ML20072A185
| ML20072A185 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/12/1983 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20072A177 | List: |
| References | |
| PROC-830412-01, NUDOCS 8306090416 | |
| Download: ML20072A185 (663) | |
Text
{{#Wiki_filter:. TABLE OF CONTENTS WATERFORD 3 STEAM ELECTRIC STATION EMERGENCY PLAN IMPLEMENTING DOCUMENT Document Section ; Section I Implementing Instructions
- EP-1-001 Recognition and Classification of Emergency Conditions
- EP-1-010 Unusual Event EP-1-020 Alert
- EP-1-030 Site Emergency
- EP-1-040 General Emergency Section II Implementing Procedures
- EP-2-010 Notifications and Communications
- EP-2-020 Contaminated Injured /Ill Personnel
- EP-2-030 Emergency Radiation Exposure Guidelines and l Control
- EP-2-031 In-Plant Radiological Controls During Emergencies
- EP-2-032 Monitoring and Decontamination
- EP-2-033 Administration of Iodine Blocking Agents EP-2-050 Offsite Dose Assessment (Manual)
EP-2-051 Offsite Dose Assessment (Computerized) l
- EP-2-052 Protective Action Guidelines l
- EP-2-060 Radiological Field Monitoring EP-2-061 Emergency. Environmental Monitoring
- EP-2-070 Protected Area Evacuation
- EP-2-071 Site Evacuation ggg * - PORC APPROVED PROCEDURES '
8306090416 830606 PDR ADOCK 05000382 F PDR
- EP-2-081 Search and Rescue
- EP-2-090 Accident Assessment EP-2-091 Emergency Chemistry
- EP-2-100 Technical Support Center (TSC) Activation, Operation and Deactivation g i
- EP-2-101 Operational Support Center (OSC) Activation, -
Operation and Deactivation
- EP-2-102 Emergency Operations Facility (EOF) Activation,-
Operation and Deactivation i
- EP-2-110 Man-Caused Emergencies
- EP-2-120 Natural Emergencies
- EP-2-130 Emergency Team Assignments
- EP-2-140 Reentry
- EP-2-150 Emergency Records
- EP-2-170 Recovery Section III Supporting Procedures EP-3-001 Emergency Plan Abstract EP-3-010 Emergency Plan Training EP-3-020 Emergency Preparedness Drills and Exercises
- EP-3-030 Emergency Planning Review and Updating
- EP-3-040 Emergency Equipment Inventory l
[ EP-3-050 Emergency Response Call List l-I
- EP-3-060 Emergency Communications Guidelines I
l
* - PORC APPROVED PROCEDURES ,
WATERFORD 3 SES PLANT OPERATING MANDAL LOUISIANA POWER & LIGHT - UTu.mES SYSTEM I-0l POM VOLUME 1a g70N , bl - [ PCM SECTION 1 APPROVAL DATE: EFFECTIVE DATE: Fuel L7ad [/ 8 F.MERGENCY PLAN IMPLDIENTING INSTRUCTION UNUSUAL EVENT Lp&L sN-3 RECORDS CONTROLLED COPY NO. 8 - PORC Mee ing No. f3 - da B } Reviewed: \ q 3RC Chai m i Approved: p t, %% \
- Plant Manager-Nuclear e
4 l
1 l l WATERFORD 3 SES PLANT OPERATING HANUAL l CHANGE / REVISION / DELETION REQUEST frocedure No. Ef- 1-A r 0 Title (J M M a n t drMd7 Effective Date /u 'l mmh (if different from approval date) i Comnlete 1. B. er C A. Change No. / B. Revision No. #/ Y . C. Deletion N/4 RFAMON FOR CHANOE. REVISION. OR DELETION 5 Lwd dibe lJww mduMua,a AISC 5,/. kal/ ' AROr - AA A' e n a, f, s A ert i REOUTRED SIGNATURES l
}
l Originator M ' Date Technical Review N/4 Date N/4 SAFETY EVALUATION , Does this change, revision, or deletion: TES NO
- 1. Change the facility as described in the FSAR7 Z
; 2. Change the procedure's as described in the FSAR7- /
- 3. Conduct tests / experiments not described in the FSAR7
- 4. Create a condition or conduct an operation which ex- Z ceeds, 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 bO I Date Y ~~I lM Group /Dep't. HeadReNew bO bo1b Date M'll-F5 u o Temporary Approvale Date (NOS) Temporary Approval
- Date QC Review ks ch'/J- Date " - ! f * -r 3 PORC Review Y lh M d Date WJ id 1 Meetingfo. fkN4 PlantManagerONuclearApprbval *kb M'W U Date MN?
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
~ _ ~ , - - . - - .
WATERFORD 3 SES PLANT OPERATING MANDAL g i MICOLE SOUTH I.OUISIANA UT1UTIES SYSTEM EP-1-020 POM VOLUME 18 REVISION 1 , g[>, / POM SECTION 1 APPR0i.*AL DATE:
. EFFECTIVE DATE: Fuel Load j DERGENCY PLAN IMPLDENTING INSTRUCTION ALERT LP&L W-3 P.2 CORDS CONTROLLED COPY no. 629 :
( PORC Meeting No. f3 024 i Reviewed: hy_ 5 Chairman 3 Approved: a LA;La Plant Manager-Nuclear
l WATERFORD 3 SES PLANT OPERATING MANUAL ; CHANGE / REVISION / DELETION REQUEST Procedure No. 5f"/-0M Title /*Adf7 Effective Date 4 44 M4A (if different from approval date) Comnlete A. B. or C A. Change No. / - B. Revision No. / , C. Deletion N4 . i REAMON FOR CHANCE. REVISION. OR DELETION
& %.J<?~ db i w. m 74of b.,.1 i
n WAC. 5,k bA m > .1 1/Cr A')) EI4 m ;o, NN REOUTRED SIGNATURES Originator N 4 +' Date / Technical Review #/A Date N/4 SAFETT EVALUATION , 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 FSAR7- 2
- 3. Conduct tests / experiments not described in the FSAR7 s'
- 4. Create a condition or conduct an operation which ex- 2 ceeds, or could result in exceeding, the limits in Technical Specifications?
l If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safet aluation checklist. Safety Evaluation @I b Date IJ - /l-N Group /Dep't. Head Revikw -NC '~O M h Date Y'I A'O V I Temporary Approval
- Date (NOS)
Temporary Approvale Date QC Review _ A' A rh r/ M .- Date " - 'E M PORC Review U $ b b k Date 4-I C' -
- 5 Meeting No. A rd Plant ManagerkNuclear Appr' oval b mO'd N Date 'b
' 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) 6
WATERFORD 3 SES PLANT OPERATING MANDAL LOUISIANA "T Ml0DLE SOUTH untmS SYSTEM EP-1-030 POM VOLUME 18 REVISION 3 y3, / POM SECTION 1 APPROVAL DATE: FFECTIVE DATE: Fuel Load g i EMERGENCY PLAN IMPLEMENTING INSTRUCTION j SITE EMERGENCY LP&L W-3 RECORCS _ _ - . -n C O N _1 M u,,'L w l COPY NO _ d PORC Mee ing No. (3.f 2 g , Reviewed: Chai n Approved: %
\h Plant Manager-Nuclear l
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l WATERFORD 3 SES PLANT OPERATING MANUAL l CHANGE / REVISION / DELETION REwJEST
.rocedure No. $A f-030 Title SCA iMa&'M Y Effective Date 4 41 wb (if different from approval date)
Comniate 1. B. or C A. Change No. *
/
B. Revision No. / C. Deletion */A
- prAMON FOR CHANSE. REVISION. OR DELETION
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! AIM Efele,,., hiN REUUIRED SION ATURES, . Originator' bbvI AM Date /* Technical Review a/ Date "/4 SAFETY EVALUATION . Does this change, revision, er 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- / ceeds, 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 valuation checklist. Safety Evaluation bO b Date Y-l)-E S l Group /Dep't. Head Review 4" N Nb Date V-( 2-N h l { l Temporary Approval
- Date (NOS)
Temporary Approval
- Date l QC Review NA an'/d- Date "-'S-77 PORC Review $ db Date 4-IN 3 Meeting No. 9Nf/
Plant Manager 1 Nuclear Apprbval M O W M Date '#N
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) i
WATERFORD 3 SES PLANT OPERATING MANDAL Louissama MICOLE SOUTH UTIUTIES SYSTEM _ EP-1-040 PCM VOLUME 18 REVISION 1 1 POM SECTION APPROVAL DATE: EFFECTIVE DATE: Fuel Load EMERGENCY PLAN IMPLNTING INSTRUCTION GENERAL EMERGENCY LP&L W-3 RECORDS CONTROLLED COPY NO. OSY PORC Meeting No. f3-02 8 [ Reviewed:\ , Approved: & Plant Manager-Nuclear
. . e
l . WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST
.rocedure No. Ef NO Title CiMEDL im.'Mirac Y Effective Date /ud2 wa6 (if different from approval date)
Comniete A. B. er C A. Change No. / B. Revision No. / * - C. Deletion __ N/4 RCAFON FOR CHANCE. REVISION. OR DELFTION r
& re n f (b Vd, L*-__ . m /.U9 rh ,.> :, /G?c da/ /bn,-J Lf Ad d E44ecT N t bn # '
REQUIRED SIGNATUHF3 Originator b w Date # H Technical Review Nfd Date /# SAFETT EVALUATION , 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 FSAR?- 7
- 3. Conduct tests / experiments not described in the FSAR? r
- 4. Create a condition or conduct an operation which ex- 7 ceeds, 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 ation checklist. l Safety Evaluation bO b Date M-/b3S Group /Dep't. Head Review Y[ bdb
- Date Y-/1 -S' 3 I
Temporary Approva1' Date (NOS) Temporary Approval' Date QC Review AW JN'd - Date e ~ w - e's PORC Review NNb Da 4-l Y-9 3 Meeting No. J3 -era PlantManagebNuclearApphoval EkN Date /k1
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 9
WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA POWER & LIGHT h E5 SYSb EP-1-001 POM VOLLE 18 ' REVISION 1 POM SECTION 1 APPROVAL DATE: May 2, 19 83 EFFECTIVE DATE: Fuel Load DiERGENCY PLAN IMPLEMENTING INSTRUCTIONS RECOGNITION AIO CLASSIFICATION OF EMERGENCY CONDITIONS tpat.W-3 p.nCOFDS CONTROW,.p. COPY NO. Oh
. hg PORC Meeting No f3-/ 74 Reviewed: . ma ~
Ch crm A Approved: d Ydb M Plant Manager-Nuclear _y
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. EP-l~00l Title knya$w uNbss/mQ etc ;., 6..JMm-l Effective Date b/ /c3/ (if different from approval date) Comnlete A. B. or C g g A. Change No. #"T'% B. Revision No. ip $ I , C. Deletion "/A RE ASON FOR CH ANGE. REVISION. OR DELETIQE To clea- /* mi ss . , L >1%n .>s ros vire l Ar $ NSC em sis?l REQUIRED SICNATURK.4 Originator lO Date I- /9- S 3 Technical Review b O bru o/ w Date 3-l&- Y 3
\1 Q SAFETY 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 V l 4. Create a condition or conduct an operation which ex- V l ceeds, 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 Safet Evaluation checklist. Safety Evaluation @h Date 3 *II'O Group /Dep't. HeadReNew v
%Ib1u Date 2~/b91 O
Temporary Approvale Date (NOS) Temporary Approval
- Date QC Review /.kA ktC&: - Date M-%f"t?
PORC Review [ I4 u h Date # ' Meeting No. f'3 -m PlantMana[r[NuclearApproval N/A h Date wh *
' 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
1 N Emsrgoney Plcn Idplemsnting'Iristruction , ss
.EP-1-001 Recognition and C1'assification of i Revision 1 Emergency Conditions -,
s s s
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TABLE OF CONTENTS . , 1.0 PURPOSE 2.0 REFERS.N CES - 3.0 RESPONSIB' ILITIES 4.0 INITIATING,CONbITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.14 Classification Matrix (1 page) s . s 7 1 TAB A ' Uncontrolled Release of Radioactivity (6 pages) 7.1 \ TAB B sLoss of'RCS Inventory (7 pages)
-7 1 TAB C DNB/ Degraded Core Sequence (4 pages) 7.1 TAB D Loss orssafety Functions (8 pages) 7.1 TAB E Hazar'ds to Station Operation (4 pages) 7 .1 TAB F Natural Phenomena'(4 pages) 7 .'1 TAB G SecuritycCompromise (4 pages) 7.1 TAB H MiscellineousJ(4 pager)
, .s 7.2 .E'xamples. of Emergsney Action Levels (2 pages) 7.3 Emergency Coo'rdinator's Close-Out Checklist (2 pages)
\ 4 LIST OF EFFECTIVE PAGES
.s , s-Title Rellision 1 1-52 Revision 1 s.
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s > s 9 %
, 1 4.
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g - - - Emcrgoney Plan Inplcnonting Instruction EP-1-001 R0sogniticn and Claccification of Rcvisien 1 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 Emergency, and General Emergency. 1.2 This procedure provides an Emergency Coordinator's Close-Out Checklist to verify that all criteria exist to terminate the emergency condition.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 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 l Nuclear Power Plants, Rev. 1 . 2.4 Waterford 3 SES Final Safety Analysis Report 2.5 EP-3-001, Emergency Plan Abstract 2.6 EP-1-010, Unusual Event 2.7 EP-1-020, Alert 2.8 EP-1-030, Site Emergency 2.9 EP-1-040, General Emergency 2.10 OP-903-024, Reactor Coolant System Water Inventory Balance, Rev. 0 2.11 FP-1-010, Fire Emergency Procedure, Rev. 0 2.12 FP-2-200, First Aid and Medical Care, Rev. 0 2
Em:rgoney Plan Inplencnting Instruction EP-1-001 R0 cognition and Classification of Rovision 1 Emergency Conditions 3.0 MespoNsIsILITIrs 3.1 The Nuclear Operations Supervisor-Shift Supervisor / Emergency Coordinator shall be responsible for implementation of this procedure and declaration of the appropriate emergency classifica-tion whenever, in his, judgement, the station status warrants such a declaration. _ .. 3.2 The Nuclear Operations Supervisor-Shift Supervisor shall assume the responsibility and authority of the Emergency Coordinator until such time that he is properly relieved of this duty by the Plant Manager-Nuclear, or his designee, in accordance with EP-3-001, Emergency Plan Abstract. 3.3 If, for whatever reason, the Nuclear Operations Supervisor-Shift Supervisor cannot immediately assume the duty of Emergency Coordinator, the Nuclear Operations Supervisor-Control Room I- Supervisor shall assume the duty of Emergency Coordinator until properly relieved as described in step 3 2. 4.0 INITIATING CONDITIONS - 4 .1 An off-normal event has occurred.or is in progress. 4.2 An action step in a plant operating or emergency operating procedure refers to' this instruction for classification of the indicated plant
, conditions.
i i e e 3
Em;rgoney Plan Impicaanting Instruction EP-1-001 Rccognition and Classification of RGvision 1 Emergency Conditions I l CAUTION ! This instruction does not replace any plant operating procedure. Ensure that any immediate actio'ns (e.g., use of Emergency Procedures) are taken for the proper operation of the plant. During an emergency condition, continue to use the appropriate plant procedures in parallel with this instruction. 5.0 PROCEDURE 5.1 Verify the off-normal ev.ent to ensure that the event is real. 3.2 Match the off-normal event with one of the following eight emergency categories:
. 2 .1 Uncontrolled Release of Radioactivity TAB A 3.2.2 Loss of RCS Inventory TAB B 5.2.3 DNB/ Degraded Core Sequence TAB C 2.4 Loss of Safety Functions TAB D 3.2.5 Hazards to Station Operation T AB E I ,.2.6 Natural Phenomena TAB F 4.27 Security Compromise TAB G 1.2.8 Miscellaneous TAB H l .
4
Em rgoney Plan Impicconting Instruction EP-1-001 Recognition and Classification of Rovision 1 Emergency Conditions NOTE The effects of combinations of initiating events that individually constitute a lower classification condition should be considered as a possibly higher emergency classification. NOTE - If the indicated off-normal condition does not appear to match any of the listed predetermined 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. 5.3 Refer to Attachment 7 1, Classification Matrix, and under the category TAS selected in step 5.2 above, match the off-normal condition with the appropriate Emergency Action Level (EAL) to determine the emergency classification. I l 5.4 Declare the highest emergency classification for which an EAL has been exceeded. 3.5 Perform the emergency actions as outlined in the appropriate Emergency Plan Implementing Instruction, one of which is provided for each classification, as follows: l l 5.5.1 Unusual Event - EP-1-010 i 5.5.2 Alert - EP-1-020 5.5.3 Site Emergency - EP-1-030 3.4 General Emergency - EP-1-040 5
Encrgoney Plan Implementing Instruction EP-1-001 Rocognition and Classification of Rovision 1 Emergency Conditions 5.6 Assessment actions shall be continued, and if necessary, the emergency classification escalated (or downgraded) as more - 4 definitive information becomes available or if the plant conditions change significantly. 57 When the_ Emergency. Coordinator has made the decision to terminate the emergency condition, Attachment 7.3, Emergency Coordinator's Close-Out Checklist, shall be completed to verify that all necessary criteria exist to terminate the emergency condition. 6.0 FINAL CONDITIONS All criteria for close-out of this instruction have been met in ac-cordance with Attachment 7 3, and the initiating conditions which activated this instruction hav'e been declassified to non-emergency status. 7.0 ATT4CHMENTS 7.1 Classification Matrix 71 TAB A Uncontrolled Release of Radioactivity 7.1 TAB B Loss of RCS Inventory l DNB/ Degraded Core Sequence 7.1 TAB C 7 .1 TAB D Loss of Safety Functions 71 TAB E Hazards to Station Operation l l 71 TAB F Natural Phenomena 7.1 TAB G Security Compromise 71 TAB H Miscellaneous 72 Examples of Emergency Action Levels 7.3 Emergency Coordinator's Close-Out Checklist 6
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CLASSIFICATION MATRIX E P-1 -001 Revision 1 7 Attachment 7.1 (1 of 1)
UNCONTROLLED RELEASE OF RADIOACTIVITY UNUSU AL EVENT EAL Any sng of the following conditions:
- 1. Any of the following airborne effluent monitors in valid alarm and release path is not isolated: -
PRM-IRE-0648 Gaseous Waste Management Monitor; at PRM-IRE-0001 Condenser Vacuum Pump Monitor; an ARM-IRE-5107 A Fuel Handling Bldg. Exhaust A Monitor; nr ARM-IRE-5107B Fuel Handling Bldg. Exhaust B Monitor; at PRM-IRE-0100.1S Plant Vent Stack Monitor; at PRM-IRE-0100.2S Plant Vent Stack Monitor; at PRM-IRE-0110 Plant Stack Noble Gas Monitor; at PRM-IRE-0002 Condenser Vacuum Pump Noble Gas Monitor.
- 2. Any of the following liquid effluent monitors in valid alarm and release path is not isolated:
PRM-IRE-0647 Liquid Waste Management Monitor; at PRM-IRE-1900 Circulating Water Discharge Monitor; an PRM-IRE-6775 Dry Cooling Tower Sump #1 Monitor; an PRM-IRE-6776 Dry Cooling Tower Sump #2 Monitor: nc PRM-IRE-677 8 Industrial Waste Sump Monitor.
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EP-1-001 Revision 1 8 Attachment 7.1 TAB A ( / of[ )
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UNCONTROLLED RELEASE OF RADI0 ACTIVITY ALERT dAL Any saa of the following conditions:
- 1. Any of the following airborne effluent monitors reading valid > 10 times alarm setpoint tai release path is not isolated:
PRM-IRE-0648 Gaseous Waste Management Monitor; at PRM-IRE-0001 Condenser Vacuum Pump Monitor; at ARM-IRE-5107A Fuel Handling Bldg. Exhaust A Monitor; nt ARM-IRE-5107B Fuel Handling Bldg. Exhaust B Monitor; at PRM-IRE-0100.1S Plant Vent Stack Monitor; at PRM-IRE-0100.2S Plant Vent Stack Monitor; at PRM-IRE-0110 Plant Stack Noble Gas Monitor; nc PRM-IRE-0002 Condenser Vacuum Pump Noble Gas Monitor.
- 2. Any of the following liquid effluent monitors reading valid > 10 times alarm setpoint and release path is not isolated:
PRM-IRE-0647 Liquid Waste Management Monitor; at PRM-IRE-1900 , Circulating Water Discharge Monitor; at PRM-IRE-6775 Dry Cooling Tower Sump #1 Monitor; at PRM-IRE-6776 Dry Cooling Tower Sump #2 Monitor; at PRM-IRE-677 8 Industrial Waste Sump Monitor. 3 Any Area Radiation Monitor (AAA, AAS) or Process Airborne Monitor (PPP, PII, PGG, PPS, PIS, PGS) " trend" indication on RM-11 console shows a valid, unexplained increase to " full scale." EP-1-001 Revision 1 9 Attachment 7.1 TAB A (JLof[ )
UNCONTROLLED RELEASE OF RADI0 ACTIVITY ALERT
- 4. Any radiological survey results indicating an unexplained increase by a factor of 1000 in direct radiation or airborne contamination levels within the facility.
- 5. NOS-SS opinion that a fuel damage accident with release of ,
radioactivity to Containment or Fuel Handling Building has oc-curred based on reported fuel handling incident verified by alarms on any of the following radiation monitors: ARM-IRE-5107 A FHB Exhaust A Monitor; at ARM-IRE-51073 FHB Exhaust B Monitor; nc ARM-IRE-03 00.2 S FHB Area Radiation Monitor; nc ARM-IRE-03 00.4 S FHB Area Radiation Monitor; at ARM-IRE-0300.1S FHB Area Radiation Monitor; at ARM-IRE-03 00.3 S FHB Area Radiation Monitor; at ARM-IRE-0100S Containment Airborne Monitor; at ARM-IRE-5013 Containment Area Radiation Monitor; at ARM-IRE-5014 Containment Area Radiation Monitor; at l l ARM-IRE-5015 Containment Area Radiation Monitor.
- 6. Steamlinefau$tconcurrentwithsignificantRCStosecondary leakage as determined by:
Uncontrolled decrease in Steam Generator pressure (s) to 1 814 psia as indicated on MS-IPT-0301 AS, (0301BS), ('03 03 AS) , (0303BS), ARD
. PRM-IRE-5500A, (B) Main Steam Line Monitor exceeds HI alarm setpoint.
EP-1-001 Revision 1 10 Attachment 7 1 TAB A (jfofd )
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UNCONTROLLED RELEASE OF RADI0 ACTIVITY SITE AREA EMERGENCY EAL Any sag of the following conditions:
- 1. ARM-IRE-0110 Plant Stack Noble Gas Monitor indicates noble gas release rate > 4.0E5 pCi/sec for 0.5 hr; an > 4.0E6 pCi/sec for 2 minutes.
- 2. Offsite Dose Assessment (CEPADAS/ Manual) projects whole body dose rates at the site boundary > 50 mrem /hr for 0.5 hr; at > 500 mrem /hr for 2 minutes.
- 3. Offsite Dose Assessment (CEPADAS/ Manual) projects thyroid dose
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rates at the site boundary > 250 mrem /hr for 0.5 hr; at > 2500 arem/hr for 2 minutes.
- 4. Radiological monitoring team measures whole body dose rates at the site boundary > 50 mrem /hr for 0.5 hr; nn > 500 mrem /hr for 2 minutes.
