 11 All the noncondensible gas in the void is hydror,en. This implies no helium or fission product gas from ruptured fuel rods and no nitrogen from Safety Injection Tanks. A cecond approsisation which eliminates this assumption is given in step 7.?2 3 4 below.
| |
| 7 22 3 3 Calculate the amount of hydro 5en as follows:
| |
| Ill *I lot -Pg;
| |
| # P ft lig @ STP = (V) 81 2 ' 4 14.7 .{9'D+ 30 Add this amount to the tot:21 hydror,en in step 5.2 5 7 22 3 4 A second approximation can Le mode in plants with a C-E designed PASS which menzimres oc'h total gas and hydrogen wnich are dissolved in the hot 3cn 11guld snaple. This approxima- a rts. ,=== w ay
| |
| | |
| , v e
| |
| f
| |
| .. .r. .
| |
| ESTIMATION OF THE AHOUNT OF HYDROGEN IN A REACTOR-VES5EL HEAD VOID-tion includesL the following assumptions regarding the. relative solubilities of the noncoudencible gases in the liquid.
| |
| A. The p. anes nre-ass'u med to ha've the same values' of Henry'a' law
| |
| ' onnstant, which relates the partial pressure. of gas to the amount of gas' dissolved in the liquid sample at equilibrium.
| |
| U. When the_ dissolved gas is not'in equilibrium with the gas in the void, the dissolved conceittrations are in the emme relative proportion as if equilibrium did exist. ,
| |
| 7.??.3 5' 'The partial pressure of hydrogen is calculate'd from H
| |
| Illt = (Pg -Pga g ) , eg,totald and the amount of hydrogen in the vessel head void is .
| |
| calculated using the equation above in step 7.22 3 3 a k
| |
| . e.A EP-2-090 Revision 2 43 At.tachnent 7 22 (': or 4)
| |
| - n
| |
| | |
| \
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| M9 N
| |
| N A
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| L e
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| \ er N O V
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| \ -o 69 N i . N N.
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| \ b
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| \ -
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| e.m O
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| E-M C U m C N 4J N M x
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| w me Pm o
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| e.*
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| mar Pat h
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| 2 \
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| e.
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| m .
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| ,f M
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| '9 o
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| -ta,
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| >* f*"* U
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| - E T,,
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| ,E.J
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| '3 <
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| , =
| |
| 5 C
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| }* O >
| |
| . T t: 69 rt,
| |
| > = C M
| |
| =
| |
| -empP tus#
| |
| 'A
| |
| -s O
| |
| mq N
| |
| o \ m C
| |
| O 7-
| |
| \. N 2
| |
| T -
| |
| O >
| |
| \ ma s
| |
| N =
| |
| , t +
| |
| .! e o
| |
| . .-.- em.=,.. ..me - -w e - . - - + = = - * = - = = - - - = = = - - * * * " , *-
| |
| ~. = g f
| |
| 1 I I e l { pJ .
| |
| n e m ~
| |
| : m. o
| |
| ,. - - e- =- -
| |
| y., *=.:~-
| |
| .t N & < s a C N CO -
| |
| 5 su.*
| |
| M M
| |
| '.) Li $r r- 'I > M Q L G M > d.
| |
| | |
| :3
| |
| . .. i .