- 5. Radiological monitoring team measures thyroid dose rates (equivalent I-131 concentrations) at the site boundary > 250 mrem /hr for 0.5 hr; at > 2500 mrem /hr for 2 minutes. (7 5 E-7
#Ci/ce ; 7 0 E-6 pCi/cc)
- 6. NOS-SS opinion that a major fuel damage accident with release of radioactivity to Containment or Fuel Handling Building has oc-curred based on reported fuel handling incident verified by greater than 10 times alarm setpoint indication on any of the following radiation monitors:
ARM-IRE-5107A FHB Exhaust A Monitor; an ARM-IRE-5107B FHB Exhaust B Monitor; at - ARM-IRE-0300.2S FHB Area Radiation Monitor; sr ARM-IR E-03 00.4 S FHB Area' Radiation Monitor; at EP-1-001 Revision 1 11 Attachment 7.1 TAB A ( IloQ6 )
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UNCONTROLLED RELEASE OF RADI0 ACTIVITY SITE AREA EMERGENCY ARM-IRE-0300.1S FHB Area Radiation Monitor; at ARM-IRE-0300.3S FHB Area Radiation Monitor; at ARM-IRE-0100S Containment Airborne Moni' tor; at ARM-IRE-50*3 Containment Area Radiation Monitor; an ARM-IRE-5014 Containment Area Radiation Monitor; at ARM-IRE-5015 Containment Area Radiation Monitor. 7 Uncontrolled decrease in spent fuel pool water level to below level of irradiated fuel as determined by visual observation of pool level; at L2 on CP-2, FUEL POOL LEVEL LO alarm, concurrent with full scale indication on any two of the following radiation monitors: ARM-IRE-0300.2S FHB Area Radiation Monitor AR M-IRE-03 00.4 S FHB Area Radiation Monitor ARM-IRE-0300.1S FHB Area Radiation Monitor ARM-IRE-0300.3S FHB Area Radiation Monitor
- 8. Steam line fault concurrent with gross RCS to secondary leakage concurrent with indication of failed fuel as determined by:
Uncontrolled decrease in Steam Generator pressure (s) to i 814 psia as indicated on MS-IPT-0301AS, (0301BS), ( 0303 AS) , (0303BS), M PRM-IRE-5500A, (B) Main Steam Line Monitor exceeds HI alarm setpoint. M l l RCS dose equivalent I-131 greater than 1.0 pCi/gm as determined by the most recent isotopic analysis results. EP-1-001 Revision 1 12 Attachment 7 1 TAB A ($'ofh ) i
1 UNCONTROLLED RELEASE OF RADIOACTIVITY GENERAL EMERGENCY l
' l EAL Any 2na of the following conditions:
- 1. Offsite Dose Assessment (CEPADAS/ Manual) projects whole body dose rate at the site boundary 1 1.0 rem /hr us4nz netual meteorciorieni conditions.
- 2. Offsite Dose Assessment (CEPADAS/ Manual) projects thyroid dose rate at the site boundary 15.0 rem /hr usine netuni meteorciorieni conditions.
- 3. Radiological monitoring team measures whole body' dose rate at the site boundary 1 1.0 rem /hr.
4 Radiological monitoring team measures thyroid dose rate (equivalent I-131 concentrations) at the site boundary 1 5.0 rem /hr (1.5 E-5 pCi/cc) . l l EP-1-001 R~evision 1 13 Attachment 7.1 TAB A (6 of6) i l
r LOSS OF RCS INVENTORY UNUSU AL EVENT NOTE There are no instruments which directly measure RCS leakage. Small magnitude RCS leakage is determined via OP-903-024, Reactor Coolant System Water Inventory Balance. The RCS leak rate shall be determined upon detection via increasing indication on any of the following instruments. For RCS to Containment Leaksee ARM-IRE-0100S Containment Atmosphere (Particulate, Iodine, Gaseous) Monitor PT.I.D. A42601 Containment Sump Inlet Flow For RCS to Secondarv Leaksee PRM-IRE-0001 Condenser Vacu'm u Pump Monitor PRM-IRE-010,0 Steam Generator 1 and 2 Blowdown Monitor PRM-IRE-5500A, (B) Main Steam Line Monitors PRM-IRE-0002 Condenser Vacuum Pump Noble Gas Monitor For RCS to CCW Leakare PRM-IRE-7050 AS CCW Monitor A PRM-IRE-7050BS CCW Monitor B PRM-IRE-5700 CCW Monitor A/B EP-1-001 Revision 1 14 Attachment 7.1 TAB B ( / of 7 )
LOSS OF RCS INVENTORY UNUSU AL EVENT ' For Pressurizer Safety Valve Leakage RC-ITI-0107 Pressurizer Relief Line Discharge Temperature RC-ITI-0108 Pressurizer Relief Line Discharge Temperature
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RC-IPI-0116 Quench. Tank Pressure RC-ILI-0116 Quench Tank Level RC-ITI-0116 Quench Tank Temperature 9
^
l I I EP-1-001 Revision 1 15 Attachment 7.1TABB($[off)
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LOSS OF RCS INVENTORY UNUSU AL EVENT EAL
- 1. RCS leakage greater than any naa of the following Technical Specification limits:
(a) Zero pressure boundary leakage (b) 1 spm unidentified leakag (c) 1 gpm RCS pressure isolation valve leakage (d) 1 gpm total primary to secondary leakage or 720 gallons per day through any one Steam Generator (e) 10 gpm identified leakage () EP-1-001 Revision 1 16 Attachment 7 1 TAB B (jf off ) L
LOSS OF RCS INVENTORY ALERT EAL Any sng of the following conditions:
- 1. RCS leakage greater t'han 50 gpm as determined by equilibrium mismatch between charging flow and total letdown flow.
- 2. RCS to secondary leakage greater than 10 gpm concurrent with loss of offsite power as determined by:
Equilibrium charging flow minus total letdown flow > 10 gpm AER PRM-IRE-5500A, (B) Main Steam Line Monitor exceeds HI alarm setpoint. AED Undervoltage alarms (P1 on CP-1 and P3 on CP-1) on both ESF 4 kV Buses. l l EP-1-001 Revision 1 ! 17 Attachment 71TABB(hoff) l l . ._
~-
r l LOSS OF RCS INVENTORY SITE AREA EMERGENCY EAL Any sag of the following conditions:
- 1. RCS to Containment leakage greater than available charging pump capacity (LOCA) as determined by:
4 Uncontrolled decrease in Pressurizer pressure and subcooling margin M Increasing Containment pressure / radiation / temperature / sump levels M No abnormal difference between Steam Generator pressures.
-~
~2. RCS to secondary leakage greater than available charging pump capacity (SGTR) as determined by:
Uncontrolled decrease in Pressurizer pressure and subcooling margin M Uncontrolled decrease in Pressurizer level M PRM-IRE-5500A, (B) Main Steam Line Monitor exceeds HI-HI alarm setpoint. M Steam flow > feedwater flow mismatch or increasing level on af-fected Steam Generator.
. EP-1-001 Revision 1 18 Attachment 7 1 TAB B (31of7 )
LOSS OF RCS INVENTORY SITE AREA EMERGENCY
- 3. RCS to secondary leakage greater than 5'O gpm concurrent with loss of offsite power as determined by:
Equilibrium charging flow minus total letdown flow > 50 gpm AED. PRM-IRE-5500A, (B) Main Steam Line Monitor exceeds HI alarm setpoint. AED. Undervoltage alarms (P1 on CP-1 and P3 on CP-1) on both ESF 4 kV Suses. 1 4 l t
. EP-1-001 Revision 1 19 Attachment 7.1TABB(dhoff)
LOSS OF RCS INVENTORY GENERAL EMERGENCY EAL Any sna of the following conditions:
- 1. Any loss of coolant accident and subsequent failures of Emergency Core Cooling Systems such that, in the opinion of the NOS-SS, a Core Melt Sequence is in progress, or imminent, and the ultimate failure of Containment is likely.
- 2. Any loss of coolant accident and subsequent failures of Containment Heat Removal Systems such that, in the opinion of the NOS-SS, a Core Melt Sequence is in progress, or imminent, and the ultimate failure of Containment is likely.
EP-1-001 Revision 1 20 Attachment 71TABB([off)
.g ~ .e gm- '- :"
I 1 DNB/ DEGRADED CORE SEQUENCE UNUSUAL EVENT , EAL Any sna of the following conditions:
- 1. Valid SIAS actuation and saf'ety injection flow indicated on SI-IFI-0311, (0321), (0331), (0341 ). '
- 2. Rapid secondary depressurization due to steam line break or secondary safety / relief valve failure or coldwater injection as determined by: ,
Uncontrolled decrease in Steam Generator pressure (s) to 1 814 psia as indicated on MS-IPT-0301AS, (0301BS), ( 0303 AS) , ( 0303 BS) . . 3 Abnormal coolant temperature and/or pressure or abnormal fuel temperature as determined by: (a) DNBR less than 1.20 as indicated by Core Protection Calculators; at (b) Peak linear heat rate greater than 21.0 kW/ft as indicated by Core Protection Calculators; at (c) RCS less than 20 degrees subcooled and RCS Tavg greater than 350 degrees F.
- 4. Fuel damage detected by LETDOWN ACTIVITY HI alarm, D1 on CP-4, and verified by isotopic analysis indicating an l increase in failed fuel greater than 0.1 percent in 3.0 minutes.
- 5. RCS pressure greater than 2750 psia.
( l t
. EP-1-001 Revision 1 21 Attachment 71TABC(/off)
DNB/ DEGRADED CORE SEQUENCE ALERT EAL Any sna of the following conditions:
- 1. Severe loss of fuel cladding verified by isotopic analysis indicating an increase in failed fuel greater than 1.0 percent in 30 minutes or total failed fuel greater than 5.0 percent.
- 2. RCS chemistry sample results indicate dose equivalent I-131 greater than 300 pCi/ml and NOS-SS opinion that sample results are not due to iodine spiking phenomenon.
- 3. Reactor Coolant Pump shaft seizure leading to fuel failure as determined by:
Reactor Trip on Low Flow and DNBR Low M DNBR less than 1.20 as indicated by Core Protection Calculators M A3, (AS), (A7), on CP-2, REACTOR CLG PUMP TRIP / TROUBLE alarm M Computer alarm, FT. I.D. D13202, (13402), (13602). (13802), RCP MTR OVERCURR/OVERLD TRIP l 352 Increasing selected isotope activity on RPM-IRE-0202, Letdown Process Radiation Monitor. EP-1-001 Revision 1 22 Attachment 71TABC(I-of)
DNB/ DEGRADED CORE SEQUENCE SITE AREA EMERGENCY EAL-
- 1. NOS-SS opinion that a " degraded core with possible loss of coola-ble geometry" condition exists based on consideration of the following:
(a) Adequacy of core cooling. (b) Reactor coolant activity sample results. (c) Containment radioactivity levels. O
/
EP-1-001 Revision 1 23 Attachment 7.1TABC(sfoff)
~ '
DNB/ DEGRADED CORE SEQUENCE GENERAL EMERGENCY 4 EAL
- 1. Loss of core heatsink such that, in the opinion of the NOS-SS, a Core Melt Sequence is in progress, or imminent, and the ultimate failure of Containment is likely based on determination of either of the following:
(a) Transient initiated by loss of all normal feedwater capability followed by failure of all emergency feedwater capability for extended period; DH (b) Loss of all offsite power and failure of both Emergency Diesel Generators and f ailure of steam-driven Emergency Feedwater Pump for extended period.
- , EP-1-001 Revision 1 24 Attachment 71TABC(foff)
LOSS OF SAFETY FUNCTIONS UNUSUAL EVENT EAL Any ang of the following cond'itions:
- 1. Loss of all offsite ac power as determined by receipt of undervoltage alarms (P1 on CP-1 a'nd P3 on CP-1) on both ESF 4 kV Buses.
- 2. Loss of operability of both Emergency Diesel Generators.
- 3. Loss of any of the following assessment capatility for greater than 15 minutes:
Both trains of plant computer; at Safety Parmneter Display System; at All meteorological instrumentation.
- 4. Loss of the following emergency communications capability: '
Operational Hotline at NRC Emergency Notification System.
- 5. Technical Specification Required Shutdown due to loss of Radiological Monitoring System.
- 6. Technical Specification Required Shutdown due to loss of engineered safety feature or fire protection system function.
7 Technical Specification Required Shutdown due to loss of Containment integrity. l l l EP-1-001 Revision 1 25 Attachment 7.1 TAB D ( /ofh ) 1
LOSS OF SAFETY FUNCTIONS ALERT EAL Any sag of the following conditions:
- 1. Loss of all offsite ac power concurrent with failure of both Emergency Diesel Generators as determined by:
P1 on CP-1, 4 kV BUS SA VOLTAGE LOST; LEE P3 on CP-1, 4 kV BUS SB VOLTAGE LOST; AER Buses remain deenergized for greater than 1 minute. (See TAB D " Site Emergency" Condition 1 for extended loss)
- 2. Loss of all onsite vital de power as determined by:
N8 on CP-35, BATTERY SA LOST / GROUND; LEE N9 on CP-35, BATTERY SAB LOST / GROUND; AHA N10 on CP-35, BATTERY SB UV/ GROUND; AEH Buses remain deenergized'for greater than 1 minute. (See TAB D " Site Emergency" Condition 2 for extended loss) 3 Loss of the ability to achieve or maintain Cold Shutdown due to any of the following: , (a) Inability to borate to Mode 5 Shutdown Margin of 2.0% Ak - at (b) Loss of both Shutdown Cooling trains; or, (b) Loss of both essential CCW/ACCW trains.
. 4. Reactor remains critical after receipt of RPS or manual trip l signal.
1 l EP-1-001 Revision 1 26 Attachment 71TABD(Ioff)
LOSS OF SAFETY FUNCTIONS ALERT
- 5. Most or all control Room innunciators lost as determined by visual observation.
- 6. Evacuation of Control Room anticipated or required with control of ,
shutdown systems established from local stations. l t l l l l l
. EP-1-001 Revision 1 27 Attachment 7.1TABD(/of[)
LOSS OF SAFETY FUNCTIONS
~
SITE AREA EMERGENCY EAL Any sng of the following conditions: ,
- 1. Loss of all offsite ac po.wer concurrent with failure of both Emergency Diesel Generators for greater than 15 minutes as determined by:
P1 on CP-1, 4 kV BUS SA VOLTAGE LOST; AHa P3 on CP-1, 4 kV BUS SB VOLTAGE LOST; ARD Buses remain deenergized for greater than 15 minutes.
- 2. Loss of all onsite vital de power for greater than 15 minutes as determined by:
N8 on CP-35, BATTERY SA LOST / GROUND; AER N9 on CP-35, BATTERY SAB LOST / GROUND; AER N10 on CP-35, BATTERY SB. LOST / GROUND; AMA Buses remain deenergized for greater than 15 minutes. 3 Loss of the ability to achieve or maintain Hot Shutdown due to any of the following: (a) Inability to borate to Mode 4 Shutdown Margin of 5.15% Ak/k; DL (b) Loss of both Steam Generators as an effective heatsink; nr (c) Inability to maintain natural circulation when forced flow is not available; at (d) Inability to make up RCS volume.
. EP-1-001 Revision 1 28 Attachment 71TABD(ylofh)
i , LOSS OF SAFETY FUNCTIONS
, SITE AREA EMERGENCY
- 4. Transient requiring operation of shutdown systems with failure to scram with no core damage immediately evident as determined by:
s NOTE If evidence of core damage exiscs, a General Emergency must be declared immediately. (a) Two or more like RPS trip channels have reached or exceeded the trip setpoint AH2 (b) Reed Switch Position Transmitters indicate 10 or more FLCEA's not fully inserted AH2 (c) No indication of core damage AE2 ' (d) NOS-SS opinion that'a transient is in progress. S'. Most or all Control Room annunciators lost and NOS-SS opinion that transient which jeopardizes reactor safety is in progress.
~ - '6., Evacuation of Control Room required with control of shutdown systems.EQI established from local stations within 15 minutes.
1 i h
. EP-1-001 Revision 1 29 Attachment 7 1 TAB D (JIof9 )
3-
LOSS OF SAFETY FUNCTIONS GENERAL EMERGENCY EAL Any ang of the following conditions:
- 1. NOS-SS opinion that a cross loss of any two of the three fission product barriers has occurred and plant conditions are such that a potential for the loss of the third barrier exists based on consideration of the following:
FOR TME 1 st BARRIER - FUEL CLADDING A. Conditions indicating a potential loss of fuel cladding can be determined by: ,
- 1. Violation of DNBR due to loss of RCS flow at loss of RCS subcooling margin an abnormally high fuel temperatures.
~
- 2. Inadequate core cooling due to loss of core heatsink at core flow blockage nn LOCA concurrent with failure of ECCS.
B. Conditions indicating a loss of fuel cladding can be determined by:
- 1. Fission product activity in the reactor coolant.
FOR THE 2nd BARRIER - RCS PRESSURE BOUNDARY l A. Conditions indicating a potential loss of the RCS pressure boundary can be determined by:
- 1. RCS overpressure transient due to loss of core heatsink l nn reactor power excursion an transient requiring opera-l tion of shutdown systems with failure to scram. .
B. Conditions indicating a loss of the RCS pressure boundary can be determined by: EP-1-001 Revision 1 30 - Attachment 7.1 TAB D ( h od3 )
LOSS OF SAFETY FUNCTIONS GENERAL EMERGENCY
- 1. Decreasing RCS pressure and increasing Containment pressure / radiation / temperature / sump levels and no abnormal difference between Steam Generator pressures '
(LOCA).
- 2. Decreasing RCS pressure and increasing radiation on Main Steam Line Monitors and steam flow > feedwater mismatch or increasing level on affected Steam Generator (SGTR).
FOR THE 1rd BARRIER - CONTATNMENT A. Conditions indicating a potential loss of containment can be
- determined by
- 1. Steam line break inside Containment concurrent with failure of Containment Heat Removal Systems.
-2 . LOCA concurrent with failure of Containment Heat Removal Systems.
3 Post-LOCA hydrogen generation concurrent with failure of Hydrogen Removal Systems. B. Conditions indicating a loss of containment can be determined by:
- 1. LOCA or steam line break followed by rapidly increasing l
, pressure in the Shield Building annulus (primary I -
Containment to Shield Building fault).
- 2. Pressure in one Steam Generator continues to decrease following actuation of MSIS with Containment pressure not increasing (SLB between Containment and MSIV).
- 3. MSIV position indication shows MSIV not fully closed following actuation of MSIS.
- 4. Multiple Containment Isolation Valve failures creating a release path from Containment to outside atmosphere.
EP-1-001 Revision 1 31 Attachment 7.1TABD(fof%)
- - - - -- w- -
LOSS OF SAFETY FUNCTIONS GENERAL EMERGENCY j l I
- 2. Transient requiring operation of shutdown systems with failure to scram and, in the opinion of the NOS-SS, a Core Melt Sequence is in progress, or imminent, as determined by:
Two or more like RPS trip channels have reached or exceeded the trip setpoint. M
^
Reed Switch Position Transmitters indicate 10 or more FLCEA's not fully inserted. M Opinion of the NOS-SS that a Core Melt Sequence is in progress, or imminent, i l l l r l l l
. EP-1-001 Revision 1 32 Attachment 7.1TABD(hof[)
HAZARDS TO STATION OPERATION UNUSUAL EVENT CAL Any saa of the following conditions:
- 1. Observation of fire within the plant which lasts longer than 10 minutes at any fire within the owner-controlled area which requires offsite fire fighting assistance.
- 2. Aircraft crash onsite but outside protected area.
- 3. Train derailment onsite.
- 4. Near or onsite explosion.
- 5. Near or onsite release of toxic or flammable gas.
EP-1-001 Revision 1 33 Attachment 7.1 TAB E ( / ofI! )
BAZARDS TO STATION OPERATION ALERT SAL Any sng of the following conditions:
- 1. Fire within the plant which potentially affects safety systems.
- 2. Aircraf t crash or missile impact inside the protected area.
3 Known explosion damage to the facility which degrades the level or safety of the plant.
- 4. Uncontrolled entry into protected area environs of toxic *or flam-mable gas such that a Protected Area Evacuation is required.
- 5. Massive turbine rotating component f ailure causing casing penetration and projection of turbine blading.
. EP-1 -001 Revision 1 34 Attachment 71TABE(yloff)
HAZARDS TO STATION OPERATION SITE AREA EMERGENCY EAL Any s.ng of the following conditions:
- 1. Fire within the plant which actually compromises the functions of safety systems.
- 2. Aircraf t crash or missile impact or explosion causes major damage to vital equipment.
- 3. Uncontrolled entry of toxic or flammable gas into facility environs such that a Site Evacuation is required.
e l t
. EP-1-001 Revision 1 35 Ittachment7.1 TABE(doff)
HAZ ARDS TO STATION OPERATION GENERAL EMERGENCY
. AL
- 1. Any major hazard which causes massive common damage to plant systems such that, in the opinion of the NOS-SS, a Core Melt Sequence is in progress, or imminent, and the ultimate failure of Containment is likely.
O e EP-1-001 Revision 1 36 Attachment 71TABE(forf)
NATURAL PHENOMENA UNUSUAL EVENT EAL Any sna of the following conditions:
- 1. Any earthquake felt in-plant cr valid receipt of L10 (on CP-7),
SEISMIC RECORDERS IN OPERATION alarm.
- 2. Any in-plant flooding condition which, in the opinion of the NOS-SS, potentially degrades the level of safety of the plant; at river water level at intake structure > +24 ft. MSL.
- 3. Any tornado onsite.
- 4. Site comes under a hurricane warning.
i 1 l i l
. EP-1-001 Revision 1 37 Attachment 7 1 TAB F ( /off )
i l l
NATURAL PHENOMENA ALERT EAL Any sna of'the following conditions:
- 1. Earthquake recording > 0.05 g ground acceleration nr. valid receipt of M10 (on CP-7), SEISMIC EVENT alarm.
- 2. Hurricane surge or other in-plant flooding condition which, in the opinion of the NOS-SS, actually degrades the level of safety of the plant; 2L river water level at intake structure > +27 ft. MSL.
- 3. Any tornado striking the protected area.
- 4. Site experiencing sustained hurricane force winds (74 mph).
EP-1-001 Revision 1 38 Attachment 7 1 TAB F (jloy ) 4
NATURAL PHENOMENA SITE AREA EMERGENCY
'E Any sna of the following conditions:
- 1. Earthquake recording > 0.1 g ground acceleration.
- 2. Hurricane surge or other in-plant flooding condition which causes actual failure of vital equipment; at river water breaching the levee (EL. +30 ft. MsL).
- 3. Tornado causes major damage to vital equipment.
4 Hurricane with wind gusts exceeding 200 mph. O O EP-1-001 Revision 1 39 Attachment 71TABF(jfof[)
,m_ __-.--- , . -
NATURAL PHEONOMENA GENERAL EMERGENCY AL ,
- 1. Any major natural phenomenon which causes massive common damage to plant systems such that, in the opinion of the NOS-SS, a Core Melt Sequence is in progress, or imminent, and the ultimate failure of Containment is likely.
l l -
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SECURITY COMPROMISE UNUSUAL EVENT LL
- 1. Any security threat, attempted entry or attemped sabotage such that Security notifies the NOS-SS of initiation of the Security Contingency Plan.
e e O e EP-1-001 Revision 1 - 41 Attachment 7.1 TAB G ( / off )
,-,w& ,--,,---aW g y- -.,--, , - - e--- -r,-- 2--rav w- -, -=w --+> e--
SECURITY COMPROMISE ALERT CAL
- 1. NOS-SS notified by Security of an ongoing security compromise in the plant, but not to vital areas as defined in the Security Contingency Plan.
p' yee 4 6 d EP-1-001 Revision 1 42 Attachment 7.1TABG(/o )
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SECURITY COMPROMISE SITE AREA EMERGENCY
. AL
- 1. Imminent loss of physical security control of the plant.
1 e I i i l l . EP-1-001 Revision 1 . 43 Attachment 71TABG(Io )
, - - - ,wmen-4 y w--r,, ---,w w.- .,_,e-,_ -,-_
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SECURITY COMPROMISE GENERAL EMERGENCY
.L
- 1. Loss of physical security control of the plant.
l' e.. s f 1 e i e EP-1-001 Revision 1 44 Attachment 7 1 TAB G (f or
)
MISCELLANEOUS UNUSU AL EVENT i _AL Any sng of the following conditions:
- 1. Transportation of contaminated injured individual from site to offsite hospital.
- 2. Other plant conditions exist that, in the opinion of the NOS-SS, warrant increased awareness on the part of the plant operating staff or state or local authorities; at require plant shutdown under technical specification requirements; at involve other than normal controlled shutdown.
M EP-1-001 Revision 1 45 Attachment 7.1TABH([off)
MISCELLANEOUS ALERT c.AL
- 1. Other plant conditions exist that, in the opinion of the NOS-SS, warrant precautionary activation of Technical Support Center and placing Emergency Operations Facility and other key emergency personnel on standby.
I i l i EP-1-001 Revision 1 46 Attachment 71TABH(o2.off)
MISCELLANEOUS SITE AREA EMERGENCY ukL
- 1. Other plant conditions exist that, in the opinion of the NOS-SS, warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site.
W 9 EP-1-001 Revision 1 47 Attachment 71TABH([of )
^
MISCELLANEOUS GENERAL EMERGENCY CAL
- 1. Other plant conditions exist that, in the opinion of the NOS-SS, could result in a Core Melt Sequence or a release of radioactivity to the envir'onment such that resultant dose at the site boundary could reach or exceed the EPA Protective Action Guidelines of 1.0 rem whole body or 5 rems to the thyroid.
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EMERGENCY C00RDINRTOR'S CLOSE-0UT CHECKLIST . INSTRUCTION
- 1. This checklist shall be used by the Emergency Coordinator to evaluate a decision to terminate 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 vital equipment necessary to maintain the plant in a stable configuration is operable.
l S. Fires are extinguished; flooding conditions and any other site damage are under control.
- 6. All vital areas requiring occupancy are j habita ble.
- 7. Site security control is established.
l 8. , Contaminated injured personnel have been j- transported to a hospital. l EP-1-001 Revision 1 51 Attachment 7 3 ( /ofl- )
EMERGENCY' COORDINATOR'S CLOSE-0UT CHECKLIST CRITERIA CRITERIA MET (Initials)
- 9. All implementing procedures, activated on'At-tachment 7.2, 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 t I EP-1-001 Revision 1 52 Attachment 7.3 (clof 2 )
F WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA MtOOLE SOUTH UT1UTIES SYSTEM EP-1-010 POM VOLUME 1o REVISION 1 PCM SECTION 1 APPROVAL DATE: EFFECTIVE DATE: EMERGENCY PLAN IMPLDIENTING INSTRUCTION IJNUSUAL EVENT LP&L W-3 RECORDS CONTROLLED COPY NO. ^90 PORC Mee".ng No. 73- 2, 3 \ Reviewed W_ _ bkC chairmatt i Approved: c ', /Ar. Plant Manager-Nuclear
WATERFORD 3 SES
~^
PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. / - /-l' IO - Ti tl e *ll'h!5at b ': %5" ' ~ ~ - - - ~ ~ - Effective Date (if different from PM-N approval date) Camolete '1. B. or C A. Change No. Ml.1 B. Revision No. l C. Deletion /v/ 7 9C ARON 20R CM1NGE. REVISION. OR DELETION E9d u Md doown bhlls - Oam A b- 6 kCrckiLv; SO N/dedi - -- d-U:-Q t kr M r%mur Esv_v es m vtanus tu -Exo_dur-g . - 6 a s J REcuTFED SIGNATifR [I A - Date 'I -- ---- Originator Technical Reviewv - N b M 4
- 'Da te - I M- E L- - -
SAFETY EVALUATION Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR?
c-
- 2. Change the procedures as described in the FSAR? v
- 3. Conduct tests / experiments not described in the FSAR?
l-
- 4. Create a condition or conduct an operation which ex- &
ceeds, 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 Safet- Evaluation checklist. Safety Evaluation bb - - - - Date - ! l-l 9- 6 ' - Group /Dep't. Head Review ONl - Date Il-17'Y ~~ 0 i Temporary Approvals -- - - -- Date - (NOS) Temporary Approval * - -' - -
-- Date - - - - ---
QC Revieu & W E -,: U W -- - - -----* Date * & O - O ~--- PORC Review \ b k k b Date I-l' '-I3 Meeting No. -f3 '#/ A-- Plant ManagerbN uclear Appro'u al NNh-Nr --- - Date NOkh3 - - - -
' Temporary approval must be followed by Plant Manager-Nuclear approval i, within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
-----p,a y - --m y- , ,-.
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Emergency Plan Implementing Instruction EP-1-010 l Jnusual Event Revision 1-l l 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 Additicnal Response Guidelines (1 page) LIST OF EFFECTIVE PAGES Title Revision 1 1-7 Revision 1 1 g .p 7.-e. --.-w --
., y7,, . . - . . ., ,, _.
Emergency Plan Implementing Instruction .EP-1-010 Unusual Event Revision 1 1.0 PURPOSE To outline the actions to be taken for an emergency condition at the Unusual Event Level. _ s
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-1-001, Recognition and Classification of E=ergency Conditions 2.3 EP-3-050, Emergency Response Call List 2.4 EP-1-020, Alert 2.5 EP-1-030, Site 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 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 Records 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 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, 2
i
+
Emergency Plan Implementing Instruction EP-1-010 Unusual Event Revision 1 4 . 2. At the direction of the Emergency Coordinator. 5.0 PROCEDURE 51 Sound the appropriate alarm as necessary: 5.1.1 Fire 5.1.2 Station 5.2 H:ke the following announcement (s): 5.2.1 Attention a11 ' 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 furthe.< instruction is giv e'n . The maintenance radio frequency'is now dedicated for I 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. 5.2.3 Repeat the3 announcement (s). 5.3 Make initial contact with Plant Manager-Nuclear. NOTE See Er.ergency Respense Organization Status
' Board for name snd phone r.umtars; also .see EP-3-050.
s 5.3.1 Dial the Plant Manager-Nuclear'::home' phone number. If during the day, dial his work number. . 5 3.2 Ifcontactcannotbeestablishedinsjep5.3.1, then dial the Plant Manager-Huclear's mobile telephone number. K 3
Emergency Plan Implementing Instruction EP-1-010 Unusual Event Revision 1 5.3.3 If contact cannot be established in step 5.3 2, then contact the Operations and Maintenance Assistant Plant Manager-Nuclear using steps 5.3.1 to 5.3.2. 5.3.4 If the Operations and Maintenance Assistant Plant Manager-Nuclear cannot be contacted, then contact the Operations Superintendent. 5.3.5 Upon contact with one of the above individuals, discuss the following: 5.3.5.1 Nature of situation 5.3.5.2 classification 5.3.5.3 Action taken or to be taken 5.3.5.4 Need to activate emergency response facilities 5.3.5.5 Ensure that the Vice President-Nuclear Operations is contacted. 5.4 If activation of 30-minute responders is necessary, then provide the Emergency Communicator with the proper pre-recorded cassettes or complete Attachment 7.3 of EP-2-010, Answering Machine Message, and direct the Emergency Communicator to activate the 30-minute responder Emergency Pager System in accordance with EP-2-010, At-tachment 7.2. 5.5 Complete Attachment 7 5 of EP-2-010, Initial Notification Form, and provide to the Emergency Communicator. Direct that he/she commence initial offsite notifications in accordance with EP-2-010 and inform him/her which notifications should be made. 5.5.1 St. Charles Parish Emergency Operations Center (EOC) 5.5.2 St John the Baptist Parish EOC > 5.5.3 Louisiana Nuclear 12.ergy Division (LNED) 5.5.4 Louisiana Office of Emergency Preparedness (LOEP) 5.5.5 Waterford 1 and 2 4 l
Emergency Plan Implementing Instruction EP-1-010
'Jnusual Event Revision 1 5.5.6 Middle South Utilities 5.5.7 U.S. Coast Guard 5.5.8 Missouri Pacific Railroad 5.5.9 American Nuclear Insurers (ANI) 5.5.10 Nuclear Regulatory Commission (NRC) 5.6 As additional information becomes available, update the Emergency Communicator by completing Attachment 7.7 of EP-2-010, Follow-Up Notification, and direct the Emergency Communicator to conduct additional updates to offsite agencies in accordance with EP-2-010 on a continual basis.
5.7 If activation of the TSC and OSC is necessary, then direct that the Emergency Communicator activate the 1-hour responder Emergency Pager System in accordance with EP-2-010, and ensure that EP-2-100 and EP-2-101 are implemented. 5.8 Ensure that logs / records are kept in accordance with EP-2-150. 59 Direct a Health Physics Technician to initiate in-plant radiological controls in accordance with EP-2-031 if a real or potential l radiological hazard exists. 5.10 Initiate any additional response measures in accordance with applicable emergency procedures listed on Attachment 7.1. l 5.11 As conditions change, periodically check EP-1-001 to determine l whether reclassification is necessary. l l 5.11.1 If reclassification is necessary, then reclassify the emergency ! in accordance with EP-1-001 and implement appropriate l ! Implementing Instruction EP-1-020, EP-1-030, or EP-1-040. 5.11.2 If closecut is appropriate, then close out the emergency with a ,
- verbal summary to all agencies / personnel as indicated on At- ;
( tachment 7 13 of EP-2-010. l 5 L
Emergency Plan Implementing Instruction EP-1-010 Unusual Event Revision 1 6.0 FINAL CONDITIONS 6.1 Oncoming Emergency Coordinator contacted. 6.2 Initial offsite notifications initiated. 63 The Unusual Event has been closed out with normal station administration resumed or the emergency is reclassified. 7.0 ATTACHMENTS 71 Procedure Reference for Additional Response Guidelines P O 6
PROCEDURE REFERENCE FOR ADDITIONAL RESPONSE GUIDELINES Topic Reference Personnel EP-2-020, Contaminated Injured /Ill Personnel EP-2-030, Emergency Radiation Exposure Guidelines and Controls EP-2-032, Monitoring and Decontamination EP-2-081, Search and Rescue Toxic, Gas, Train EP-2-110, Man-Caused Emergencies Derailment, Airplane Crash, Explosion, Transportation i Accidents Tornado, Hurricane, EP-2-120, Natural Emergencies Flood Radiation Releases EP-2-060, Radiological Field Monitoring Emergency Facil.ities EP-2-102, Emergency Operations Facility (EOF) Activation, Operation and Deactivation Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentry EP-2-170, Recovery EP-3-050, Emergency Response Call List EP-3-060, Emergency Communications Guidelines EP-1-010 Revision 1 7 Attachment 7.1 (1 of 1)
WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA MiocLE south UTluTES SYSTEM
- EP-1-020 POM VOLUME 18 REVISION 1 FCM SECTION 1 APPROVAL DATE:
EFFECTIVE DATE: EMERGENCY PLAN IMPLEMENTING INSTRUCTION ALERT t.P&t.W-3 RECORDS CONTROLLED
. COPY
,.a n n e .
PORC Meeting No, f3 tJd i Reviewed: CRC Chairman y Approved: 'J l o.' l{. .;s- d Plant Manager-Nuclear
WATERFORD 3 SES
'N PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. -
-l-US Title - lc tb - ' - - ~ - - ~ ~ - - - - - - -
Effective Date (if different from PM-N approval date) Cbmnlete 1. B. o r- C A. Change No. MM - B. Revision No. / C. Deletion d1 921 SON FOR CM1NOE. REVISION. OR DELETION h &[ w y / i b, , a b.i < lr; /4- / fun /- h lr-hizr ?r'r.. n: m/h'-:Us& - r/, r :,, sh vc (k m .'y.N A., n; !,, / h y,, ,y / n~; Gray-lb - -- --
*/ 7 4 W REOUTRED SIGNATURPS Originator k 'l b 3'm
- Date d'Ibb- ---
Technical ReviYwu --k bib - -' - Date O'N 4 L - '- J SAFETY EVALUATION
,. Does this change, revision, or deletion: YES NO
- 1. 6
~
Change the facility as described in the FSAR?
- 2. Change the procedures as described in the FSAR? L
- 3. Conduct tests / experiments not described in the FSAR7 b
4 Create a condition or conduct an operation which ex- V ceeds, 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 Saf t- Evaluation checklist. Safety Evaluation k b - -- - Date N 'E ' - Group /Dep't. HeadRev0ew 'S ObGM -- Date'II'I9'El- - l \ l l Temporary Approva18 - -- - - - - Da te - - (NOS) Temporary Approval
- Date - -
QC Revieu - A W Y $ N - & * -
------- Date - */~/ T d'iE* ---
i PORC Review h bb Date d 3 5 '-- Meetin N o . - f f ',9 8- - Plant ManagerSNuclear Approval - bMwb--~~- Date E IV - - - -
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
l UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1) l
Emergency Plan Implementing Instruction EP-1-020 Alert Revision 1 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 1 1-7 Revision 1 I 1
. _ _ = , , _ _ _ _ - _ _ . _ _ _ _ _ _ _ _ __
Emergency ~ Plan Implementing Instruction EP-1-020 Alert Revision 1 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 Classification of Emergency Conditions 2.3 EP-1-010, Unusual Event 2.4 EP-1-030, Site Emergency 2.5 EP-1-040, General Emergency 2.6 EP-2-010, Notifications and Communications 27 EP-2-031, In-Plant Radiological Controls During Emergencies 2.8 EP-2-050, Offsite Dose Assessment (Manual) 2.9 EP-2-051, Offsite 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 Records 2.15 EP-3-050, Emergency Response Call List 3.0 R ES PON SIB ILITIES The Emergency Coordinator is responsible for ensuring that the actions outlined in this procedure are carried out. 2
Emergency Plan Implementing Instruction EP-1-020 Alert Revision 1 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 appropriate alarm as necessary: 5.1.1 Fire 5.1.2 Station 5.2 Make the following announcement (s): 5.2.1 Attention all personnel; attention all personnel. An Alert has been declared. All members of the Technical Support Center and the Operational Support Center report to your stations. All other personnel await further instructions. (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 (e.g., fire), announce its type and location, and instruct personnel to stand clear of this area. 5.2 3 Repeat the announcement (s). 53 Make initial contact with the Plant Manager-Nuclear. NOTE See the Emergency Response Organization Status Board for names and phone numbers; also see EP-3-050. 3
Emergency. Plan Implementing Instruction EP-1-020 Alert Revision 1 5.3.1 Dial the Plant Manager-Nuclear's home phone number. If during the day, dial his work number. 5.3 2 If contact cannot be established in step 5 3 1, then dial the Plant Manager-Nuclear's mobile telephone number. 5.3 3 If contact cannot be established in step 5.3.2, then contact the Operations and Maintenance Assistant Plant Manager-Nuclear using steps 5.3.1 and 5.3.2. 5.3.4 If'the Operations and Maintenance Assistant Plant Manager-Nuclear cannot be contacted, then contact the Operations Superintendent. 5.3.5 Upon contact with one of the above individuals, discuss the , following: 5.3.5.1 Nature of the situation 5.3.5.2 Classification 4 5 3 5.3 Action taken or to be taken 5 3.5.4 Need to activate emergency response facilities 5 3.5.5 Ensure that the Vice President-Nuclear Operations is contacted. 5.4 Provide the Emergency Communicator with the proper pre-recorded cassettes or complete Attachment 7.3, Answering Machine Message, of EP-2-010. Direct the Emergency Communicator to activate the 30-minute responder and 1-hour responder Emergency Pager Systems in accordance with Attachment 7 2 of EP-2-010. 5.5 Complete Attachment 7 5, Initial Notification Form, of EP-2-010 and provide it to the Emergency Communicator. Direct that he commence initial offsite notifications in accordance with EP-2-010 and inform him of which of the following notifications should be made. 5.5.1 St. Charles Parish Emergency Operations Center (EOC) 4 5.5.2 St. John the Baptist Parish EOC i 4
Emergency Plan Implementing Instruction EP-1-020 Alert Revision 1 5.5 3 Louisiana Nuclear Energy Division (LNED) 5.5.4 Louisiana Office of Emergency Preparedness (LOEP) 5.5.5 Waterford 1 and 2 5.5.6 Middle South Utilities 5.5.7 U.S. Coast Guard 5.5.8 Missouri Pacific Railroad 5.5 9 American Nuclear Insurers (ANI) 5.5.10 Institute of Nuclear Power Operations (INPO) 5.5.11 Nuclear Regulatory Commission (NRC) 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 offsite agencies in accordance with EP-2-010 on a continual basis. 5.7 Initiate offsite 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 ac-cordance with EP-2-052, Protective Action Guidelines. 5.8 If radiological releases are occurring, instruct the Health Physics Coordinator to activate Radiological Field Monitoring Teams in ac-cordance with EP-2-060. 5.9 Activate the Technical Support Center in accordance with EP-2-100, 5.10 Activate the Operational Support Center in accordance with EP-2-101. 5.11 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 potential radiological hazard exists. 5
Emergency Plan Implementing Instruction EP-1-020 Alert Revision 1 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 Ensure that Technical Advisors are dispatched to local Parish Emergency Operations Centers. 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 emergency in accordance with EP-1-001 and implement the appropriate Emergency Plan Implementing Instruction: EP-1-010, EP-1-030 or EP-1-040. 5.15.2 If closecut is appropriate, then close out the emergency with a verbal summary to all agencies / personnel as indicated on At-tachment 7.13 of EP-2-010. 6.0 FINAL CONDITIONS 6.1 The oncoming Emergency Coordinator is contacted. 6.2 The EOF Director is contacted. 6.3 Initial offsite notifications are initiated. 6.4 The Alert has been closed out with normal station administration resumed or the emergency is reclassified. 7.0 ATTACHMENTS 7.1 Procedure Reference for Additional Response Guidelines 6
I l PROCEDURE REFERENCE FOR ADDITIONAL RESPONSE GUIDELINES 1 Tooic Reference Personnel EP-2-020, Contaminated Injured /Ill Personnel EP-2-030, Emergency Radiation Exposure Guidelines and Controls EP-2-032, Monitoring and Decontamination EP-2-081, Search and Rescue Toxic Gas, Train EP-2-110, Man-Caused Emergencies Derailment, Airplane Crash, Explosion, Transportation Accidents Tornado, Hurricane, EP-2-120, Natural Emergencies Flood Emergency Facilities EP-2-102, Emergency Operations Facility (EOF) Activation, Operation, and Deactivation Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentry EP-2-170, Recovery EP-3-001, Emergency Plan Abstract EP-3-050, Emergency Response Call List EP-3-060, Emergency Communications Guidelltas EP-t-020 Revision 1 7 Attachment 7 1 (1 of 1)
WATERFORD 3 SES
, PLANT OPERATING MANGAL E
I OUISIANA POWER & LIGHT UTlUTIES SYSTEM EP-1-030 POM VOLUME 18 REVISION 1 PCM SECTION 1 APPROVAL DATE: EFFECTIVE DATE: I DiER0ENCY PLAN IMPLDIENTING INSTRUCTION SITE EMERCENCY LP&L W-3 RECORDS CONTROLLED COPY NO. OS $ - . PORC Meecing No, f3fJJ g Reviewed:
? ~ Cha1 pan i
.. 1 l
Approved: '}- .L a .h Plant Manager-Nuclear l
WATERFORD 3 SES m PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. h~ l'8 SC ' Ti tl e Irh -lank'dd - - --^- - - -^- - Effective Date (ifdifferentfrbmPM-Napprovaldate) Comniete 1. B. or C A. Change No. M4 B. Revision No. / C. Deletion AM 9EASON POR CM1NGE. REVISION. OR DELETION SI)TI-) n n/W< i c/ra //s !<wc/ 'r-kr -Ih ?E!w kukvk/i! - -- t/,n,rAr m: thuih5hv., wnd 05 assus;- S ,ro-l% N- -- - - - - - N *j ~1
==f REOUTRED SIGNATURCS Originator # [ ENn Date l l- 19 -EL - ----
Technical Review v 4Yh - -
- Date -il'l9-8 b- -
i SAFETT EVALUATION
,- Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR?
L-
- 2. Change the procedures as described in the FSAR?
L-
- 3. Conduct tests / experiments not described in the FSAR?
- 4. Create a condition or conduct an operation which ex- D ceeds, 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 N [b0lb -- - Date I M-E L -- - Group /Dep't. Head Review Whd. V j Date I I ' 17- El- - l Temporary Approvala
------Date- -
(NOS) ! Temporary Approval * -- --- Date - - QC Review - d d ~4 -- - ------- Date - M/ 3 -' fd - - - - PORC Review kbM Dat - I- M -$3 - -- Meeting No.11 G# -- PlantManagehNuclearApprhval b O N M -~~~ Date M IS .i - - --
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emsegsney Plen Impismanting Instruction EP-1-030 Site Emergency Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
30 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 1 1-10 Revision 1 1
Emergency Plan Implementing Instruction EP-1-030 Site Emergency- Revision 1 1.0 PURPOSE To outline the actions to be taken for an emergency condition at the Site 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 EP-3-050, Emergency Response Call List 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 Communications 2.8 EP-2-031, In-Plant Radiological Controls During Emergencies 29 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-2-070, Protected Area Evacuation 2.13 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.14 EP-2-101, Operational Support Center (OSC) Activation, Operation, l and Deactivation 2.15 EP-2-102, Emergency Operations Facility (EOF) Activation, Opera-tion, and Deactivation 2.16 EP-2-150, Emergency Reports
- . 2.17 EP-2-052, Protective Action Guidelines l 2
I
Emergency Plan Implementing Instruction EP-1-030 Site Emergency Revision 1 3.0 RES PONSIBILITIES The Emergency Coordinator is responsible for ensuring that the actions as outlined in this procedure are carried out. 4.0 INITIATING CONDITIONS This procedure is to be initiated upon reaching the following conditions: 4.1 Whenever a Site 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 Sound the appropriate alarm as necessary: 5.1.1 Fire 5.1.2 Station 5.2 Make the following announcement (s): o i f 3 1
Emarconey Plan Impicmsnting Instruction EP-1-030 Site Emergency Revision 1 NOTE A Protected Area evacuation is required at a Site Emergency. If conditions do not prevent personne1 from assembling at either of the onsite assembly areas, then proceed to step 5.2.1. If conditions (such as a radioactive plume passing over the Administration Building parking lot) prevent personnel from mustering at one of the onsite assembly areas, then the following announcement should be made: Attention all personnel; attention all personnel. A Site 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 one of the locations: St John the Baptist Catholic Church or Monsanto Park area). Upon arrival, all supervisors shall assemble and log their personnel. Personnel in radiation controlled areas proceed to the Health Physics control points. There will be no smoking, eating or drinking until further notice. The maintenance radio frequency is now dedicated for emergency use only. Repeat the message. 5.2.1 Attention all personnel; attention all personnel: a Site Emergency nas been declared. All members of the Emergency Organization report to your stations. All other personnel within the Protected Area, Trailer City Area and Administration Building Area report to the Administration Building parking lot. All other personnel within the Construction Area report to the parking lot south of the Ebasco Building. All personnel in radiation controlled areas proceed to the Health Physics control points. 4
i Em2rgsney Plan Implcmanting Instruction EP-1-030 Site Emergency Revision 1 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 (e.g., fire), announce its type and location and instruct personnel to stand clear of this area. 5.2 3 Repeat the announcement (s). 5.2.4 Dispatch a Health Physics Technician and the Assembly Area Supervisor, if appropriate, to the appropriate assembly area. 5.3 Make initial contact with Plant Manager-Nuclear. NOTE See Emergency Response Operation Status Board for names and phone numbers; also see EP-3-050. 5.3.1 Dial the Plant Manager-Nuclear's home phone number. If during the work day, dial his work number. 5.3.2 If contact cannot be established in step 5.3.1, then dial Plant Manager-Nuclear's mobile telephone number. 5.3.3 If contact cannot be established in step 5.3.2, tnen contact Operations and Maintenance Assistant Plant Manager-Nuclear, using steps 5.3.1 and 5.3.2. 5.3.4 If Operations and Maintenance Assistant Plant Manager-Nuclear can-not be contacted, then contact the Operations Superintendent. 5.3.5 Upon contact with one of the above individuals, discuss the following: 5.3 5.1 Nature of situation 5.3.5.2 classification 5.3.5.3 Action taken or to be taken 5
Emergency Plan Implementing Instruction EP-1-030
^
Site Emergency Revision 1 5.3.5.4 Need to activate emergency response facilities 5.3.5.5 Ensure Vice President-Nuclear Operations is contacted. 5.4 Provide the Emergency Communicator with the. proper prerecorded cassettes, or complete Attachment 7.3, Answering Machine Message, of l EP-2-010, and direct the Emergency Communicator to activate the 30-minute responder and 1-hour responder Emergency Pager Systems in j accordance with EP-2-010. 5.5 Complete Attachment 7.5, Initial Notification Form, of EP-2-010, and provide to the Emergency Communicator. Direct that he/she commence initial offsite notifications in accordance with EP-2-010 and inform him/her which notifications should be made. 5.5.1 St. Charles Parish Emergency Operations Center (EOC) l 5.5.2 St. John the Baptist Parish EOC 5.5.3 Louisiana Nuclear Energy Division (LNED) 5.5.4 Louisiana Office of Emergency Preparedness (LOEP) 5.5.5 Waterford 1 and 2 5.5.6 Middle South Utilities 5.5 7 U.S. Coast Guard 5.5.8 Missouri Pacific Railroad 5.5.9 American Nuclear Insurers (ANI) 5.5.10 Institute of Nuclear Power Operations (INPO) I 5.5.11 Nuclear Regulatory Commission (NRC) 5.6 As additional information becomes available, update the Emergency Communicator by completing Attachment 7 7, Follow-Up Notification, of EP-2-010, and direct the Emergency Communicator to conduct additional updates to offsite agencies per EP-2-010 on a continual basis. 6 y -w - , , - - - - . , . -
Emargency Plan Impicmsnting Instruction EP-1-030 Site Emergency Revision 1 5.7 Initiate offsite 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. 5.8 Ensure that personnel are expeditiously evacuated from the protected area in accordance with EP-2-070 should the situation warrant.- 5.9 If radioactive releases are occurring or anticipated, instruct Health Physics Coordinator to actuate Radiological Field Monitoring Teams in accordance with EP-2-060. 5.10 Activate the Technical Support Center according to EP-2-100, if not previously activated. 5.11 Activate the Operational Support Center according to EP-2-101, if not previously activated. 5.12 Activate the Emergency Operations Facility according to EP-2-102. 5.13 Ensure the emergency logs / records are kept.in accordance with i EP-2-150. 5.14 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.