| |
| RADIOLOGICAL f:13 ARACTERISTICS GF fiRC' CATEGORIES 'OF FUEL DAHAGE (DOSE RATE)-
| |
| Fercent ot'' Source Inventory Distributton os Fission Mgchnnina of Source of PRC Coter, cry.of Ern.4 tic.tLin &npL.a5pp.ep%
| |
| Es 1.eD:n EsisDwd 19..Cn.n%ak.varD% -
| |
| EncS Datu.nst - Eshan. Erst.Ents Less than 1- Airborne llalogen Spikin6 Ces Cap
| |
| : 1. tio Fori Damage Tramp Uranium Less than 10 Ai rbor ne Gas. Gap
| |
| : 2. Inittal Cloddin Fn1 Jure- Airbor ne l Can Gap 10 tp 50-3, 1ctermediate Clad Durr.t and Gas Cladding Failure Gap Diffusion Releasa ,
| |
| Airborrie
| |
| ' Gas Gap
| |
| . Greater tnan 50 ri . Hajor Cladding Failurc Airoorne :
| |
| Fuel Pellet Lens than 10 5 Initial Finei Pe57 1005 Noble Gas Overheating 25s Ilatogen
| |
| )rainDoundary Diffusion to to 50 Plated out
| |
| : f. , Intermediate Fuci Fuel Pellet 255 ilasogen Pc11ct Overheatirs 15 Solids Fuel Pellet Greater tnan 50 7 linjor Fuel Pellet Diffusional Reicase overheating From UD- Grains
| |
| *4
| |
| ' ~' -
| |
| . . - a n a n cther ntl. 7_ Q fa of 1)
| |
| | |
| 4 POST ACCIDE'IT DCSE RATE INSIDE THE CONTAI': MENT 3dILDING
| |
| ' 1x10 0-
| |
| *IJ om 5
| |
| 1x10 -
| |
| CA g&~
| |
| -#47
| |
| ?? &p
| |
| #4 N
| |
| Ok
| |
| $ %e'>' +.1'O
| |
| %,lp O C
| |
| /,g, N g, #
| |
| +
| |
| e x
| |
| <fg 9
| |
| ?4 . .
| |
| # \
| |
| Nx N
| |
| \
| |
| 1x10 1
| |
| \ 4 \, ,
| |
| -1 10 100 1000 TIME POST ACCIDENT, HOLIRS CYLINDRICAL CCNTAECE'iT
| |
| [EP-2-090 hvision 2 ' 31 Attachment 7.24 (! of 1)
| |
| ~
| |
| | |
| .e
| |
| <,V^
| |
| l1 p e.
| |
| I-TEMPERATURE,'PHESSURE AND DAMAGE ESTlHATE
| |
| ~ 7 25 1' RecorAl the following data:
| |
| l "Itaximura ' Core E'xit Thermocouple . Temperature . #F Time of Haximum. Temperature .
| |
| 1 Reactor Coolant System Pressure at Above; Time pain .
| |
| 7 25,2 From Attachment .7 26, at maximum thermocouple temperature and'at appropriate pressure, read percent of ruptured rods. 5 7 ? 'i . 3 comment on probable bias or> result in 7 25 2-(see section 5.2.5 in text). ,
| |
| 7051 NHC catc6ery of cladding failure from Attachment 7 2 l
| |
| EP-2 090 Hevision 2 5? Attachment 7 75 ( l of 1)
| |
| | |
| PERCENT OF FUEL RODS WITH RtiPTURED CLAS vs MAXIMUM CORE EXII THERMOCOUPLE TEMPERATURE 100" a Pc100 PSIA j 80 -
| |
| U 8
| |
| @ P<1200 PSIA t
| |
| w a N-E E
| |
| e a 40 -
| |
| w
| |
| % Pc1650' PSIA o
| |
| E ' 20 _.
| |
| S U -
| |
| 0 i i , , ,
| |
| 1200 1400 1600 1800 2000 2200 MAXIMUM CORE EXIT THERMOCOUPLE TEMPERATURE
| |
| ~EP-2-090 Revision 2 53 Attachment 7.26 (1 of 1)
| |
| | |
| WATERFORD 3 SES 7 PLANT OPERATING MANUAL ~~ _
| |
| ~
| |
| LOUISIANA
| |
| ~
| |
| POWER & LIGHT
| |
| * U$SNEM POM' VOLUME ia EP-2-091 POM SECTION 2 REVISION 2 Emergency Plan Implementing Procedures I
| |
| Emergency Chemistry LP&L W-3 RECORDS UNCONTROLLED COPY i
| |
| LO NOT UP.E IN ANY SAFETY-RELATED TESTr IvtAiN10ivANCE, OR OPERATIOi4AL ACTIVITY
| |
| ! PORC geeting No, 84-01 Reviewed:
| |
| J' / j., -
| |
| A .A.* u wIe , -. - --
| |
| 4' f PORC Ch' airman Approved th s' l!bY Plant Manager-Nuclear Approval Date Fuel Load Effective Da 5 '
| |
| -. - _. .-_.-}}
| |