5.15 Initiate any additional response measures in accordance with the applicable emergency procedures listed on Attachment 7.1. l l l l 7
Em2rgency Plan Implementing Instruction EP-1-030 Site Emergency Revision 1 j l NOTE A Site Evacuation can be ordered at the Emergency Coordinator's discretion. If it is ordered, the Emergency Coordinator should ensure the following announcement is made over the public address system: Attention all personnel; attention all personnel. A Site Evacuation is required. All nonemergency personnel proceed immediately to the (state one of the locations- St. John the Baptist Catholic Church or Monsanto Park area). Upon arrival, all supervisors shall assemble and log their personnel. There will be no smoking, eating or drinking until further notice. Repeat the message. 5.16 If not previously accomplished, ensure Tecnnical Advisors are dispatched to the local Parish Emergency Operations Centers. 5.17 As conditions change, periodically check EP-1-001 to determine whether reclassification is necessary. 5.17.1 If reclassification is necessary, then reclassify emergency ac-cording to EP-1-001 and implement appropriate Implementing Instruction EP-1-010, EP-1-020, or EP-1-040. l I 5.17.2 If closecut is appropriate, then close out emergency with a verbal summary to all agencies / personnel as indicated on At-tachment 7.13 of EP-2-010. l 8
Emcrgsncy Plan Imp 1cmsnting Instruction EP-1-030 Site Emergency Revision 1 6.0 FINAL CONDITIONS 6.1 Oncoming Emergency Coordinator contacted. 6.2 EOF Director contacted. 6.3 Initial offsite notifications initiated. 6.4 The Site Emergency has been closed out with normal station administration resumed or the emergency reclassified. 7.0 ATTACHMENTS 7.1 Procedure References for Additional Response Guidelines I I 9 i-- - . - - . -_
PROCEDURE REFERENCES FOR ADDITIONAL RESPONSE GUIDELINES Topic Reference 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 Iodine Blocking Agents EP-2-052, Protective Action Guidelines EP-2-071, Site Evacuation EP-2-081, Search and Rescue Toxic Gas, Train EP-2-110, Man-Caused Emergencies Derailment, Airplane Crash, Explosion, Transportation Accidents Tornado, Hurricane, EP-2-120, Natural Emergencies Flood Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentry EP-2-170, Recovery EP-3-001, Emergency Plan Abstract EP-3-050, Emergency Response Call List EP-3-060, Emergency Communications Guidelines EP-3-100, First Aid and Medical Care EP-1-030 Revision 1 10 Attachment 7.1 (1 of 1) mevmen o.-----o
WATERFORD 3 SES PLANT OPERATING MANGAL
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LOUISIANA M100LE SOUTH UT1UTIES SYSTEM EP-1-040 POM VOLUME 18 REVISION 1 PCM SECTION 1 APPROVAL DATE: EFFECTIVE DATE: DERGENCY PLAN IMPLEMENTING INSTRUCTION GENERAL DERGENCY LP&L W-3 RECORDS CONTROL _ED COPY No. 02'.l - t PORC Meeting No. f3-02 8 Reviewed: , Approved: S Plant Manager-Nuclear w m ~w = - - - - - - - _ -
WATERFORD 3 SES S PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST
.rocedure No.
- /'d d - Tit 1e - /W wcL^nrzr -- - - - " -
Effective Date (if different from EM-NYapproval date) Camnlete 1L. B. or C A. Change No. N/A ' B. Revision No. / C. Deletion MU MMMON' FOR CM1NGE. REVISION. OR DELETION N$ hxo)(2fochs dl$- -bd -b e- Yldhi nad/h/NAh ~~ t dharn au;0 kn4 A,m &n%M-- --- -
-1 -T "/ &
REOtfIRED SIGMA?URES Originator %' h b % l Date bS^ --- Technical Review O "D bh -- Date M -l N L - -- - I SAFETT EVALUATION
,-,Does this change, revision, or deletion: YES NO
. . Change the facility as described in the FSAR7 - '
- 4. Change the procedures as described in the FSAR? M
- 3. Condact tests / experiments not described in the FSAR7 '-
- 4. Create a concition or conduct an operation which ex-ceeds, 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 Safety aluation checklist. ! Safety Evaluation b M ~ --
-' Da te IN M'2. - - - -
l Group /Dep't. Head Review b Ubb V J Da te ~ ll' I 9 -R L - Temporary Approval * - Da te - -
- (NOS)
Temporary Approval * - -- -- - --- Date - QC Review M I M M - -- - ------- Da t e - -/-~/3-U' - - PORC Review k 'k Date- 1 Ed - - Meeting No. fMJA --' Plant ManagehNuclear Apprdral - NtN-~~- Date DI83 - - --
' Temporary approval must be followed by Plant Manager-Nuclear approval y ithin 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
\-
i s [ - , E ;trgsney Plan Implementing Instruction EP-1-040
,[GeneralEmergency A
' Revision't R L
's
^'
TABLE OF CONTENTS 1.0 PURPOSE
.[
2.0 REFERENCES
. ~
3.0; RESPONSIBILITIES-4.0' INITIATING CONDITIONS 5.0 PROCEDURE . 6.0 eFINAL CONDITIONS 7.0 AThACHMENTS 7 .1.. Procedure Reference for Additional Response Guidelines (1 page) LIST OF EFFECTIVE PAGES Title Revision 1 1-8 Revision 1 4 i L h 4
"J 1
} .
Encrgsncy Plan Impismsnting Instruction EP-1-040 Ganarol Emsrgoney Revision 1 1.0 PURPOSE 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 23 EP-3-050, Emergency Response Call List 2.4 EP-1-010, Unusual Event 2.5 EP-1-020, Alert 2.6 EP-1-030, Site Emergency
'7 EP-2-010, Notifications and Communications 2.8 EP-2-031, In-Plant Radiological Controls During Emergencies 29 EP-2-050, Offsite Dose Assessment (Manual) 2.10 EP-2-051, Offsite Dose Assessment (Computerized) 2.11 EP-2-052, Protective Action Guidelines 2.12 EP-2-060, Radiological Field Monitoring 2.13 EP-2-071, Site Evacuation 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, Opera-tion, and Deactivation 4.17 EP-2-150, Emergency Records l 2 l
Ensrgency Plen Impismsnting Instruction EP-1-040 General Emergency Revision 1 3.0 RES PONSIBILITIE S The Emergency Coordinator is responsible for ensuring that the actions as outlined in this procedure are carried out. 4.0 INITIATING CONDITIONS This procedure is to be initiated upon reaching the following conditions: 4.1 Whenever 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 Sound the appropriate alarm as necessary:
.1.1 Fire 5.1.2 Station 5.2 Make the following announcement (s):
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. All other personnel proceed immediately to the (state one of the locations) (St. John the l Baptist Catholic Church - or - Monsanto Park area). Upon arrival, all supervisors shall assemble and log their personnel. Personnel in radiation controlled areas proceed to the Health Physics control points. 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 (e.g., fire), announce its type and location and instruct personnel to stand clear of this area. 3.2.3 Repeat the announcement (s). l 3 l
Encrgsney Plan Impidmenting instruction EP-1-040 General Emergency Revision 1 5.2.4 Dispatch a Health Physics Technician and the Assembly Area Supervisor, if appropriate, to the respective assembly area. ! 5,. 3 Make initial contact with Plant Manager-Nuclear. NOTE See Emergency Response Organization Status Board for names and phone numbers; also see EP-3-050. 5.3.1 Dial the Plant Manager-Nuclear's home phone number. If during the day, dial his work number. 5.3.2 If contact cannot be established in step 5.3.1, then dial the Plant Manager-Nuclear's mobile telephone number. s.3.3 If contact cannot be established in step 5.3.2, then contact the Operations and Maintenance Assistant Plant Manager-Nuclear using steps 5.3.1 to 5.3.2. 5.3.4 If the Operations and Maintenance Assistant Plant Manager-Nuclear cannot be contacted, then contact the Operations Superintendent. 5 3.5 Upon contact with one of the above individuals, discuss the following: 5.3.5.1 Nature of situation 5.3.5.2 Classification 5.3.5 3 Action taken or to be taken 5.3.5.4 Need to activate emergency response facilities 5.3.5.5 Ensure that the Vice President-Nuclear Operations is contacted.
.4 Provide the Emergency Communicator with the' proper pre-recorded cassettes or complete Attachment 7.3 of EP-2-010, Answering Machine Message, and direct the Emergency Communicator to activate the l
Em2rgsney Plan Impicmsnt.ing Instruction EP-1-040 . General Emergency Revision 1 30-minute responder and 1-hour responder Emergency Pager Systems in accordance with EP-2-010. 5.5 Complete Attachment 7.5 of EP-2-010, Initi,a1 Notification Form, and provide to the Emergency Communicator. Direct that he/she commence initial offsite notifications in accordance with EP-2-010 and inform him/her which notifications should be made. 5.5.1 St. Charles Parish Emergency Operations _ Center (EOC) 5.5.2 St John the Baptist Parish EOC 5.5.3 Louisiana Nuclear Energy Division (LNED) 5.5.4 Louisiana Office of Emergency Preparedness (LOEP) 5.5.5 Waterford 1 and 2 5.6 Middle South Utilities 5.5.7 U.S. Coast Guard 5.5.8 Missouri Pacific Railroad 5.5.9 American Nuclear Insurers (ANI) 5.5.10 Institute of Nuclear Power Operations (INPO) 5.5.11 Nuclear Regulatory Commission (NRC) 5.6 As additional ~information becomes available, update the Emergency Communicator by completing Attachment 7.7 of EP-2-010, Follow-Up Notification, and direct the Emergency Communicator to conduct additional updates to offsite agencies in accordance with EP-2-010 on a continual basis. 5.7 Initiate offsite 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 ac-cordance with EP-2-052, Protective Action Guidelines. 5
Emsrgsney Plan Impismsnting Instruction EP-1-040 Gansral Emargsney Revision 1 5.8 Ensure that personnel are safely and expeditiously evacuated from the site area to an offsite assembly area in accordance with EP-2-071, should the situation warrant. 5.9 If radiological releases are occurring or anticipated, instruct the Health Physics Coordinator to actuate the Radiological Field Monitoring Teams in accordance with EP-2-060. 5.10 Activate the Technical Support Center in accordance with EP-2-100, if not previously activated. 5.11 Activate the Operational Support Center in accordance with-EP-2-101, if not previously activsted. 5.12 Activate the Emergency Operations Facility in accordance with EP-2-102, if not previously activated.
.13 Ensure that emergency logs / records are kept in accordance with EP-2-150.
5.14 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. 5.15 Initiate any additional response measures in accordance with emergency procedures listed on Attachment 7 1. 4 5.16 If not previously accomplished, ensure that Technical Advisors are dispatched to local parishes and the LNED Emergency Operations Centers. 5.17 As conditions change, periodically check EP-1-001 to determine whether reclassification is necessary. 5.17.1 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'. 6 i
Emsrgsney Plan Implemsnting Instruction . EP-1-040 General Emergency . Revision 1 i 5.17.2 If closecut is appropriate, then close out the emergency with a verbal summary to all agencies / personnel as indicated on At-tachment 7.13 of EP-2-010. 6.0 FINAL CONDITIONS 6.1 Oncoming Emergency Coordinator contacted. 6.2 EOF Director contacted. 6.3 Initial offsite notification initiated. 6.4 The General Emergency has been closed out with normal station administration resumed or the emergency is reclassif' icd. 7.0 ATTACHMENTS 7.1 Procedure Reference for Additional Response Guidelines t i l
- 7 l
I i l
l PROCEDURE REFERENCE FOR ADDITIONAL RESPONSE GUIDELINES l Tonic Reference ) 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 Iodine Blocking Agents EP-2-081, Search and Rescue Toxic, Gas, Train EP-2-110, Man-Caused Emergencies Derailment, Airplane Crash, Explosion, Transportation Accidents Tornado, Hurricane, EP-2-120, Natural Emergencies Flood .
Administration EP-2-130, Emergency Team Assignments EP-2-140, Reentry EP-2-170, Recovery EP-3-001, Emergency Plan Abstract EP-3-050, Emergency Response Call List ; EP-3-060, Emergency Communications Guidelines l l EP-1-040 Revision 1 8 Attachment 7.1 (1 of 1)
WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA POWER & LIGHT
$?Db$r$ .
EP-2-010 l 18 REVISION g3 ,Qj d POM VOLUME 2 APPROVAL DATE: May 2, 19 83 UU PCM SECTION EFFECTIVE DATE: Fuel Load i DIERGENCY PLAN IMPLEMENTIhT, PROCEDURE NOTIFICATIONS AND CCMMUNICATIO S LP&L W-3 RECORDS CONTRO;_LEJ t COPY ~ NO. PORC Meeting No. d ./74 Reviewed: w -
.0 Chairma '- .
l Approve : h. -31o N Plaic~ Sanager-Nuclear
- . . - -..--,-_,__,-m, - . - - - - - - --- --4 - . _ - , - - - . - - - . - - , . - . , - -
- . ~ . - -
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 50 1-010 Title floNAL- s w %.A d. . a;g Effective Date A1/ MP (if different from approval date) Comolete A. B. or C A. Change No. I B. Revision No. L , C. Deletion N/1 -- REASON FOR CHANGE. REVISION. OR DELETION
& %sp~e (we e.d:., n f D stew L xht kind,w v1e x tl/
OLO. /9 ' ' REQUIRED SIGNATUMS
//
Originator Y & EA A w Date Of TechnicalRev1(w A/ M vM b Date A//6v Nb - SAFETY EVALUATION Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR7 v
- 2. Change the procedures as described in the FSAR7
- 3. Conduct tests / experiments not described in the FSAR7 v
- 4. Create a condition or conduct an operation which ex- V ceeds, 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 Safet Evaluation checklist. Safety Evaluation Off Date S'9 -3 h Group /Dep't. Head Rev$ew N Date 8- 9 'I b U d Temporary Approval' Date (NOS) Temporary Approval
- Date QC Review A41 W W A A A w Date f- f F%
PORC Reviewk (e k b b D S -/4-33 Meeting No. f 3 -/ WM Plant Manager Nuclear App royal h btN Date # //O/ D
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
l UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 20
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Emergency Plan Implementing Procedure EP-2-010 Notifications and Communications Revision 3 LIST OF EFFECTIVE PAGES Title Revision 3 -: 1-40 Revision 3 s$t cLp i chJn . 9 F I.
- 3 -42
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-I s
I i e e.W I I l i 2
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f WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. M-MO Title 7Lh-h M bw~ -d4 Effective Date Pu 20 L-J (if different from approval date) Comnlete A. B. or C A. Change No. ^/# 4 B. Revision No. 3 C. Deletion MA REAMOM FOR CHAMCE. REVISION. OR DELETION ,
% /w 'tfzo (14 m 1 w b C-e' d wr tM tM JAz cm ,i h o c.- ._ T REQUIRED SICMATURES Originator Cum OME Date 3bT Technical Review Nv ObA Date 3IM3%
i SAFETY EVALUATION 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 FSAR7- d
/
- 3. Conduct 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 Evaluation checklist. Safety Evaluation k[ Date 3 "Y8 S Group /Dep't. Head Review RO $cA Date UM 13 4 ) Temporary Approval
- Date (NOS)
Temporary Approval
- Date QC Review / #4 9 N'Mu f
Date #- N '# 7 PORC Review N I 2
- N + Date M Meeting No. P3- 0 4 i Plant Mana rYNuclear Approval ' M/ 4
- Date N/ #
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
- 7. G
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Emsrgsney Plan Implcmenting Procsduro EP-2-010 Notifications and Communications 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 Operation of the Answering Machines (1 page) 7.2 Activation of LP&L 30-Minute Response and 1-Hour Response Personnel (3 pages) 7.3 Answering Machine Message (1 page) 7.4 Initial Notification Procedure (4 pages) 7.5 Part I - Initial Notification for State, Parish and Secondary Agencies; Part II - NRC Operations Center Event Notification Form (4 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 (6 pages) 7.8 Request for Offsite Assistance (3 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 (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) i I
1
e Emsrgency Plan Implementing Procedure- EP-2-010 Notifications and Communications Revision 3 t LIST OF EFFECTIVE PAGES + i Title Revision 3 1-40 Revision 3 1 I- i o h i r r 2
,-..-.--.-.c..-.. .._.,,_..,____.,__,,,,y_, _
Emargency Plan Imp 1(menting Proceduro EP-2-010 Notifications and Communications Revision 3 1.0 PURPOSE This procedure provides guidance for making notifications during an emergency and outlines the methods for activating the LP&L Emergency Response Organization.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 State of Louisiana Peacetime Radiological Response Plan 2.3 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.4 EP-2-150, Emergency Records 2.5 EP-3-050, Emergency Response Call List 2.6 EP-3-060, Emergency Communications Guidelines 3.0 RESP 0NsIBILITIES The Emergency Communicator and/or the EOF Communications Coordinator is responsible for carrying out the actions outlined in this procedure. ! 4.0 INITIATING CONDITIONS l 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 l 3
Emergency Plan Implementing Procedure EP-2-010 Notifications and Communications Revision 3 NOTE The 30-minute and 1-hour responder pager systems are to be activated only by direction of the Nuclear Operations Supervisor-Shift Supervisor (NOS-SS). 4.2.2 Alert 4.2.3 Site Area Emergency 4.2.4 General Emergency 5.0 PROCEDURE 5.1 INITIAL NOTIFICATIONS BY THE ON-SITE ORGANIZATION 5.1.1 Activation and Notification of 30-Minute and 1-Hour Response Personnel 9 NOTE 1 If only the 30-minute responders are to be activated, then perform only those steps applicable to 30-minute response personnel. NOTE 2 If conditions exist, such as a toxic chemical or radioactive release, provide appropriate information (wind speed, direction, etc.) in accordance with Attachment 7.3. t 4
Emcrgency Plan Implementing Proceduro EP-2-010 Notifications and Communications Revision 3 5.1.1.1 Place 30-minute responder answering machines and 1-hour responder answering machines in operation according to At-tachment 7.1. 5.1.1.2 Activate and notify the 30-minute response personnel (for Alert, Site Area Emergency or General Emergency) according to At-tachment 7.2, step 1.0. 5.1.1.3 Activate and notify 1-hour response personnel (for Alert, Site Area Emergency or General Emergency) according to Attachment 7.2, step 1.1. NOTE
- 1. Activation of additional personnel to support the Operational Support Center (OSC) or Engineer Support activities will be directed by the OSC Supervisor, if required. Telephone listinbs for the needed crafts will be maintained by the OSC Supervisor.
- 2. Activation of Emergency Operations Facility (EOF) personnel will be accomplished by the EOF Director and EP-3-050.
l
- 3. Activation of Corporate Command Center personnel will be accomplished by the Emergency Director.
5.1.2 Conduct initial offsite notifications in accordance with At-tachment 7 4 and update Attachment 7.13, Notification Checklist. 5.1.3 Upon completion of the initial offsite notifications, verify 30-minute response personnel activation and 1-hour response l personnel activation according to Attachment 7.2, sections 2.0, 3.0 and 4.0. l 5 c
Emergency Plan Implementing Procedure EP-2-010 Notifications and Communications Revision 3 5.1.4 Continue to update offsite agencies / personnel in accordance with Attachment 7.4, Initial Notification Procedure, and update At-tachment 7.13, Notification Checklist. 5.1.5 When directed, make requests for offsite assistance according to Attachment 7.8, Request for Offsite Assistance. 5.2 When informed by the TSC Lead Communicator, transfer communications responsibilities to the TSC in accordance with Attachment 7.9. 5.3 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 ATTACHMENTS 71 Operation of the Answering Machines 72 Activation of LP&L 30-Minute Response and 1-Hour Response Personnel 7.3 Answering Machine Message 7.4 Initial Notification Procedure 7.5 Part I - Initial Notification for State, Parish and Secondary Agencies; Part II - NRC Operations Center Event Notification Form 7.6 Follow-Up Notification Procedure 7.7 Part I - Follcw-Up Notification for State, Parish and Secondary Agencies; Part II - NRC Supplementary Event Notification Information 7.8 Request for Offsite Assistance 79 Control Room Checklist for Transferring Communications Responsibilities to the TSC 7 10 TSC Checklist for Accepting Responsibility for Communications Systems 6
-~ . __ _ .. - - - . _ -
Emergancy Plan Implementing Procedure. EP-2-010 Notifications and Communications Revision 3 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 t 7
~
OPERATION OF THE ANSUERING 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:
Pull down the EJECT lever
- 3) To deliver a message and record incoming calls:
Install the appropriate cassette Press STOP Press ANSWER r
- 4) To verify correct information:
Call 3450 and listen for the correct message and tone hour responder Call 3460 and listen for the correct message and tone minute responders
- 5) To play back incoming messages:
Press STOP Press REWIND Press PLAYBACK ! 6) To record new messages: Install the appropriate cassette i Press STOP Press RECORD (a tone will sound) Speak into the microphone Press STOP (the message will automatically replay) l l EP-2-010 Revision 3 8 Attachment 7 1 ( of )
. , . - ~ . . . , _ _ . . . . - . - - - _.. _. . _ . - - - . .- _
OPERATION OF THE ANSWERING MACHINES NOTE Refer to EP-3-070, Emergency Communications Systems Routine. Testing, Attachment 7.10, for details not covered by this attachment. l l l EP-2-010 Revision 3 9 Attachment 7.1 ( of ) w v-- e - --- --
ACTIVATION OF LP&L 30-MINUTE RESPONSE AND 1-HOUR RESPONSE PERSONNEL 1.0 ACTIVATING THE 30-MINUTE RESPONSE EMERGENCY PAGER SYSTEM Activate 30-minute response personnel in accordance with the Emergency Pager Assignment Roster. 1.1 ACTIVATING THE 1-HOUR RESPONSE EMERGENCY PAGER SYSTEM Activate the 1-hour response personnel in accordance with the Emergency Pager Assignment Roster. NOTE The Emergency Pager Assignment Roster is a confidential list'ing of pager numbers, both individual and group, and is distributed to t.he following personnel only:
- 1) NOS-SS(6)
- 2) R. Barkhurst
- 3) L. Maurin
- 4) D. Lester
- 5) S. Alleman
- 6) F. Drummond
- 7) G. Bailey
- 8) 0.D. Hayes 2.0 VERIFYING RESPONSE 2.1 To verify response to the pager system of the 30-minute response and 1-hour response personnel:
2.1.1 Press PLAYBACK and machines will automatically rewind and play back called-in messages. EP-2-010 Revision 3 10 Attachment 7.2 ( of )
ACTIVATION OF LP&L 30-MINUTE RESPONSE AND 1-HOUR RESPONSE PERSONNEL j l l l 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 The answering machine will automatically stop after the last message has been played. 2.1.4 Press ANSWER to start receiving calls after listening to the last message. 2.1.5 To erase all messages previously received, press REWIND ERASE and then press REWIND. 2.2 Update communications status board. 3.0 BACKUP METHOD FOR ACTIVATING 30-MINUTE RESPONSE AND 1-HOUR RESPONSE PERSONNEL 3.1 Using EP-3-050, attempt to contact the individuals listed as 30-minute response or 1-hour response personnel via telephone. If the primary person cannot be reached, contact via telephone the alternate listed for that position. Upon reaching either the primary or alternate, give the following information: WE HAVE DECLARED AN/A EMERGENCY AT WATERFORD 3. (Alert, Site Area, General) YOUR IMMEDIATE RESPONSE TO THE SITE IS REQUIRED. WHAT IS YOUR ANTICIPATED ARRIVAL TIME? Do not engage in a discussion of the situation with the individual. If questions arise, inform the individual he/she will be briefed l upon arrival on site. EP-2-010 Revision 3 11 Attachment 7.2 ( of )
ACTIVATION OF LP&!. 30-MINUTE RESPONSE AND 1-HOUR RESPONSE PERSONNEL 4.0 UPDATING THE EMERGENCY COORDINATOR 4.1 Provide a list of the individuals responding and not responding and their stated anticipated arrival times to the Emergency Coordinator. 4.2 Request the names of personnel to substitute for those not contacted. Once names have been provided, contact personnel via telephone and repeat the' message in step 3.1 above. EP-2-010 Revision 3 12 Attachment 7.2 ( of )
ANSWERING MACHINE MESSAGE
- 1. Complete the following message and provide to the Emergency Com-municator:
AN (Unusual Event, Alert, Site Area or General) EMERGENCY HAS BEEN DECLARED AT
.WATERFORD 3 DUE TO YOUR IMMEDIATE RESPONSE TO THE SITE IS REQUIRED. AFTER THE SOUND 0F THE FOLLOWING TONE, LEAVE YOUR NAME, ANTICIPATED ARRIVAL TIME ANL TITLE OF EMERGENCY POSITION AT THE END OF THIS MESSAGE.
l l l l l EP-2-010 Revision 3 13 Attachment 7.3 (1 of 1) L.
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, of this procedure. 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 (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 statementi 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 (TAB 2 TO ATTACHMENT 1 0F THE STATE OF LOUISIANA PEACETIME RADIOLOGICAL RESPONSE PLAN) AND STAND BY TO RECORD INFORMATION. Allow a few noments for the agencies' representatives to obtain the l form. 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 3 14 Attachment 7.4 (loff) l
INITIAL NOTIFICATION PROCEDURE 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 number of the appropriate agency (ies) and perform steps 2.3 and 2.4 above. 2.5.1.1 St. Charles Parish EOC 789-6266-2.5.1.2 St. John the Baptist Parish EOC 652-2222 . 2.5.1.3 Louisiana Nuclear Energy Division (LNED) - Emergency Prepared-ness 1 025 4518- . 2.5.1.4 Louisiana Office of Emergency Preparedness (LOEP) - Com-munications Office 1-942-5470 . 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. 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 19, or PABX 71-8797, or 464-0101 2.7.1 When Waterford 1 and 2 come on the line, repeat the initial notification form. l 3.0 NOTIFICATION VIA THE NRC EMERGENCY NOTIFICATION SYSTEM NOTE Communications with the NRC may be i continuously maintained. 1 i 31 Lift the receiver for the NRC Emergency Notification System phone. Once a response is obtained, make the following statement: EP-2-010 Revision 3 15 Attachment 7.4 (8 off ) l t
INITIAL NOTIFICATION PROCEDURE THIS IS -- AT THE LP&L WATERFORD 3 STEAM ELECTRIC STATION. (Name/ Title) THE FOLLOWING IS A NOTIFICATION OF AN EMERGENCY. 32 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:
- 1. Commercial telephone 1-202-951-0550
- 2. Health Physics network 3.3 Update Attachment 7.13, Notification Checklist.
3.4 If relieved by an NRC Representative, continue with communications duties. l 4.0 Secondary notifications will be made at the direction of the Emergency Coordinator or the Emergency Operations Facility Director. When the groups in steps 4.1-4.5 are contacted, repeat the intial notification form. 4.1 Middle South Utilities - (J. Richard) - 960 us09 , 4.2 U.S. Coast Guard - 589-7101. 1 4.3 Missouri Pacific Railroad, between 0700-2300 hours - 785-6613. If no answer, call 566-8014 EP-2-010 Revision 3 16 Attachment 7.4 (jf of f )
INITIAL NOTIFICATION PROCEDURE 4.4 American Nuclear Insurers (ANI), Farmington, CT 201-677-7105 4.5 Institute of Nuclear Power Operations, Atlanta, GA - 12404 c59-0904 5.0 VERIFICATION, CALL NOTE If St. Charles Parish EOC, St. John the Baptist Parish EOC, the LNED or LOEP is noti-fled via any method other than the Operational Hotline, then a verification call is required. Record required information belca. 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) EP-2-010 Revision 3 17 Attachment 7.4(forf) O
p *t. I_ INITIAL NOTIFICATION FOR STATE, PARISH AND SECONDARY AGENCIES
* ,e i
er 1 This is with Message No. 1 , at hrs., (Name) (Time) 2 on with Telephone No. (Date) (Site) 3 Events are such that a/an Unusual Event Site Area Emergency . 4 Alert General Emergency 5 was declared at hrs. 6 Brief description of events (s): 7 l THE FOLLOWING _ INFORMATION APPLIES: 9 nelease: NO l 10 TES - Liquid; Gaseous; other Wind Speed :sph
.. Wind Direction from into Sector (s) .
(degrees) (A-R) 13 Recommend Protective Actions: _ None o 14 Shelter i 15 other 16 l A comprehensive assessment of conditions is in progress at this time. l Additional information will be provided to you as the situation develops. h 1CENCY CCORDINATOR / TIME ,
,PLEASE ACKNOWLEDGE RECEI?T OF THIS MESSAGE AS YOUR STATION IS CALLED.
LNED I- St. Charles EOC i L0EP St. John EOC l TIME TRANSMITTAL VF.RIFICATION - CCMMUNICATOR'S SICNATURI EP-2-010Revisionj Attachment 7.5 (1 of 4)
I' PRIMARY NOTIFICATION AGENCIES SECONDARY NOTIFICATION' AGENCIES St. Charles EOC (783-6266) Waterford 1&2~ (71-8797) St. John EOC (652-2222) US Coast Guard (589-7101) La. Nuclear Energy (1-925-4518) Missouri Pacific RR' (785-6613) La. Office Zaarg'ency Middle South Utilities (569-4509) Preparedness (1-342-5470) ANI (1-203-677-7305) INPO (1-404-953-0904 i
. b' l .
l l EP-2-010 Revisionj g Attachment 7.5 (2 of 4)
. , _ -- m y- m , _.--,wn n .
PART lI - NRC OPERATIONS CENTER EVENT NOTIFICATION FORM
- 1. TIME OF REPORT: - --- ----- - -- -
DATE: -- - ----
- 2. FACILITY OR ORGANIZATION: LOUISIAN A POWER AND LIGHT - WATERFORD 9 SES
- 3. ----------- -- - -
CALLER'S NAME: - - 1
- 4. EVENT CLASSIFICATIONS: - - -' -
50.72 UNUSUAL EVENT ALERT SITE AREA EMERGENCY
- ------ ~*-
GENERAL EMERGENCY TRANSPORTATION PHYSICAL SECURITY; SAFEGUARDS
-- OTHER CATEGORY
- 5. EVENT DESCRIPTION:
- 6. EVENT TIME: - - - - - - ---- - - -
- 7. --- - - - " - - - -
CAUSE:
- 8. POWER PRIOR TO EVENT: - ---- - -- -
- 9. - --------- ------- - -- ---
POWER NOW:
- 10. ANY SAFETY INJECTION OR ECCS? - - - - - - - - - ' - - - - - -- - -
- 11. COOLING MODE:
EP-2-010 Revision 3 20 Attachment 7.5(8off)
PART II - NRC OPERATIONS CENTER EVENT NOTIFICATION FORM (QUANTIFY): -- - -
- 12. ANY CONTAMINATION?
(QUANTIFY):
- 13. ANY RELEASES? ,
- 14. CONTAINMENT STATUS (IF APPLICABLE):
- 15. ANY OTHER PROBLEMS:
- 16. ANYTHING UNUSUAL OR NOT UNDERSTOOD?
- 17. PLANS: -- - - - -
- - - ~ - ~
- 18. ANY OUTSIDE AGENCY OR PERSONNEL NOTIFIED: - - ' -
Emergency Coordinator's Signature / Time
.......f................. ... .. ...
Time Transmittal Verified / Emergency Communicator's Signature tr-2-010 Revision 3 21 Attachment 7.5(foff) I
FOLLOW-UP NOTIFICATION PROCEDURE 1.0 Receive from the Emergency Coordinator Attachment 7.7, Follow-Up ; Notification, of this procedure. NOTE Notify only the appropriate personnel / agencies of conditions that change. 2.0 Renotify St. Charles Parish EOC, St. John the Baptist Parish EOC, 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 respresentative identifies himself, respond with WATERFORD 3 STEAM ELECTRIC STATION: STAND BY and note the title of the agency responding. 2.3 Af ter all agencies have identified themselves or two minutes have elapsed, make the following statement: THIS IS - AT THE WATERFORD 3 NUCLEAR POWER STATION. (name/ title) THE FOLLOWING IS A SUBSEQUENT NOTIFICATION 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. Allow a few mcments for the agencies' representatives to obtain the checklist. 2.4 Read information on the Folicw-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. 2.5.1 Dial the appropriate agency's(ies') phone number (s) and perform steps 2.3 and 2.4 above. EP-2-010 Revision 3 22 Attachment 7.6 (/ ordI)
FOLLOW-UP NOTIFICATION PROCEDURE 2.5.1.1 St. Charles Parish EOC 789-6266 -- 2.5.1.2 St. John the Baptist Parish EOC 652-2222 . 2.5.1.3 Louisiana Nuclear Energy Division (LNED) - Emergency Prepared-ness 1~-425 4518 . 2.5.1.4 Louisiana Office of Emergency Preparedeness (LOEP) - Com-munications Office 1-942-5470- , 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. 2.5.3 Ensure that the Lead Communicator / Communications Coordinator receives verification of transmittal. 2.5.4 Lead Communicator / Communications Coordinator notifies the Emergency Coordinator / EOF Director of verification of transmittal. 2.6 Update Attachment 7.13, Notification Checklist. 27 Waterford 1 and 2 SES will be notified using one of the following methods: LP&L Emergency Telephone, dial 19, or PABX 71-8797, or 464-0101 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 H AV E DE CL ARED A ( N ) - - - - - - - - - - - - - - - - - - - AT (emergency classification) HOURS. WE---------------- HAD A RADIOACTIVE (time) (have/have not) RELEASE. EP-2-010 Revision 3 23 Attachment 7.6 (JEofdi)
FOLLOW-UP NOTIFICATION PROCEDURE (Provide a brief description of the event) WATERFORD 3 SES REQUESTS TH AT - ----- -
~
(Protective actions, assistance, etc.) 3.0 Secondary notification will be initiated at the direction of either the Emergency Coordinator or Emergency Operations Facility Director. When the groups in steps 3 1-3.5 are contacted, 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 (time) (have/have not) RELEASE. (Provide a brief description of the event) - - - - - ~ - - - -- -- ------ WATERFORD 3 SES REQUESTS THAT -- l (Protective actions, assistance, etc.) 3.1 Middle South Utilities - (J. Richard) - 564-4509 l 1 3.2 U.S. Coast Guard - 584-7101 3.3 Missouri Pacific Railroad, between 0700-2300 hours - 785-6619 l l EP-2-010 Revision 3 24 Attachment 7.6 (JIofdf) l
FOLLOM-UP NOTIFICATION PROCEDURE If no answer, call - 566 8014 3.4 American Nuclear Insurers (ANI), Farmington, CT 209-677-7905 3.5 Institute or Nuclear Power Operations, Atlanta, GA 404-959 0004 4.0 NUCLEAR REGULATORY COMMISSION (NRC) VIA NRC EMERGENCY NOTIFICATION SYSTEM (Control Room and TSC only!) NOTE Communications with the NRC will be continuously maintained. 4.1 Lif t 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 (name/ title) STATION. THE FOLLOWING IS AN UPDATE OF INFORMATION REGARDING OUR DECLARED EMERGENCY. 4.2 Provide the NRC representative with the information written on the NRC Supplementary Event Notification Information 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. i 4.2.1 If the NRC Emergency Notification System (ENS) is not operational, contact the NRC by the following method:
- 1) Commercial telephone 202-951-0550 l
l EP-2-010 Revision 3 25 Attachment 7.6(//ofd')
-FOLLOW-UP NOTIFICATION PROCEDURE
- 2) Health Physics network 4.3 Ensure that the Emergency Coordinator receives verification of transmittal.
4.4 Update Attachment 7.13, Notification Checklist. .o 4.5 If relieved by an NRC Representative, continue with communications duties. EP-2-010 Revision 3 26 Attachment 7.6([off)
PART 1 - FOLLOW-UP NOTIFICATION FOR STATE PARISH AND SECONDARY AGENCIES Li-Num. Page 1 1 This is with Massage No. , at hrs. (Name) (Number) (Time) 2 n with Waterford 3 Steam Electric Station Telephone No. 464- ; (Data) _ (Site) ; 3 Events are such that a/an: Unusual Event Site Area Emergency 4 Alert General E=argency 5 was declared at hrs. This classification is (Escalated, De-escalated, Unchanged. Terminated) from the last report. 6 Reason for reclassificatic': n 7 8 THE FOLLOWING INFORMATION APPLIES: 9 SECTION A: Radiological Release Information N/A 10 This information is: A) New Information 3) Unchanged 11 (1) Type of Radiological Release: Liquid, Gaseous: Other 12 (2) Time of Reactor Shutdown: hrs. 13 (3) Initial Time of Release hrs. 14 (4) Release Terminated: NO; TES TIME TERMINATEP hrs. 15 (5) Duration of Release: KNOWN or TOTAL PROJECTED (hours) (hours) 16 (6) Release Rate: Noble Gas Ci/sec Monitored; Calculated i 17 Iodine C1/sec Monitored; Calculated 18 Particulate C1/see MonitoredfCalculated 19 (7) Release Elevation: Ground Lavel: Elevated 20 (8) Estimate of Surface Contamination In-Planc, Onsite, or Offsite: 21 . l ~22 SECTION B: Meteorology N/A 23 This information is: A) New information 3) Unchanged 24 (1) Wind: Speed sph 25 Direction from into Sector (s) (degrees) (A-R) 26 (2) Stability Class: A B C D E F G 27 (3) Precipitation: None; Rain; Sleet; Snow; Hail EP-2-010Revisionj W O Attachment 7.7 (1 of 6)
Lins
, Numb r FOLLOW-UP NOTIFICATION - Page 2 ,
)
SECTION C: Offsite Radiological Dose Consecuences N/A This is: A) New Information B) Unchanged Projected (1) Projected Whole Body Dose At: Dose Rate Duration Projected Dose 3 A) Site Boundary mR/hr mrem 4 B) 2 Miles mR/hr mRea 5 C) 5 Miles mR/hr mrem 6 D) 10 Miles dR/hr mrem (2) Projected Thyroid Dose Coucaltment At: Projected Dose 7 A) Site Boundary mrem 8 B) 2 Miles mrem 9 C) 5 Miles mrem 10 D) 10 Miles mrem 11 (3) Affected Sectors 12 SECTION D: Emergency Response Considerations N/A 13 This is A) New Information B) Unchanged 14 (1) Recommended Protective Actions: None; other (Describe) t-17 (2) Licensee Emergency Actions Underway: None; Cther (Describe) 18 19 20 (3) Request for Offsite Support: None; other (Describe) 21
=
22 23 - (4) Prognosis for Worsening or Termination of Event Based on Plant Information: 24 None; Other (Describe) 25
, 26 27 (5) Other Comments: None; Other (Describe) 28 29 30 L b
EMERGENCY C00RDINATOR'S/ EOF DIRECTOR - TIME
-1 EP-2-010 Revisionj Attachment 7.7 (2 of ,6) a m- - - - -
,- ,_ .---.,,_e,--,a---,-----, - . .-- - . - - ,- , , - - , , - , , ,
i l Please acknowledge receipt of this message as your station is called: LNED . LOEP St. Charles EOC St. John EOC TRANSMITTAL VERIFIED: COMMUNICATOR SIGNATURE / TIME PRIMARY NOTIFICATION AGENCIES SECONDARY NOTIFICATICN AGENCIES St. Charles EOC (783-6266) Waterford 1&2 (71-8797) St. John ECC (652-2222) ,US Coast Guard (589-7101) La. Nuclear Energy (1-925-4518) Missouri Pacific RR (785-6613) La. Office Emergency Middle South Utilities (569-4509) Preparedness (1-342-5470) ANI (1-203-677-7305) INPO (1-404-953-0904)
/*
e e 9 0 EP-2-010 Revision / Attachment 7.7 (3 of ) . t l
I PART II - NRC SUPPLEMENTARY EVENT NOTIFICATION INFORMATION THIS IS LOUISIANA POWER & LIGHT COMPANY - W3 SES WITH A SUPPLEMENTARY EVENT NOTIFICATION NUMBER - AT - - - - - - - HOURS, ON -- - . (date) FURTHER L'ICENSE ACTIONS i Taken ------------- Planned - - - -- ------- - - ------- --- Property Damage - -- ---- ---- -- -- R ADIO ACTIVITY RELE ASED' (OR- INCREASED- RELEASE-)? Liquid / Gas? - - Location / Source of Release --- Elevation - - Release Rate - Duration----------------- Stopped? - - -- - - Release Monitored? - - - - - - - - - Amount of Release -- - ---
'---~~-----
INCREASED R ADIATION - LEVELS- IN- PL ANT: Loca tion (s ) ~ ~ ~ * --- -
- Radiation Level (s) -- - ----
Areas Evacuated * - ------- ---- - --
- - * - ' - ' - - - - - *- ~ ~ * * - - *
- Maximum Off-Site Dose Rates -----'--' --
Integrated Dose Location METEOROLOGY Wind Direction from --- , Wind Speed -
------- ---~~- - - (Meter /sec or miles /hr) l T -- ( C or F ) Sigma Theta - - - - - - - - Temperature -- -- ( C or F)
Stability Class A B C D E F Raining (Yes/No) i l Projected Doses: I Dose Rates Integrated Dose
---^--- -' ' - * - * *
- --------~~---
2 mi
- --~~~------** - - - - - - - - - - - - - - - - - *---
5 mi
- *--~~~------ ---* -- - -------
10 mi
- -------~~~-- -------- ~------ - ' - -
Sectors EP-2-010 Revision 3 30 Attachment 7.7 ( f ofh )
PART II - NRC SUPPLEMENTARY EVENT NOTIFICATION INFORMATION Contamination (Surface): In-Plant ---- Onsite - Offsite - --- REACTOR OPERATIONS: REACTOR- SYSTEM- STATUS Power Level --- Pressure -
---Temp.---------- Flow (pumps on)
Cooling Mode ---~- ---- --- ECCS Operating / Operable -- CONTAINMENT STATUS Containment Isolated? - -- -- -- --- Containment Temp. - Containment Pressure ---------- Containment Radiation - R/hr Standby Gas Treat Sys (BWR)- - - - - - - - - - - REACTIVITY CONTROLS Control Rods Inserted -------- Status of Emer. Boration System - STEAM PLANT STATUS S/G Lev els - ---- - -- - Equip. failures Feedwater Source / Flow - ------ --- -------- S/ G Isola t e d? - - - - - - - - - - - - MSIVs (BWR) Closed --------- --- -- -- Eieetrical Dist. Status: Normal Offsite Power Available? Major Busses / Loads Lost ---------------- - ---- -- - - -- Safeguards Busses Power Source - ------- - D/G Running? -- - - ~~--------*--~~'---- --
-* Loaded - ---*---
SECURITY / SAFEGUARDS: Bomb Threat: Search Conducted? - ------ -- - - -- -- Search Results Site Evacuated? EP-2-010 Revision 3 31 Attachment 7 7 (jfordI)
PART II - NRC SUPPLEMENTARY EVENT NOTIFICATION INFORMATION Ertortion: Source (Phone, letter, etc.)?------"-----'-------------
*~~~----~~---------- --- ~~--- --- *-- -- -
Location or Letter Intrusion: Insider? *** ---------------- Outsider? -- - Furthest Point of Intrusion Fire Arms Related? - ------ Stolen / Missing Ma terial? - --- - - Rr Oner'1 Demonstration:
. Size of Group --- - - - - - Demands -
Violence?
- --------- -- Fire Arms Related? - ---
Sabotare/ Vandalism: Radiological? --- Arson Involved? Stolen / Missing Material? TRANSPORTATIOH; Mode (Road / Rail / Air /etc.) - ----- ------ -
-- Carrier
'-' ~~~~ ~ ----**--*-~~-- ------ ~~'- -- -
- Exact Location Type of Material (HEU/ Spent Fuel / Cat III/Other) - - -- - - --
- ---~--- - - - - -
Description of Shipment - ---' ----------- - Labels: (On material package) - --- ---- - --- O n v ehicl e ) - - - - - - - -- -
--* ----------~~~~--~~~~~~ -- -- - -- --- ---------------**
Spillage Physical damage to container? - Fire / Smoke - - --- -- -- - Missing material? -- MATERIALS AND FUEL FACILITIES: Kind of Licensee (processor, radiographer, medical, et al. ) -
- -- Isotopes involved --- -
Sealed / Loose? - - - - Solid / Liquified?
. . . ............q.
Emergency Coordinator's/ EOF Director's Signature / Time
**- "-----~~-*---- --- - -
Transmittal Verified Communicator Signature / Time - ? l t EP-2-010 Revision 3 32 Attachment 7.7 ( [of d)
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, and/or the Com-munications Log Form, Attachment 7.1, of EP-2-150. NOTE Notify or request assistance only from the appropriate personnel / agencies as directed R by the Emergency Coordinator or the Emer-gency Operations Facility Director. 2.0 REQUESTS FOR OFFSITE ASSISTANCE
2.1 Hospitals
see EP-2-020, Contaminated Injured /Ill Personnel 2.1.1 Requests for medical assistance will be made directly to the appropriate hospital using PABX telephone. 2.1.1.1 West Jefferson General Hospital - 9u7-5511, 2.1.1.2 Ochsner Foundation Hospital - 876-9000. 2.1.1.3 St. Charles Hospital - 1BS-62t2 i NOTE When contacting the above hospitals, ask for the chief nurse and provide the necessary I information as prescribed in the applicable I attachment in EP-2-020, 2.2 AMBULANCE SERVICES 2.2.1 Requests for Ambulance Services will be made directly to the I appropriate facility. 1 EP-2-010 Revision 3 33 Attachment 7.8 ( / of0f )
REQUEST FOR OFFSITE ASSISTANCE 2.2.2 St. Charles Hospital Ambulance Industrin1- Hotiine or 785-6242. 2.2.3 West Jefferson General Hospital (Air Care - Helicopter Services) 1 800-982-4006. 2.2.4 Ochsner Foundation Hospital - 898-9000. NOTE When requesting offsite ambulance assistance, ensure that EP-2-020, Contaminated Injured /Ill Personnel, Attachment 7.3, Security Notifica-tion 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 Guard - 1s504-589-7101- or Operntf enni- Hetidne. 2.3.2 Missouri Pacific Railroad Company '785s6619 or 566-8014 2 3.3 Louisiana State Police 508-568-5751 or- Ocerational- Hotline. 2.3.4 St. Charles Parish Sheriff's Department - St. Charles-Industrial Hotline or Onerational Hotidne. 2.3 5 St. John Parish Sheriff's Department - 78126807 2.4 FIRE FIGHTING ASSISTANCE 2.4.1 Hahnv111e Volunteer Fire Department - St. Charles 7ndustrini Hotline. 2.5 ENGINEERING ASSISTANCE 2.5.1 Combustion Engineering, Inc. - 1s20926 88-1911, 2.5.2 Ebasco Services, Inc. - (NY, NY) 212 899-1000 2.5.3 Ebasco Services, Inc. (On- stte-)- Mr .- stnmoiev- 7 2-9 51 2.5.4 Middle South Utilities - (J. Richard) - 560- 8509.- EP-2-010 Revision 3 34 Attachment 7.8 (JEoff )
RE' QUEST FOR OFFSITE ASSISTANCE 2.6 TECHNICAL / ENGINEERING ASSISTANCE 2.6.1 Institute of Nuclear Power Operations (INPO) 404-959-0904, 2.7 DEPARTMENT OF ENERGY 2 7.1 Radiation Emergency Assistance Center - 615-576-9191 or . 615-576-9190. . 2.7.2 Radiological Assistance for Region II - 615-525-7885 or 615-576-1005 2.8 NUCLEAR REGULATORY COMMISSION 2.8.1 Use dedicated NRC-Metline or- 1-202-951-0550. 2.9 OTHER LP&L FACILITIES 2.9.1 Waterford 1 and 2 SES LP Emerrenev Dial 10:* PABX 71 87o7 or 464-0101, 292 Luling District Office - 785-6-251 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:
Emergency Coordinator or (Time /Date) EOF Director Signature EP-2-010 Revision 3 35 Attachment 7.8 (;fof;I)
CONTROL ROOM CHECKLIST FOR TRANSFERRING COMMUNICATIONS RESPONSIBILITIES TO THE TSC
- 1. When the TSC is activated and is ready to accept the responsibilities for all offsite and onsite communications, the Control Room Emergency Communicator will:
1
- a. Stand by and monitor all communications systems.
- b. After the TSC Emergency Coordinator accepts the onsite and offsite communications responsibilities, the TSC Communicator will announce over all telephone systems: WATERFORD 3 TECHNICAL SUPPORT CENTER HAS BEEN ACTIVATED and COMMUNICATIONS ARE NOW BEING HANDLED BY THE TECHNICAL SUPPORT CENTER EMERGENCY CONTROL CENTER. Also announce 7
over the a'ctivated line: THE WATERFORD 3 CONTROL ROOM RELINQUISHES COMMUNICATIONS ON THIS LINE.
- 2. Upon completion of the transfer, the Control Room Emergency Com-municator will perform the following functions:
- a. Inform the NOS-SS that communications have been transferred to the TSC ECC.
- b. Deliver all dispatched or developed Initial Notification, Follow-Up 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 3 36 Attachment 7 9 (1 of 1) 4
TSC CHECKLIST FOR ACCEPTING RESPONSIBILITY FOR COMMUNICATIONS SYSTEMS
- 1. The TSC Lead Communicator will be delivered a copy of each Initial Notification, 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 can perform the following actions:
- a. Review the material to become familiar with communications to this point, if time permits.
- 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 Coordinator to continue handling communications.
- c. At the direction of the Emergency Coordinator "to shift com-munications to the TSC," make the following announcement on the active lines (one at a time to allow proper response from the Control Room): WATERFORD 3 TECHNICAL SUPPORT CENTER HAS BEEN ACTIVATED. COMMUNICATIONS ARE NOW BEING HANDLED BY THE TECHNICAL SUPPORT CENTER.
- 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 Revison 3 37 Attachment 7.10 (1 of 1)
TSC (EOF) CHECKLIST FOR TRANSFERRING COMMUNICATIONS RESPONSIBILITIES TO THE EOF (TSC)
- 1. Establish communications with the EOF (TSC) Communicator and provide the following information in the areas in which responsibility is to be transferred:
- a. 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)
- 2. Offsite communications:
- a. Continue maintaining communications on the activated line after completing the steps above.
- b. After the EOF (TSC) Communicator announces: WATERFORD 3 EMERGENCY OPERATIONS FACILITY (TECHNICAL SUPPORT CENTER) IS NOW RESPONSIBLE FOR COMMUNICATIONS ON THIS LINE, announce over the activated line:
THE WATERFORD 3 (EMERGENCY OPERATIONS FACILITY) TECHNICAL SUPPORT CENTER RELINQUISHES COMMUNICATION ON THIS LINE.
- c. Inform the (EOF Director) Emergency Coordinator that communications have been transferred.
EP-2-010 Revision 3 38 Attachment 7.11 (1 of 1)
EOF CHECKLIST FOR ACCEPTING COMMUNICATIONS RESPONSIBILITIES FROM THE TSC
- 1. Establish communications with the TSC Communicator and discuss the 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)
- 2. Offsite communications:
- a. EOF Communicator directs the TSC Communicator to shift com-l 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 Communications Log Sheet (Attachment 7 1, EP-2-150, Emergency Records).
NOTE Do not respond; allow the TSC Communicator to continue handling communications.
- 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 FACILITY IS NOW RESPONSIBLE FOR COMMUNICATIONS ON THIS LINE.
- d. Stand by for the TSC Communicator to announce that THE WATERFORD 3 TECHNICAL SUPPORT CENTER RELINQUISHES COMMUNICATION ON THIS LINE.
After hearing the announcement, inform the EOF Communication Coordinator that communications have been transferred.
- e. The Communications Coordinator shall notify the EOF Director that offsite communications have been transferred.
EP-2-010 Revision 3 39 Attachment 7 12 (1 of 1)
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WATERFORD 3 SES PLANT OPERATING MANUAL laulSIANA MICCt.E SCUTH UTIUTES SYSTEM EP-2-020 POM VOLUME 18 REVISION g b# YW3
- APPROVAL DATE: May 2, 1983 PCM SECTION 2 ETTECTIVE DATE: Fuel Load EMERGENCY PLAN IMPL"ENTING PROCEDURE CONTAMINATED INJURED /ILL FERSONNEL LP&L W-3 RECORDS CON-. ROLLED
~
COPY NO- OO . PORC Meeting N . 73 9 ?4 Reviewed: /u % RC rman . Approved: l MM i Plant Manager-Nuclear
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WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 8Al-020 Title 6 % d 1 4 /in'm #/ # d%( Effective Date h/[dwl (if different from approval date) Comelete A. B. o r- C A. Change No. / B. Revision No. 3 . C. Deletion W4 REASON FOR CHANGE. REVISION. OR DELETION
* !A tenJ d e 1:Jav < .Cr d 2 r ma $ -t'la k;Nu 1k' d du' 4ML$td * /
REQUIRED SICMA Originator I b 4 & u Date i Technical {evi k /l$l 0 Date //l4 l'lb SAFETY EVALUATION Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR7 L
- 2. Change the procedures as described in the FSAR7- 1s
- 3. Conduct tests / experiments not described in the FSAR7 D
- 4. Create a condition or conduct an operation which ex- / e--
ceeds, 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 Safet Evaluation checklist. Safety Evaluation OY Date ESM Group /Dep't. HeadReYiew UU Date 0943 i . Temporary Approval
- Date (NOS)
Temporary Approval
- Date QC Review #d? A W E u Date 5- Y-P-2 PORC Review k k Date 8-lO-SS Meeting No. f 3 -if -
~~
PlantManagehNuclearApprbval bb Date S /0/8 T l
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) l ZG l f
l I' '
. ', i WATERFORD 3 SE3 PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No.' N ~HAC' Title [ 5 \Ad ?NeA Effective Data D Lc'-* (if different from approval date) canntata 1. B. era C A. Change No. FIA B. Revision No. '3 C. Deletion N/A
. nruou ron estiver. nrvision. on artrTrow r, A s w-a ,n ca ~ .au Cie A./.E 1.wmu.) kl HECUIRED SICMATURES Originator b~~ OA Date 3/2Vh Technical Review G, D\SuCL. Date' N4/81 u a SAFETT EVALUATION Does t.his change, revision, or deletion: TES NO
- 1. Change the facility as described in the FSAR7 -
- 2. Change the procedures as described in the FSAR7- g 3 Conduct tests / experiments not described in the F3AR7 _ _ p_.
- 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 N bb Date T d'O Group /Dep't. Head Review b 8 b o'- Date 3 M-% 3 i- w g Temporary Approval
- Date (NCS)
_. Temporary Approvale Date _ QC Review - M #re' M - Date #-- A P-e 7 Date <fM PORC Review I d h N Meeting No. YbN Plant ManagerINuclear Approval ' #I4 "# Date */4 "'M
' Temporary approval aust be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2 Cs
f Emergency Plan Implescnting Proceduro- EP-2-020 Contaminated Injured /Ill Personnel Revision 73
~
TABLE OF CONTENTS 1.0 PURPOSE 2.0 REFEREN CES . 3.0 RES PONSIBILITIES 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 Ochsner Foundation Hospital Notification Checklist (2 pages) 7.3 West Jef ferson.Gener.al Hospital. Notif teationeCheex11st-(2 pages) 7.4 Security Notification Checklist (1 page) 7.5 Health Physics Responsibilities on Site (1 page) 76 Health Physics Responsibilities at Support Hospital (2 pages) LIST OF EFFECTIVE PAGES Tif.le
' " ~ ~ ~
Revision 2 1-16 Revision 2 Jh i k,.y.i chlfs l
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. l q Em:rg ncy. Planc I plemcnting Procoduro EP-2-020 "
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Contaminated Injured /Ill Personnel ,, Revision J3)W 4 6/13 7-
.- ,j ..
[ i
;j 1.0 PU R Pos e ,, ,
The purpose ofathis, procedure id to prcvide guidance to the Emergency Coordinator, in the' event that contaminated injured /,ill
- personnel must be transported off site.
2.0 ReceneNCES , 2.1 Wa'terf ord 3 SES Em,ergency Plaa , 2.2 Emergency Medical' Assistance Progrcm (EMAP), Draf t 4
.t- .
2.3 NUREG 0654/ FEMA-REP-1, Rev. 1 , 2.4 EP-3-050, EmergencyiResp nse call; List
' 2.5 FP-2-200, First Aid and, Medical Care i .
f
/ 4 +
t . , f 2.6 EP-3-040, Emergenc'y Equiscent Inventory- .- ' t ;> , , 30 .
- ,. Res PONST37trTres 74i . > #
k j/ ,) The Emergency \ Coordinator is responsible forf ensuring thce.the a actions as outlineo'in <' this praIedure are. carried out) 1 t
,. f. ;
4.0 INITIATINC. CONDrTIONS U , p . s
\
j Injured /ill personnel are contaminated and aust be transported off j v sit.. .
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- Emergency Plan Implementing Procedure" ~ -
EP-2-020 Contaminated Injured /Ill Personnel RevisionJ3/fS Knt?b , 1 1 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 personnel.
- 2. Serious injuries requiring medical treatment shall take precedence over decontamination of injured /ill personnel.
5.0 RRocEnuRE NOTE For life-threatening conditions, the Emergency Coordinator shall give the EFAT/HP immediate access to the victim. 5.1 IMMEDIATE ACTIONS AND NOTIFICATIONS Upon the determination that contaminated injured /ill personnel must be transported off site, the-Emergency Coordinator shall: 5.1.1 Direct the Emergency First Aid Team to treat victim (s) in ac-cordance with FP-2-200. l 5.1.2 Coordinate the activation of the EFAT with the OSC Supervisor when l
- - - ~
the OSC is manned. I l
- 5~.1.T~'Di'r'ect Health Physics personnel to support the Emergency First Aid -
Team in accordance with Attachment 7.5, Health Physics Responsibilities on Site. 3
l l
' ~
Emergency Plan Implementing Procedure EP-2-020 Contaminated Injured /Ill Personnel - Revision E3)$^*4 l 9%73 , 1 5 .1. 4 Direct'the Emergency Communicator (s) to notify the appropriate ambulance service (s) in accordance with Attachment 7.1, Ambulance Notification Checklist. 5.1.5 Direct the Emergency Communicator (s) to notify Ochsner Foundation T Hospital or West Jefferson General Hospital in accordance with At- r tachment 7.2 or 7 3, respectively, j 5.1.6 Direct the Emergency Communicator (s) to notify the Waterford 3 Security Shif t Supervisor in accordance with Attachment 7.4, Security Notification Checklist.
)
5.1.7 Request and coordinate additional support, as required (e.g., search and rescue, emergency repair, etc.). 5.1.8 Make contact with the Health Physics Superintendent-Nuclear or his
- designee and inform him/her of the event to ensure proper Health Physics staffing. Refer to EP-3-050.
5.2 FOLLOW-UP ACTIONS AND COMMUNICATIONS Upon the completion of the immediate actions and notifications of this procedure (section 5.1), the Emergency Coordinator shall: 5.2.1 Direct that Health Physics and Emergency First Aid Team personnel l move the victim (s) to a rendezvous point...(if req.uired) wher_e the. ambulance personnel can place victim (s) in the ambulance (s). NOTE In the event that severe injuries (e.g., l back injuries, severe bleeding) prevent the moving of victim (s), await assistance from ( , qualified ambulance personnel. l 5.2.1.1 Step 5.2.1 should be performed in accordance with Attachment l 7.2, Ochsner Foundation Hospital Notification Checklist, or 7.3, 4 l
r Emergency > Plan Implementing- Procedureatass " - EP-2-0202 '- Contaminated Injured /Ill Personnel Revision 23l7 '#
, 4V#
West Jefferson General Hospital Notification Checklist, and At-
~
tachment 7.5, 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., east side of RAB, Fuel Handling Building doorway, etc.) or loca-tion of victim to which Security will escort the ambulance person-nel. 5.2.3 Direct that Health Physics personnel escort victim (s) to Support Hospital (s). 5.2.4 Direct that Health Physics personnel provide assistance at the Support Hospital (s) ir. accordance with Attachment 7.6, Health p Physics Responsibilities at Support Hospital. S.2.5 Direct the Health Physics personnel to control potentially contaminated areas, equipment, and personnel involved with onsite response (e.g., personnel handling victim (s), area through which victim was moved. etc.) in accordance with Attachment 7 5, Health Physics Responsibilities On Site. NOTE Communications with ambulance can be maintained through the receiving hospital. 5.2.6 Direct the Emergency Communicator (s) to notify the Support Hospital (s) of any changes the Support Hospital (s) may not be l aware of (e.g. , changes in estimated time of arrival, condition of victim (s), number of victims, etc.). . 6.0 FINAL CONDITIOMS 6.1 Victim (s) are admitted to Support Hospital (s) and are under I professional medical supervision. l l 5
,2. Emergency Plan Implessnting-Precodurow:=w'-' -
EP-2-020 U Contaminated Injured /Ill Personnel Revisionf3lbf**# T/9/Y3 6.2 Health Ph'ysics personnel at Support Hospital (s) have all potentially contaminated personnel; areas, and equipment controlled in ac-cordance with Attachment 7.6, Health Physics Responsibilities at l . Support Hospital. - 7.0 ATTACHMFMTS 7 .1 Ambulance Notification Checklist ! i 7.2 Ochsner Foundation Hospital Notification Checklist i 7 .~ 3 West Jefferson General Hospital Notification Checklist ; 7.4 Security Notification Checklist 7.5 Health Physics Responsibilities On Site 7.6 Health Physics Responsibilities at Support Hospital e 6 __ . . l
i AMBUL AN CE4 NOTIFIC ATION- CHECKLIST: ccE iB , ! i (Notification via PABX Telephone) St. Charles Hospital Ambulance Dispatched.via.-St. 4harles f arish. Sherif f Dept. - Industrial or Operational Hot Line West Jefferson Hospital Air-Ambulance 1-800-182 4006 '
- 1) Emergency Communicator (name)
/ /
- 2) Time and date of call (24-hour clock) day mo. yr.
- 3) EOC Communicator on-line (name)
- 4) Repeat the following message: MY N AME IS . I AM THE (emergency position) AT THE WATERFORD 3 STEAM ELECTRIC STATION. WE NEED AMBULANCE SERVICE (S) FOR THE TRANSPORTA-TION OF CONTAMINATED INJURED PERSONNEL FROM WATERFORD 3
- 5) Then discuss the following information:
a) Number of victims b) Type of injuries (discuss) c) Contamination (circle) YES NO d) Type of contamination (circle) Skin Clothing Internal e) Gate ambulance is to enter (if known) (gate) , EP-2-020 Revision / 3 /cA*) / 7 Attachment 7.1 ( / of JD l 19119 i
AMBULANCE rNOTIFICATION -CHECRUISWM Ma~ l s) Method of transport (circle) Ground Air
- 7) Name of ambulance service (s)
(name(s))
. . . . . . . . ,.... .. ~
- 8) If Air Care is to be employed, the following transportation to the 4
Helicopter Landing Area is to be used: a) ESASCO ambulance 72-444 (circle) YES NO b) Security pickup (circle) YES NO c) Other available pickup (circle) YES NO
- 9) Additional Information EP-2-020 Revision /3ldk ,91 8 Attachment 7 1 (jk of jk)
Chl9
~
OCHSNER FOUND'ATI0tti HOSPITAL "NOTIFICATIOFCIlECKtIST'"" Ochsner Foundation Hospital Telephone # 818 1000
- 1) Emergency -Communicator (name)
/ /
- 2) Time and date of call (24-hour clock) day mo. yr.
- 3) Dial 828 1000 and, when answered, request the Emergency Department.
The operator will transfer you to the proper individual.
- 4) When the Emergency Department is on line, request his or her name and position ; then repeat the following message:
My name is . I am the (emergency position) at the Waterford 3 Steam Electric Station. We are preparing to transport contaminated injured personnel to your facility. Prepare your radiation emergency area.
- 5) Then discuss the following information:
a) Number of victims b) Type of injuries (discuss) 6 i c) Degree of contamination (circle) CPM MREM d) Type of contamination (circle) Skin Clothing Internal l EP-2-020 Revision /3lEA*-S I 9 Attachment 7.2 (/ ofjb) flSl33 l
0CHSNER FOUNDATION: HOSPITAL .NOIIEICAIIGN IlfECKLI" ~ ' - U - - -- ! e) First aid already administered onsite (discuss) f) Method of transport (circle) Ground Air NOTE If Air Care transport is to be used, ensur,e that site transportation is available in accordance with Attachment 7 1, section 8. g) Name of ambulance service (s) (names) h) Estimated time of arrival (24-hour clock) _ _ _
- 6) Inform the Emergency Department that 'daterford 3 Health Physics personnel will accompany victim in ambulance.
- 7) Inform the Emergency Department that he will be notified of any changes and give him your phone number.
- 8) Additional Information EP-2-020 Revision /3 leAwyl 10 Attachment 7.2 (2b of jl)
.189l9
WEST J EFEERSON . GENERALuHOSPITAE3 NOTIFICATIONI-CHECKDISP-LE - ' w- ~ 2, West Jefferson Hospital Telephone # 800-182 u006
- 1) Emergency Communicator (name)
- 2) Time and date of call / /
(24-hour clock) day mo. yr.
- 3) Dial 800 '82 u006 and, when answered, repeat the following message:
My name is . I am the (emergency position) at the Waterford 3 Steam Electric Station. We are preparing to transport contaminated injured personnel to your facility. Prepare your radiation emergency area, and request the Emergency Department. i 4) When the Emergency Department is on line, request his or her name and,
- 5) Repeat your message: My name is . I am the (emergency position) at the Waterford 3 Steam Electric Station. We are preparing to transport contaminated injured personnel to your facility.
Prepare your radiation emergency area.
- 6) Then discuss the following information: _ _ _ _ . , , _ ,____
7)---Number of victims - - - - - - - -
~
-~
-"-~---b)-Mype of injuries (discuss) ------ --
EP-2-020 Revision /3 l(-Q l 11 Attachment 7 3 (/ off) Clsith i l
. UEST JEFFERSON -EENERAbHOS2IhMOTIFICAT, ION CHECKLIS&M '-ri? "C ~iA ---
c) Degree of contamination (circle) CPM MREM d) Type of contamination (circle) Skin Clothing Internal e) First aid already administered onsite (discuss) f) Method of transport (circle) Ground Air NOTE 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)
.. . - . . . . (names.)i + u.- --- - - -
h) Estimated time of arrival (24-hour cleck)
- 7) Inform the E=ergency Department that 'daterford 3 Health Physics personnel will accompany victim in ambulance.
- . 8) Inform the Emergency Department that he will be notified of any changes and give him your phone number.
- 9) Additional Information EP-2-020 Revision 1316l'"44# 12 Attachment 7.3 (2 of 2)
J*hl13 i l 1
~
SECURICKOTIFICITIUff?CHECXCTSF*#N~ " ' 7 ~ '~- 'I l} Emergency Communicator (name) ;
/ /
- 2) Time and date of call (24-hour clock) day mo. yr.
- 3) Name of Shift Security i Supervisor on-line (name)
- 4) Repeat the following message: MY NAME IS . I AM THE (emergency position). WE REQUEST SECURITY SUPPORT TO AID IN THE PREPARATION OF THE TRANSPORT OF CONTAMINATED INJURED PERSONNEL TO THE HOSPITAL (S).
- 5) Then discuss the following information:
a) Location of victims (discuss) ' b) Number of victims l c) Gate ambulance snall enter site (discuss) (gace) . . d) Method of transport (Circle) Ground Air e) Estimated time of arrival I (e4-nour clocx> f) Name of ambulance service (s) (name> g) Security pickup needed for transport to the Helicopter Landing Area (circle) YES NO h) Other Security support (discuss) ___ .._ _6) .Additiona1 Information .__. . . .
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EP-2-020 Revision 13jd / 13 Attachment 7 4 ( / of / )
HEALTH ~PHISICS:RESPONSIBILIIIES_.ON:SITEr urr
- 1. Notify the Emergency Coordinator of radiological conditions associated with the victim, including-
- a. Approximate contamination levels on victim and nature of contamination (i.e. , skin, clothing. internal uptake)
- b. If overexposure has occurred or is possible due to the victim's location
- c. If ambulance personnel are required to be issued TLD's and protective clothing prior to gaining access to the victim (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 available for ambulance personnel upon arrival on site i '
l 1
~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 necessary under part le above.
- --- - --5 . --- E n s u re- th a t the Health Physics technician escorting the victim to ~~ ~
the-hospital is not contaminated. Control at the hospital-~ill'l Fe
- ~'
extremely difficult if the Health Physics technician Is-~Fe~stricEWd~ -- l --- -----due to his/her own contamination. - - - ~ ~ - ~ ' - ~ ~ ~ - - ~ ~ - ~ EP-2-020 Revision 23 f 6kmg/ 14 Attachment 7.5 ( [ of / ) l 4/%l$3
HEALTH PHYSICS RESPONSIBILITIESi ATISUPPdRT?'HOSPITAGM3E '- - - - 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 measures upon arrival at the support hospital:
- 1. Instruct the ambulance driver to close the ambulance after the victim has been 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 ac-cess, 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 personnel or request hospital staff to monitor under your guidance. 4 Check hospital staff for proper dosimetry and protective clothing. i Close out the incident as follows:
- 1. Ensure that all involved personnel 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 necessary, and package contaminated waste (all final surveys must be documented).
- 4. Return contaminated waste to Waterford 3 EP-2-020 Revision /3/LAa5d/
15 Attachment 7.6 (/of2) 4hl0
HEALTH PHYSICS- RES PONSISILITIES t.AT ' SUPPORT 1HOSRITXCC : L J-- '
- 5. Notify the Emergency Coordinator of the final status of ambulance / ambulance personnel.
Personnel Exposures Personnel Contamination and Current Status Equipment Contamination and Current Status Material being returned to Waterford 3 for decontamination or disposal __ ...- . . . . : .. ~ - -. I t l l EP-2-020 Revision /3/C / 16 Attachment 7.6 (I of 2) i J/1/3 EXTED Process?
WATERFORD 3 SES PLANT OPERATING MANUAL
$ LoulSIANA POWER & LIGHT UUNSYSE EP-2-030 POM VOLUME 18 REVISION 1 POM SECTION 2 APPROVAL DATE:
EFFECTIVE DATE: EMERGENCY PLAN DIPLEMENTING PROCEDURE a EMERGENCY RADIATION EXPOSURE GUIDELINES AND CONTROLS LP&L W-3 RECORDS CONTROLLED COPY No.OS$ PCRC Meeting No. f3 -01 d Reviewed: E
.- RC Cha man l' App roved: "* U. L h Plant Manager-Nuclear 1
l l
l 1 WATERFORD 3 SES l
/S PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. t 0-f 8(:- TiL1ek?': r <' :'<< Nh-brh%- b vr = -b:, A/i,Li ial Effective Date (if differ'ent[ from PM-N approval date) bM/
Chmnlete 1.- B . e r* C A. Change No. NM B. Revision No. / C. Deletion ev /4 gr ASON FOR CM1NGE. REVISION. OR DELETION -
/dOB]i, ,; if //m.ov s-/r,Yl< lcn?/-b-i-*k'%' *
/ ;//' ? '/ '?f - ~
, l -y,.m ~ rd!.y, R., % s s%.. //&'s,.,,. r ,fe. -_ in i , 'l- - N- - - -
REQUIRED SIGNATtfREE
-l
/ 'l Originator I Date ))-l b 3 ' ---
Technical Review A f b b MY- - Date - O ' dD- - V 1 SAFETY EVALUATION
,3 Does this change, revision, or deletion: YES NO
- 1. Change the f acility as described in the FSAR? e--
- 2. Change the procedures as described in the FSAR? -L
- 3. Conduct tests / experiments not described in the FSAR? -
~L-
- 4. Create a condition or conduct an operation which ex- "
l ceeds, 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 Safet- evaluation checklist. Date M -7 Safety Evaluation A/ -- - - Group /Dep't. HeadReviN C/ O bd - Date ll~/ 7O - 4 i Temporary Approvala -- -- - -- Date - (NOS) Temporary Approval * --- Date - - QC Revieu - d W Y ; P- - ' ------- Date - */~ U ~9 ~ - - - PORC Review Y O d \- Date I -l 'l-M ' - - Meeting No. fNit -- Plant Manager Nuclear Approval -e MED - --- Da te 6B-
/ - - - -
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
l l UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Proce.durc EP-2-030 Emergency Radiation Exposure Guidelines Revision 1 l and Controls TABLE OF CONTENTS 1.0 PURPOSE i
2.0 REFERENCES
3.0 RES PONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Emergency Exposure Authorization Form (2 pages) 7; LIST OF EFFECTIVE PAGES Title Revision 1 1-7 Revision 1 1
9 Emergency Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 1 and Controls 1.0 PURPOSE To provide guidelines and administrative controls for radiation ex-posures in excess of 10CFR20 limits during life saving or accident-mitigation 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 2.3 National Council on Radiation Protection Report No. 39, Basic Radiation Protection Criteria 3.0 RES PON SIBILITIES 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: 4.1 Defined emergency response actions to perform life saving or ac-cident-mitigating functions are expected to result in radiation ex-posures in excess of the 10CFR20 limits. 5.0 PROCEDURE NOTE The Emergency Coordinator is the only indivi-dual who can authorize emergency exposures in excess of 10CFR20 limits. 2
Emergency Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 1 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. 5.2 The guidelines for emergency exposure are: Organ Corrective Action Life Savine Whole Body 25 rem 100 rem Extremities 100 rem 300 rem Thyroid 125 rem 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 or professional rescue person. 5.3.2 Individual is generally familiar with the radiological consequences of the exposure. 5.3.3 Fertile females shall not be used. l 5.3.4 Individual has not previously received emergency exposure. 5.4 Personnel shall not enter any area where dose rates are unknown or unmeasurable with doce 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. 3
Emergency Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 1 and Controls NOTE
- 1. The Emergency Coordinator 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.
5.7 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 equivalenc exceeds 10 rem for the whole body, 30 rem for the thyroid, 60 rem for the skin, and/or 150 rem l 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. 5.8.2 If an individual's dose equivalent exceeds 25 rem for the whole body, 75 rem to the thyroid, 150 rem for the skin, and/or 375 rem 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 4
Emergency Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 1 and Controls report on the emergency exposure, including necessary reports in ac-4 cordance with 10CFR20.403. 6.0 FINAL CONDITIONS All sections of Attachment 7.1 are complete and assignments have been made for completing necessary exposure reports. 7.0 ATTACHMENTS f 7.1 Emergency Exposure Authorization Form l l I 5 l
EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION A
- 1. Name (to receive exposure):
Soc. Sec. No.:
- 2. Individual TLD Number: Employer /LP&L Department:
3 Task (s) to be Performed:
- 4. Date of Authorization: Authorized Limit:
5 Conditions: Individual is a volunteer or professional rescue person. Individual is broadly familiar with radiological consequences of ex-posure. Fertile females shall not take part (Reg. Guide 8.13). Individual has not received an emergency exposure before. Dose rates in area are known/ measurable. Life saving Action? Corrective Action?
- 6. Emergency Coordinator; (signature)
SECTION B I have been briefed in the radiological consequences of the proposed emergency exposure, and I have volunteered to perform the emergency measures during which I will receive the emergency exposure. 7 Signature: Date: EP-2-030 Revision 1 6 Attachment 7 1 (lof.2)
EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION C (Attach exposure evaluation)
- 1. Dose equivalent assigned for entry:
- 2. TLD/ Dosimeter Results:
3 Bioassay Results:
- 4. Medical Evaluation / Action:
Doctor: 4 5 Radiological Controls Coordinator: Date: SECTION D
- 1. - Disposition (Allow additional exposure, restricted access, etc.):
- 2. Individual assigned to follow up reports (s):
- 3. Radiological Controls Coordinator: Date:
i 1 EP-2-030 Revision 1 7 Attachment 7.1 (d of d)
WATERFORD 3 SES PLANT OPERATING MANDAL l OUISIANA POWER & LIGHT NSY EP-2-031 POM VOLL'ME 18 REVISION 2 POM SECTION 2 APPROVAL DATE: May 2, 19f3 EFFECTIVE DATE: Fuel Load DIERGENCY PLAN IMPLDfENTING PROCEDURE IN-PLANT RADIOLOGICAL CONTROLS DURING DIERGENCIES Lpat. W-3 S I L CONTRE .sj O'i> NO, ' - PORC Meeting No. 73-/'1 4 ! Reviewed: - 4 om ~ l F RC Chaiisan Approved : ' O ISE Plant Manager-Nuclear G
l
. I l
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 59'2-03' Title A-M PM bM Ov-w Effective Date PJ LM (if different from approval date) h cannista 1. B. or. C A. Change No. B. Revision No. 2 ' C. Deletion N/A RFAMON FOR CHANCE. REVISION. OR DFLFTION Tc /e O b_.-da uh r w L 6
~
Nat c M MEOUTRED STCN ATUMES Originator 0- Date V Technical Review b bh - " Date 4/5l8 ) Q SAFETY EVALUATION Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR?
, 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- '
ceeds, 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 b8bd Date 4-5-T A Group /Dep't. Head ReviN k O b b Date V-s -g 3 v i Temporary Approval
- Date (NOS)
Temporary Approvale Date QC Review / J'd M ' b la--- Date MM 3 PORC Review 2.<? N - Date MM Meeting No. 73-M 4 Plant Ma edNuclearApproval 'MY Date a/4 +
' 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 y,y,y- - . - - . - - ,e._-,_-s -
-- - , ___,,._g ._w,, - - . _ _ _ _ ___m_ _ _ _ _ _ _ _
Emsrgancy Plan ImplGmsnting Procs. dure , EP-2-031 In-Plant Radiological Controls During Revision 2 Emergencies TABLE OF CONTENTS 1.0 PURPOSE 2.0 REFEREN CES 3.0 RES PONSIBILITIES 4.0 IIIITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS
~
7.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 2 1-8 Revision 2 6 a e e l l l l t 1 r. r
Emsrgency Plan Implcmanting Procsdure EP-2-031 In-Plant-Radiological Controls During Rcvision 2 Emergencies 1.0 PU R POSE ' 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 REFEREN CES 12 . 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) Activation, Operation, and Deactivation 3.0 RES PON SIBILITIES The Health Physics Coordinator and/or the Radiological Controls Coordinator is responsible for implementing this procedure.
\
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
~
4.3 In the judgement of the Health Physics Coordinator and/or the Radiological Controls Coordinator, normal Health Physics procedures would restrict the response capabilities necessary to mitigate the consequences of the emergency condition. 2
r# ~ ~ ,1 f, t
} i,Rovision Emcrgoney Plan Impicacntthg Proccdure EP-2-031 In-Plant Radiological Jontrols During
/ 2 Emergencies /., .I
/,'
f, - , , 5.0 PROCEDUR?, ' 5 .1 During emerg'ency conditions, the Health Physics Coordinator and/or the Radiological Controls Coordinator will evaluate the potential radiological hazard with,in the plant and the maintenance and operations 'necessary t'o ' mitigate thej consequences of the incident. 5.2 If, in the opinion of the Health,,Phyr.ics'Coordin'ator and/or Radiologiaal Controls Coordinator, the normal Health Physics procedurer will not support the energency response in any specific area or in all. areas in general, the Rad'iological Controls Coordinator will consider the following guidelines in place of any
- normal Health Physics procedures.
NOTE The objective of emergency radiological controls is to utilize as many of the normal Health Physics procedures and practices as practical. If any of l the following guidelines are implemented, normal
~
Health Physics proceduies should be reinstituted as soon as practical. 5.3 The following guidelines are established in a checklist format with discussion as to how each should be implemented. The Radiological Controls Coordinator will determine which of the guidelines will be
' implement ed. Specific individuals shall be assigned by the Radiological Controls Coordinator as necessary to implement the following guidelines: ,
5 3'.1 AccerbControl ' 5.3.1.1 ,Petentiall Problem: Hormal Access Control Point (s) does (do) not
' provide e'dequate control over access and egress to the affected i r .
a'es r due to significant radiological hazards within the Reactor
; , ,, y '
~ <
r . ' _ , - t
.. s
~
' }, .
3 , e! s f i, ,-
Emsrgoney Plan Inple2Gnting Procsduro EP-2-031 In-Plant Radiological Controls During Rovisicn 2 Emergencies Auxiliary Building, or the affected area includes areas not normally controlled for radiological purposes. 5 3.1.2 Guidelines: Through evaluation of the operational and
- radiological aspects of the incident, re-establish access control points to encompass the entire affected area. For areas of significant radiological hazard (greater than 1 R/hr, greater
. than 100 times MPC, greater than 100,000 dpm/100 cm a9, evaluate all possible access routes into the area and ensure that each is positively controlled by:
A. Posting personnel to restrict access
~
B. Locking access doors or gates 5.32 Control Point operations 5.3.2.1 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. 5.3.2.2 Guidelines: Control Point personnel will brief individual (s) prior to entering the affected areas, using Attachment 7.3 of EP-2-101. 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 of minimizing exposure are understood. Control Point pe'rsonnel will debrief persuit ' ex-iting the affected area, using Attachment 7.4 of EP-2-10;, The briefing will identify the exposure received by each individual; contaminated personnel are identified and directed to appropriate decon facilities for decontamination in accordance with EP-2-032, and dose rates and other radiological hazards encountered during the entry are identified and documented.
-. 4
Eccrgency Plan Impicmanting Procaduro EP-2-031 In-Plant Radiological Centrols During RGvision 2 Emergencies 5.3.3 Radiation Work Permits 5.3 3.1 Potential Problem: Normal administrative requirements of RWP's would restrict critical operations and maintenance activities
. aimed at mitigating the consequences of the emergency.
5.3.3.2 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 Control Point personnel and used in conjunc-tion with the briefing and debriefing forms, Attachments 7.3 and
. 7.4 of EP-2-101.
NOTE RWP's will normally be filled out prior to entry into an affected area when time permits. During an emergency wh3n time does not permit the filling out of an RWP. the
- ~
briefing, debriefing ahd Control Point Log will be used in lieu of an RWP until an RWP can be completed. 5.3 4 Respiratory Protection 5.3.4.1 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. 5.3.4.2 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. 5 l i L
Encrgsney Plan Implementing Procodure EP-2-031 In-Plant Radiological Controls During Revision 2 Emergencies All individuals entering the affected area shall be identified for subsequent bioassay analysis to determine internal exposure. 5.3 5 Bioassay Program 5.3.5.1 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 5.2 Guidelines: Personnel exiting areas of significant or unknown airborne radioactivity should be directed to the individual responsible for bioassay analysis by the Control Point personnel. Lists of personnel requiring bicassay analysis shall be forwarded by the Control Point personnel to the individual responsible for bioassay to ensure all individuals requiring evaluation are properly evaluated. For individuals who have received uptakes in excess of a Derived Investigation Level, follow-up evaluations will be scheduled. For individuals who have received in excess of 50% of a body or organ burden, the Radiological Controls Coordinator and Health Physics Coordinator shall be notified to determine the need for medical consultation. Any individual who has in excess of a Derived Investigation Level shall be restricted from reentry into the affected area without the approval of the Radiological Controls Coordinator or Health Physics Coordinator. 5.3.6 Radiological, Surveys 5.3.6.1 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 rely on previous data for purposes of estimating exposures on subsequent entries. 5.3.6.2 Guidelines: Surveys will be performed in conjunction with entries for specific maintenance and operations tasks. Control 6
- ~ + e -- e+-- - -n -
i Emsrgency Plan Impicmsnting Procsdurs EP-2-031 In-Plant Radiological Controls During Rcvision 2 Emergencies 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. NOTE Dose rates and airborne activity levels deter-
~
mined during one entry should be considered as estimates for futura entries but shall not substitute for continuous monitoring during those subsequent entries. 5.4 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 Administration / Logistics Manager at the Corporate Command Center. 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. 1 6.2 A recovery Health Physics organization is established and implemented, if necessary. l 7 \
~. . . . _ ~ ~ ... . . . ..-. _-.-..- , . -,.- ._. - .. . . . _ _ _
Emsrgsney Plan Implementing:Procsdure- EP-2-031 In-Plant Radiological Controla During Revisicn 2 Emergencies 4. 4 t 7.0 ATTAc m MTs ! ! NONE-4- , !' I i t r t 1 1 1 f a ! 4 1 1 , t - i ? i i j - l 3 v i i ! I - l'
-- 8 r evein o.....in
, . . , . , , . , _ - ,n. , , -- .,..,-w,....-wr_,-_... . , , - , . . ,. .w,,-,,_,.,q.,. ,_-n.,,-. ,, .,~ ,,,. ,. , .s- n _ __ _._ .-+ _ . , ..._..n_n..__._ - .__. _
WATERFORD 3 SES - PLANT OPERATING MANDAL LOUISIANA M100LE SOUTH UT1UTIES SYSTEM EP-2-032 PCM VOLUME 18 REVISION 2 g PCM SECTION APPROVAL DATE: M3v 2. iog3 EFFECTIVE DATE: Fuel Load DIERGENCY PLAN DIPLEMENTING PROCEDURE MONITORING AND DECONTMfINATION LP&L W-3 ITECOF.DS CONTRu_., tt..c u C0PY NO. b! PORC Meeting No. 93-p74 w_ Reviewed: / ,, m [PQRCChir=an App roved: d l'nq !!f$$h . _ _ . _ _ _ _ _ _ _ _ Plant Manager ' Nuclear
~
, WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 69-1-071 Title h _C' d b mCl-ri Effective Date F'tud L -J (if different front approval date)
Camelete 1. B. or C A. Change No. ~b B. Revision No. 1 C. Deletion "/A REAMON FOR CHANCE. REVTSTON. OR DELETTON ,
'T- Ee N OewL t.~2_o L% al-o tu d
~ k a Y - L ,. cA A.)R C + AW', -
J REOUTMED STCNATURES Originator b- kh Date 22b
-yTechnical Review M#dd t-Date MMM ~
( - SAFETT EVALUATION Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR7 7
- 2. Change the procedures as described in the FSAR7-
~
X
- 3. Conduct tests / experiments not described in the FSAH7 '
- 4. Create a condition or conduct an operation which ex-
/
ceeds, 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 b 8 0 "'O'1 Date 4-IIN Group /Dep't. Head Review $8NA u Date 'f ' /I - 8 t 1 Date Temporary Approval * (NOS) Temporary Approval
- Date
~
QC Review -
#A 8tW M u Date NWM PORC Revi bI2 *a- - Date 4M6 Meeting No. P3 - 3 74 PlantManage[-NuclearApproval '*/4 Date "M "?"
- 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 (o
---) " m.. _ .m
. Emergency Plan Implementing Pr'ocedure EP-2-032 --
Monitoring and Decontamination Revision 2 TABLE OF CONTENTS 1.0 PURPOSE
^
12 .0 REFEREN CES 3.0 RES PONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5 .1 Onsite Personnel Monitoring and Decontamination 5.2 Offsite Personnel Monitoring and Decontamination , 5.3 Vehicle Monitoring and Decontamination e 6.0 FINAL CONDITIONS - 7.0 ATTACHMENTS
- 71 Skin Decontamination Record (2 pages) 7.2 Vehicle Decontamination Record (1 page)
LIST OF EFFECTIVE PAGES Title Revision 2 1-10 Revision 2 9 9 ** Am eo em o m e 1
Emergency Plan Implementing Procedure EP-2-032 __ Monitoring and Decontamination Revision 2 1.0 PURPOSE To provide guidance and instruction for the decontamination of Waterford 3 personnel and vehicles and for the documentation and follow-up on those contamination incidents during emergencies when the normal plant Health Physics procedures can no longer be ef-fectively implemented.
2.0 REFERENCES
2.1 EP-2-031, In-Plant Radiological Controls During Emergencies 2.2 EP-2-150, Emergency Records 2.3 EP-3-040, Emergency Equipment Inventory 2.4 EP-3-050, Emergency Response Call . List . 2.5 HP-2-704, Personnel Decontamination ' 2.6 HP-1-220, Bioassay Prog' ram 30 RESPONSIBILITIES The Radiological Controls Coordinator is responsible for ensuring the implementation of this procedure. The assigned Decontamination - Supervisor is responsible for implementir e procedure. 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, personnel and/or vehicles are or are suspected to be contaminated. 4.2 As directed by the Emergency Director or Health Physics Coordinator. 2
l Emergency Plan Implementing Procedure EP-2-032 __ Monitoring and Decontamination Revision 2 5.0 PROCEDURE 5.1 ONSITE PERSONNEL MONITORING AND DECONTAMINATION , 5.1.1 The Radiological Controls Coordinator shall assign a Decontamina-tion Supervisor for onsite personnel monitoring and decontamination. This individual can be a Health Physics supervisor, engineer,- or technician and can eventually be a consulting Health Physicist. 5 .1. 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 Auxiliary Building (RAB). A backup facility is located on , the +7 ft elevation of the RAB. , Monitoring equipment and person-nel decontamination kits are located in the Health Physics Laboratory. , 5.1 3 All personnel with contamination levels in excess of 1,000 - disintegrations per minute (dpm) as determined by a pancake-type Geiger Muller.(GM) tube shall be considered contaminated. 5.1.4 The Decontamination Supervisor shall: , 5.1.4.1 Assign control point monitors to perform monitoring of all personnel leaving affected areas. 5.1.4.2 Direct 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 1,000 dpm are unsuccessful, contact the Health Physics Supervisor or Health Physics Superintendent-Nuclear for further guidance. 3
Emergency Plan Implementing Procedure EP-2-032 __ Monitoring and Decontamination Revision 2 5.1.4.6 Record all predecontamination and postdecontamination informa-tion on Attachment 7.1, Skin Decontamination Record. 5.1.4.7 Return all records to the Radiological Controls Coordinator. 5.2 0FFSITE PERSONNEL MONITORING AND DECONTAMINATION 5.2.1 The Radiological Controls Coordinator shall assign a Decontamina-tion Supervisor for offsite 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 as determined by a pancake-type GM tube shall be considered contaminated. , 5.2.4 The 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 to the Decontamination Supervisor. 4 I-
Emergency. Plan Implementing Procedure EP-2-032 -- Monitoring and Decontamination Revision 2 I 5.2.4.5 Direct all contaminated personnel to be decontaminated with the i portable decontamination kit using the techniques of HP-2-704, Personnel Decontamination. 5.2.4.6 If attempts to decontaminate personnel to levels below 1,000 dpm l are unsuccessful, contact the Health Physics Supervisor or the I Health Physics Superintendent for follow-up decontamination. 5.2.4.7 Record all predecontamination and postdecontamination informa-tion on Attachment 7.1, Skin Decontamination Record.
~
5.2.4.8 Return all records to the Radiological Controls Coordinator. 5.3 VEHICLE MONITORING AND DECONTAMINATION 5 3.1 The Radiological Controls Coordinator shall assign a Decontamina-tion Supervisor for vehicle monitoring and decontamination. ihis individual can be a Health Physics supervisor, engineer, or technician. 5.3.2 All vehicles with contamination levels in excess of 1,000 dpm/100 ! cm' shall be considered contaminated. l 5.3 3 The Decontamination Supervisor shall: 5.3.3.1 Obtain a portable radio from the OSC HP locker and perform a radio check. 5.3.3 2 Assign emergency response personnel to obtain monitoring equipment and portable radios from the OSC HP 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. 5
Emergency Plan Implementing Procedure EP-2-032 _ Monitoring and Decontamination Revision 2 NOTE 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 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). NOTE I Masslinn cloths (or equivalent) are located at the Health Physics Laboratory, Site 'darehouse and in I portable decontamination kits. 5337 If attempts to decontaminate vehicles to levels below 1,000 dpm are unsuccessful, detain the vehicle for additional decontamination. 5.3.3.8 Record all predecontamination and postdecontamination informa-tion on Attachment 7.2, Vehicle Decontamination Record. 5.3.3.9 Return all records to the Radiological Controls Coordinator. 5.4 Instances of skin contamination involving real or suspected internal deposition of radionuclides will be handled in accordance with HP-1-220, Bioassay Program (Reference 2.6). 5.5 Personnel and vehicles shall be considered fully decontaminated when l levels are less than 1,000 dpm (less than 1,000 dpm/100 cm 1 for vehicles). 6
Emergency Plan Implementing Procedure EF-2-032 -- Monitoring and Decontamination Revision 2 6.0 FIN AL CONDITIONS 6 .1 All personnel and vehicles identified as contaminated have been _ decontaminated or have been detained for further evaluation and possible additional deco,ntamination. 6.2 All records are in accordance with EP-2-150, Emergency Records. 6.3 Normal Health Physics procedures for decontamination are fully implemented. 7.0 ATTACHMENTS 7 .1 Skin Decentamination Record , 7.2 Vehicle Decontamination Record e e D l l 7 l
* ~
HP- AD
- OTYPE C 7.18
'. SKIN DECONTAMINATION RECORD HAME OF CONTAMINATED INQlV! DUALS .
(FIRST) fe8tOOLf1 (L AST . sSNs TLD NO. EMPLOTER/L.P. & L. DEPT.8 . DATE AND TIME OF CONTAMINATION OCCURRENCES s RWP ,NO WORKING UNDER WHEN CONTAMINAl! C STATION LOCATION WNERE CONTAMINATION OCCURREDs APPARENT CAUSE OF OCCURRENCE: HP SUPERVISOR NOTIFIEDs CNO OTEs INJURT INVOLVEDs
*- O NO OTEs (Empi.i ) ,
MEDICAL ASSISTANCE OBTAiNEDs , NO OTEs (Ei,torab
~_"
FACIAL CONTAMINATION:
-=
ONO OTEs (Espiot.> 1
. NASAL SMEARS TAKENs 4,. LT NOSTRit e,.
ONO OTEs RT NOSTRit s. DATE AND TIME DECON BEGANs I l DATE AND TIME DECON COMPLETED:
-- - .-a a..4 4-- 9 J' ttt;aCGment t.A (1 07 d
SKIN DECONTAMINATION RECORD (CON'T) LOCATION OF CONTAMINATION (INDICATE ON APPROPRIATE SKETCH OR SKETCHES) OLEFT I HANO,5ACK g' I ORT. HAND, PALM L , . I M 8:A f ( O. I O RT. HAND, , OE HAND, h V FACE FRONT BACK DECONTAMI. NATION DATA CONTAMINATION LEVEL CONTAMINATION LEVEL U " IU
- CONTAMINATED BEFORE BEGINN!NG' TH!S AFTER COMPLETJNG THIS SKIN LOCATION OECON CYCLE (cpm)
DECON CYCLE (:pm) s
- l
_t l e' / .
. FURTHER ACTIONS REQUIRED: O NO O:rES SKIN CON 0lTION AFTER DECON:
(EXPL AIN) BICASSAT REC'Os C NO ,0TES ' O WBC O THYRO!D SCAN O EXCRETA O OTHER: _ _ , _,
~~ _ _ . . _ . . _ . . _ _ .
REMARKSs
'^ ~
REYlEWED BT DISTRIBUTION: HE ALTH PHYSICS OFFICE (ORIGINAL) INDIVIDUAL'S EXPOSURE Fit.E HE ALTH PHYSICS ENGINEER
-a a ae, n .4,4 .2. / -
Attachment 7.1 (2 of 2)
' ~
VEHICLE DECONTAMINATION RECORD __ MODEL: LICENSE f: COLOR: OWNER: E:
'IF OWNED BY OFFSITE AGENCY, PRINT DEPARTMENT AND ADDRESS:
STATION LOCATION WHERE CONTAMINATION OCCURRED: TYPE OF WORK BEING PERFORMED: l APPARENT CAUSE OF OCCURRENCE: { I BODY DAMAGE TO VEHICLE 7 YES NO HEALTH PHYSICS SUPERVISOR NOTIFIED 7 YES NO explain DATE AND TIME DECONTAMINATION BEGAN: DATE AND TIME DECONTAMINATION COMPLETED: , I. 2
- A i
\\ } (a f i
~ _ _
/
( u o - DECONTAMINATION DATA Contamination Level Decontamination Contamination Level Contamination Before Beginning this . Technig'ue and ' After5egi6ning this Decon Cycle (dpm) . Agent Used . Decon Cycle (dpm)- Location .. .. .._. _
,. I i
FIISTHER ACTION REQUIRED? Remarks: 6 _YES NO kr. VIEWED BY: EP-2-032 Revision A - g_ Attachment 7.2 (1 of I) h
WATERFORD 3 SES PLANT OPERATING MANDAL
.s
# LOUISIANA MICOLE SOUTH UT!UTIES SYSTEM EP-2-033 POM VOLUME 18 REVISION 1 POM SECTION 2 APPROVAL DATE:
EFFECTIVE DATE: EMERGENCY PLXi IMPLEMENTING PROCEDURE ADMINISTRATION OF IODINE BLOCKING AGENTS LP&L W-3 RECORDS CONTROLLED COPY NO. O b , 1 PORC Mee ing No. 93 - C 2 3 ' Reviewed: k I? CRC Ch ir:::an _ 1 Approved: - '\ P2. ant Manager-Nuclear c. l
WATERFORD 3 SES N PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. -bl 0*L' D Title $ n'a W A m S E d m ddu ' extb Effective Date (if different from pH-N approval [ ate) Cbmniete 1. B. or C A. Change No. W1 B. Revision No. / C. Deletion MJ RF AEON FOR CM1NGE. REVISION. OR DELETION s .
- b /0
- f .z:!;-l a/Yi u h) //- l//.S thhmy'Y - *? ! c V -h% ;3,rl - ~
No -A ~.c (lt i,k., R ,3r_p <w I / 6 rrj-A7y: 17s ~ , I6 - --
'l / 'l "/ 1 REQUIgrD SIGNATUkEV originator N .- 1 Date H r *1 D- -**-
Technical Revipw 4 h Ma - -'
- Date Ib I 4' S ' -
o - SAFETY EVALUATION
- ,Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR7 c-
- 2. Change the procedures as described in the FSAR? u
- 3. Conduct tests / experiments not described in the FSAR7
- 4. Create a condition or conduct an operation which ex- u ceeds, 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 b bb - -- - Date b b8~2--- -- Group /Dep't. HeadReybew M 0 %.Sem - Date I/'/f-I' '- U i Temporary Appr.ovain , --- -- - -- Date - (NOS)
- -' -- - ~ -- - - ---
Temporary Approval' Da te - - QC Revieu W W Y Y $ u V - -- - ------- D a t e - h* / -3 ~ f 3 - ~ - - PORC Review Mk kN- Date 1 -l 1 -S S ' - -- Meetin No . -N~ t'2 # - - Plant ManagerI N uclear App) oval b M b-5sh -~- - Date /M- ----
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
. - - - - ... ..m_.--e,.,, ep... _
,_,.g ---% - -,-,-m-----,rw--
Emergency Plan, Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 l 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 1 1-9 Revision 1 1
Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 J 1.0 PURPOSE To provide the guidelines for determining when potassium iodide (KI) should be administered to site personnel to minimize I-131 intake and for implementing and recording the administering of potassium iodide (KI).
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 NCRP Report No. 55, Protection of the Thyroid Gland in the Event of Releases of Radiciodine 2.3 IAEA Technical Report No. 152, Evaluation of Radiation Emergencies and Accidents 2.4 Patient Package Insert for Commercial Packaged Potassium Iodide 2.5 EP-3-040, Emergency Equipment Inventory 2.6 Appendiy I, Waterford 3 Emergency Medical Assistance Plan (EMAP) to Waterford 3 Emergency Plan 2.7 EP-2-020, Contaminated Injured /Ill Personnel 2.8 EP-2-150, Emergency Records 30 RES PON SIBILITIES The Health Physics Coordinator is responsible for the implementation of this procedure. 4.0 INITIATING CONDITIONS This procedure shall be initiated upon reaching the following condition: The Health Physics Coordinator determines that exposure to I-131 may result in quantities sufficient to cause a thyroid dose equal to or greater than 10 rads. 2 L _____,s
4 Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 5.0 PROCEDURE 5.1 Determine the need for KI administration by using Attachment 7 1, Thyroid Dose Graph. NOTE KI is not to be used in lieu of proper respira-tory protection (i.e., as a prophylactic). KI is to be used only to block the thyroid gland prior to/after unavoidable exposure or after acci-dental exposure to radiciodine. 5.1.1 Verify and record the calculations / measurements / estimates on At-tachment 7 3, Potassium Iodide Administration Form. 5.1.2 Report the results to the Emergency Coordinator. 5.2 If the thyroid dose is estimated to be 10 rads or greater (the minimum dose for KI administration), the identified physician at Ochsner (see Emergency Call List) and the Emergency Coordinator must be consulted to determine the need to order administration of KI. NOTE If communication cannot be made to the Ochsner physician, proceed to determine the need to order administration based on verified calculations and consultation with the Emergency Coordinator. 5.3 Upon authorization by the Emergency Coordinator, for the administration of KI to the appropriate individuals, perform the following steps. 5.3 1 Note the authorization in the Control Room Log. 3
Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 5.3.2 Direct the First Aid Team to report to the KI Administration Area to administer KI. (KI is located in the First Aid Area and First Aid Kits.) 5.3.3 Notify the consulting physician at Ochsner of the administration order. NOTE This may be unnecessary if consultation was recently completed and/or the notification must be delayed due to conditions / duties. 5.3.4 Assign one or more escorts to transport and assemble the individual (s) at the KI Administration Area. 5.3.5 Verify the above transport. 5.4 Have the First Aid Team direct the exposed individual (s) to read At-tachment 7.4, Potassium Iodide Precaution Leaflet and sign At-tachment 7.3, Potassium Iodide Administration Form. This is to verify that the individual (s) read and understand the leaflet and understand the taking of KI to be voluntary. 5.5 Issue one KI tablet to each individual each day for a minimum of six l (6) to a maximum of ten (10) consecutive days and record on At- , tachment 7.2, KI Issue Record. l I NOTE Unless medical personnel are available, only the First Aid Team administers KI. KI shall not be administered to anyone suspected of iodide allergy. 5.6 Forward all completed forms to the Emergency Coordinator for keeping. 4 1
Emergency Plan Implementing Procedure
- EP-2-033 Administration of Iodine Blocking Agents Revision 1 5.7 Direct a whole-body count and/or bioassay analysis be performed on each individual at the earliest opportunity and that the consulting Ochsner physician (s) provide supervision and verification of its completion to the Em&rgency Coordinator.
6.0 FINAL CONDITIONS 6.1 Each individual whose estimated exposure to radioiodine exceeded 10 rads has been identified and administered KI. 6.2 All Potassium Iodide Administration Forms and KI Issue Records are completed, signed / initialed and in keeping by the Emergency Coordinator (in accordance with EP-2-150, Emergency Records). 6.3 Each exposed person has been scheduled for bioassay analysis. 7.0 ATTACHMENTS 7.1 Thyroid Dose Graph 7.2 KI Issue Record 7.3 Potassium Iodide Administration Form 7.4 Potassium Iodide Precaution Leaflet 5
! '-, ,-- INSTRUCTIONS FOR USE l'. Determine (estimate er actual) the I-131 airborne conce l m =- a _ _ .___ _; tration in the area (s) of interest. Divide this by the E S n = g _ M protection factor of the equipment used (if unknown,
_ _ _ 7 --- = = = _ use 1). Locate this number on the Horizontal Axis. ! e i
' 2. Follow that line vertically until it intersects with tt i 8------ Horizontal Line from the duration of exposure in minute '
(Vertical Axis), i ; , ;-3. If this point of intersection is to the left or below t 4 to aaa '_ ___ Z ' line curve, the thyroid dose is less than 10 rad. r _ - - - = .
,Z __ v - - -
2 4. If this point of intersection is to the right or above l e____J _ line curve, the thyroid dose is greater than 10 rad. j 4--- bmwe- ME=W"w= .Tre-A - =mq . If this ~ 10 rad. point is on the line, then the thyroid dose is ~ 4 1000 ' _._m__ J_
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. _ I-131 Concentration Factor / Protectio,n Factor
~ '
EP-2-033 Revision l . 6 Attachment 7.1 (1 of 1)
i* KI ISSUE RECORD i b'
' s
** KI Administration - .
6 7 3 9 10 2 3 4 5 I Date Date Date Date Date ' Date Date Date Date Date ' Int. Int. Int. Int. Int. Int. Int. Int. Int. Int. Name: _ SS No.: l I I \
, Name:
( SS No.:
- i Name:
SS No.: ' I Name: SS No.: __ I Su No.: l
' Nome SS No.: /
l I Name:/ .. SS Np'.: l Noyie: 5 11
. _ ' 5o.:
' Nome:
/
SS No.: l l / Name: . SS No: . . Ncme: SS No.: . Name - SS No.: (.. } 7 . ( y
'tP-2-033 Revision T- _
. Attachment 7.,2 (1 of O
e e e
.v.- *----e-y w-y.y w ----mw ,+ rm,, -- - -
POTASSIUM IODIDE ADMINISTRATION FORM Name of Exposed Individual Last Middle First Social Security Number - - LP&L Badge Number Duration of Exposure Minutes I-131 concentration suCi/cc in Air Estimated Thyroid Dose 110 RAD / <10 RAD (Check One) Date of Exposure Respiratory Protection Worn During Exposure Yes No PF Known Iodide Allergy / Previous Allergic Reaction Yes No I verify that I have read and understand the precaution leaflet and understand that taking thyroid blocking agent is voluntary.
/
Signature of Exposed Individual /Date Potassium Iodide tablets issued by:
/
Signature of First Aid Team Member /Date NOTES:
- \
t EP-2-033 Revision 1 8 Attachment 7.3 (1 of 1)
7
~
f , s
*6
' POTASSIUM IODIDE PRECAUTION 1.EAFLET f F HOW POTASSIUM IDDIDE WORQ Certain forms of lodine help your thyroid glar.d work right. Most Patinat Passage lasert For people get the lodine they need from foods, like lodized salt or
' fish. The thyroid can " store" or hold only a certaan amount of
- lodies.
~
In a ndistion emmsency, adI= cove sodine may w rel==d in THYRO. BLOCK" the air. This material may be breathed or own!! owed. It may enter the thyroid gland and dasnage it. The damage would pro. bebly not show itself for years. Childrus are most likely to have ( ' ' (PoTAsstuna noosos)
'p es p TA h EYE m M OF'*Id d***8**
I ,(abtreviasse M7) . *. TAstgTS and SOLUDON U S.P. If you take potassium lodida. It wiu fiD up your thyroid gland.
'~ This reduces the chance that harmful radioactive iodine will
- enter the thyrodglend.
.j ,, /
' ' L,
'J' WHO SHOULD No!TAKE PCTASSIUM ICDIDE ' TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HF.ALTH OFFICIALS TELL YOU. IN A RADIATION 4 The only people wie should zwt take potassium lodide a4v people ,l who know they are allerghlte Mide. You may take getassium . ~ EMERGENCY. RADIOACTIVE IODINE COULD BE lodide even if you are taking medicine e for a threcid problem (for RELEASED INTO THE AIR. POTASSIUM IODIDE - (A
', example, a thyroid hormone or satitbyroid drus). Pngnant and FORM OF IODINE) CAN HELP PROTECT YOU. nursing women and babies and childtt e me ;she take this drug.
- f. .
IF YOU ARE TOLD TO TAKE THIS MEDICINE. TAKE IT HOW AND WHEN TO TAME!*0TASSluM IOC1DE ONE TIME EVERY 24 HOURS. DO NOT TAKE IT ?.! ORE r Potassium Iodide should be takes as soon as possible af,ter CJTELb10RE WILL N(7r HELP YOU AND MAY IN. public health officials ten you.You should take one dose every 24~ i C.' TEASE THE RISK OF SIDE EFFEC";S.130 NOT 7AKE ' hours. More win not help you beause the thyrsf casFhold" on. / TnS DRflG IF YOTI KNOW YOU ARE ALLE)tGIC TO 17limited amounts of iodine. Larger & sees win increase the risk 010PIDE. (SEE SIDE EFFECTS BELOWJ ' , of side effects. You win probably 'as told not to take the drug for + more than 10 days. ,
/ 5f DE EFFECTS r' UsusUy. side effects of potassium iodide happea whou people
; INDICATIONS take higher doses for a long time.You should be careful not to THY.ROID,S. LOCKING IN A RADIATION EMERGENCY taue more aan e. ,ecomm.nd.d dose or tak. it for lon.e, than om. you are told. Side effects an unlikely beause of the low dose and the short time you will be taking the drug.
d" DIRECTIDNS FOR USE . Possible side effects Inc!vde skin rsshes, swe!!Ing of the seUvary
- e Use waly as directed by State or local public health authorides in glands, and " iodism"(metauic taste, burning mouth and throat.
the event of a radiadon ee rgency. sore teeth and gums, symptoms of a head cold, and sometimes
< ./
DOSE ******h upset and diarrheal e
! ADULTS AND CHILDREN 1 YEAR OF ,
Tabic.d A few people have mis aBergic reaction with more serious symp. AGE OR OLDER: One (1) tablet once a
- 7
- tems.These could be fever and joint pains, or swe1Eng of parts of
/ day. Crush for sman children.
' _j
' W face and body and at times severe shortness of breath requir.
' BABIES UNDER 1 YEAR OF AGE: '
. ing irnmedaste medical attention.
One half (1/23 tablet once a day. Crush
-
- E'88" Taking lodido may rarely cause overactivity of the thyroid t .
ADULTS AND CHILDREN 1 YEAR OF El and, underactivity of the thyroid ghnd. or enlargement of the l Sohtion: AGE OR OLDER: Add 6 drops to one. thyroid gland (goitari. .g half glass ofliquid and drink each day,
- BABIES UNDER 1 YEAR OF AGE: .
WHATTO DO IF SIDE EFFECTS CCCUR t Add 3 drope to a smaH smount of Equid , 'If the side effects are severe or if you have en ai!ergic reaction. p once a day. l stop taking potassium Iodide. Then if possibie, call a doctor or - s For s# descge forms Take for 10 days unless directed otherwsse public health authority for Instruedons. by State or local public health suthorities. ' HOW SUPPLIED Ct=re'et controlled room temperature betweea 15* ard 30*C (59 THYRO-BLOCKN TABLETS (Potassium Iodide. U.S.PJ bot-to 86*Fh Keep container tightly closed and protect, from light. ties of 14 tabh ts (NDC 0037 0472-20.1 Each white, round, scored De not ese the solotionif it appears brownish in the nozzle of de tablet contsle 130 mg potassium sodide. bottle. . THYRO-BLOCKN SOLUTION (Potassium Iodide Solution. UJa'.P.) 30 ml(1 !L oz.) light-resistant, measured-drop dispensing WARNING units (NDC 0037 4237 25). Each drop contains :1 mg potassium potassiam iodide should net be used by people a#ergic to iodide. lodade, Key out of the reach of children. In case of overdose or aBergic reaction, contact a physician or the public health authority. ,t WALLACE LABORATORIES
'( OMsion of DESCRIPTION CARTga.wALLACE. INC.
, Ese THYRO-BLOCKW TABLET contains }30 mg of r Cranbury. N** Jsey c8512 l f ,6 m odds, N sof THYRO BLOCKM SOLUTION contains 21 mg of CW-toists-tol7s issue 10.7s
, p%.aciam aedida.
m +
' EP-2-033 Revision 9 1 Attachment 7.4 (1 of 1)
/
J_ = . . x, _ ._ __
WATERFORD 3 SES m PLANT OPERATING MANDAL dd ' l_QUISIANA ! POWER & LIGHT MIDDLE SOUTH UT1UTIES SYSTDA EP-2-050 POM VOLUME 18 REVISION 1 POM SECTION 2 APPROVAL DATE: May 2.19 83 EFFECTIVE DATE: Fuel Load EMERGENCY PLAN IMPLEMENTING PROCEDURE OFF-SITE DOSE ASSESSMENT (MANUAL) LP&L W-0 GECTS f V M ew4T ah? 4 [**:i E C. e . ,., ;u L D v/ COPY NO d O PORC Meeting ::; f3 -j g 4 Reviewed: ; r#1 __ 70RC Chg1 p n Approv d: (1
- kl
<I,..Jf@CJ!,dl)AJN Plant Manager-Nuclear e
WATERFORD 3 SES PLANT OPE 3ATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. $~A ~ MO Title OW-S;/e Zhre Assessment brianc.n0 l Effective Date w/ Iaod (if different from approval date) canniste 1. B. er C l
~
A. Change No. ._ B. Revision No. / C. Deletion NM RFAMON FOR CHAMcF. RFVTMTON. OR DFLRTTON 0^9,0lfh A#lkslDn B $8 9 Asf AMA RFOUTRFD STCMATURFA Originator Date / / Technical Review 4 9 bb " Date i D i SAFETT EVALUATION Does this change, revision, or deletion: TES NO
- 1. Change the facility as described in the FSAR7 1
- 2. Change the procedures as described in the FSAR7- X
- 3. Conduct tests / experiments not described in the FSAE?
X
- 4. Create a condition or conduct an operation which ex- A 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 Safegt Evaluation checklist. l Safety Evaluation k U bN Date N ~#N Group /Dep't. Head Review Y N h . Date d-/ V-I3 0 Temporary Approvale Date (NOS) Temporary Approvals l Date l QC Revteu s MA GM! , ! - Date #* f-P? PORC Review I b +M N -- -Date *MG Meeting No. F3 04 PlantManhrduelearApproval ' MM Y ' Date NM "A
' 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 .
, - - - - 9' r -
- c. , , - - - , - - --- , , - -
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Emargsney Plan Implcmsnting Procaduro EP-2-050 Off-Site Dose Assessment (Manual) Revision 1 TABLE OF CONTENTS
.A 1.0 PURPOSE ,
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2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Dose Projections Based on Plant Monitoring Data (22 pages) 7.2 Dose Projections Based on Field Monitoring Data (7 pages) 73 Dose Projections Based on Known Isotopic Release Data (6 pages) 7.4 Dose Projections Based on FSAR Accident Data (4 pages) 7.5 Meteorological Data (18 pages) LIST OF EFFECTIVE PAGES Title Revision 1 J 1-62 Revision 1 l I I I ! l 1
Emargancy Plen Implcmanting Proc 9duro EP-2-050 l Off-Site Dose Assessment (Manual) Revision 1 1.0 PURPOSE Provide methods for determining projected off-site doses following a major accidental release of radioactive material; for purposes of recommending off-site protective actions; and for long-term continuous updating of the off-site doses in the event the computer-based system (CEPADAS) is not available.
2.0 REFERENCES
2.1 EP-2-051, Offsite 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, Revision 1 - Meterological Programs in Support of Nuclear Power Plants 2.4 U.S. NRC Regulatory Guide 1.109 - Calculation of Annual Doses to Man
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from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I, Rev. 1, October 1977 2.5 U.S. NRC Regulatory Guide 1.145, Revision 1, Atmospheric Dispersion Models for Potential Accident Consequent Assessments at Nuclear Power Plants 3.0 RESPONSIBILITIES The Radiological Assessment Coordinator / Dose Assessment Coordinator is responsible for ens'uring this procedure and all calculations are performed in accordance with this procedure. 4.0 INITIATING CONDITIONS 4.1 Any of the following emergencies has been declared: Alert Site Area Emergency - General Emergency 4 2
Emsrgancy Plcn Implemsnting Procsduro EP-2-050 Off-Site Dose Assessment (Manual) Revision 1 l and 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 or the Emergency Coordinator. 5.0 PROCEDURE NOTE This procedure is arranged in attachments, each describing a specific method of assessing off-site dose. The specific attachment (s) which is (are) to be utilized in performing dose ass'essment shall be based upon availability of plant operating data and radiological field data. Only if no plant or field data is available, should Attachment 7.4, Dose Projections Based on FSAR Accident Data, be used. Each attachment is described below. 5.1 Attachment 7 1 - Dose Projections Based on Plant Monitoring Data. This attachment is used to rapidly assess the maximum off-site doses ( to determine if off-site Protective Action Guides will be exceeded l 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, especially those that may be based on actual field data. l 5.2 Attachment 7.2 - Dose Projections Based on Field Monitoring Data. This attachment provides methods of performing dose projections based on actual measurements by off-site monitoring teams. 5.3 Attachment 7.3 - Dose Projections Based on Known Isotopic Release Rate. This attachment provides methods of calculating off-site doses when isotopic analysis of the release path exists. 3 l l l
Emargancy Plan Impicmsnting Procaduro EP-2-050 Off-Site Dose Assessment (Manual) Revision 1 l I i 5.4 Attachment 7.4 - Dose Projections Based on FSAR Accident Data. This 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 insuf-ficient information to utilize the procedures identified in At-tachment 7.1, 7.2 or 7.3. 5.5 Attachment 7.5 - Meteorological Data. This attachment provides the method for obtaining meteorological data needed to perform dose projections. The attachment provides the method for using overlays to determine dispersion factors. NOTE An adequate supply of all forms for each attachment is maintained in the TSC and EOF (primary and backup) for the Radiological Assessment Coordinator / Dose Assessment Coordinator's use. 6.0 FIN AL CONDITIONS 6.1 Releases of radioactive material to the atmosphere have been l terminated or decreased below the EAL for an alert category or: l l 6.2 Releases are controlled and a long term monitoring program has been 1 established. 4 l
Emsrg9ncy Plan Implcmsnting Proceduro EP-2-050 Off-Site Dose Assessm]nt (Manual) Revision 1 70 ATTACHMENTS 7.1 Dose Projections Based on Plant Monitoring Data s 7.2 Dose Projections Based on Field Monitoring Data 7.3 Dose Projections Based on Known Isotopic Release Data 7.4 Dose Projections Based on FSAR Accident Data 7.5 Meteorological Data O e O e 5
DOSE PROJECTIONS BASED ON PLANT MONITORING DATA 1.0 PURPOSE This attachment provides the methods for quickly calculating projected off-site doses in order to determine the need for protective actions. 2.0 PROCEDURE 2.1 Determination of whole body and child thyroid doses at specific off-site locations is performed using the. attached work sheets. 2.2 D'etermination of accident type. 2.2.1 Based on information communicated by the emergency coordinator, select the form for the most appropriate accident type and log the exposure duration in Column 5. NOTE The exposure duration (for all except main steam line break) should be assumed as two hours unless plant information provides an accurate, dependable prediction of release duration. Attachment 7.1 Page 5 - Fuel Handling Accident Attachment . Page 6 - Waste Gas System Failure Attachment . Page 7 - Liouid Waste System Failure Attachment
- F Attachment Page Page 8 LOCA Maohai$elFailure 9 --LOCA', <1 ed Fuel Attachment . Page 10 - S.G. Tu e Rupture, Major Fuel Failure Attachment . Page 11 - S.G. Tube Rupture, <1, Failed Fuel MAIN STEAM RELEASE = MSR Attachment 7.1, Page 12 - MSR, Major Fuel Failure, Steam Line Break Attachment . , Page 13 - MSR Major Fuel Failure, Relief Valve Attachment Page 14 - MSR Maaor Fuel Failure, Atmos. Feed Dump Attachment
. , Page 15 - MSR Major Fuel Failure, Emer. Pump Tur ine Akkackm!nk h$k kkk <1 h$k h$ e$$$ fha $v Attachment Page 18 < Failed Fuel Atmos. Dump
<11"#, Failed Fuel Attachment .
Page 19 .-- MSR Emergency Feed Pump Turbine EP-2-050 Revision 1 6 Attachment 7.1 (/ of/2)
DOSE PROJECTIONS. BASED ON PLANT MONITORING DATA NOTE It is possible that two release paths and two forms are applicable. If this occurs, the projected doses and release rates from each
- form should be added together. i
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2.3 Record the date and time on the selected forms. 2.4 Record the following meteorological data: NOTE Data from both the primary and backup meteorological towers is available on the CRT in the Control Room. Data from the backup tower should be used only if the required information is not available from the primary tower. Figure 1 of Attachment 7.1 provides a description of the meteorological data to be available in the Control Room. If data from neither tower is available, follow the procedure outlined in Attachment 7.5. 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. 2.4.2 Record the wind direction in whole degrees from which the wind is blowing in section 7 of the selected form. 2.4.3 Record the delta T (60 m - 10 m) in degrees centigrade ( C) in section 8 of the selected form. 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. 2.5 Record the proper radiation monitor reading in Column A. EP-2-050 Revision 1 7 Attachment 7.1 (1sof)CI4 l l I - l -
DOSE PROJECTIONS BASED ON PLANT MONITORING DATA 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. 2.6 Record the flow rate in efm in Column C. See Attachment 7 1, Table 1, page 20, to determine cfm to use in Column C. 2.7 Multiply A x B x C and record the product in Column D as noble gas release rate. 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. 2.9 Multiply D x G and record the product in Column H, as iodine release rate. 2.10 Multiply H x I and record the product in Column J. If more than one release path exists, sum Column H to use for dose calculations. 2.11 Enter the value from Column F in Column 1 in each row designated for noble gas (NG). 2.12 Enter the value from Column J in Column 1 in each row designated for Iodine (I). 2.13 Complete the calculations below for each row. 2.13.1 Multiply 1 x 2 and divide by 3. Record the result in Column 4 as the dose rate (mrem /hr) for whole body and for a child's thyroid. 2.13.2 Multiply 4 x 5 and record the product in column 6 as projected dose in mrem. 2.14 When there is a significant change in the monitor reading (A 20%); wind spe(d (A 50%); wind direction (different sector) or factor of EP-2-050 Revision 1 8 ' Attachment 7.1 (jfot220
DOSE PROJECTIONS BASED ON PLANT MONITORING DATA five (5) in dispersion factor, the dose projections should be revised on another sheet. 2.15 The data recorded on each sheet should be appropriately entered on the Dose Assessment Status Boards located in the TSC and EOF. 2.16 It should also be entered at the appropriate locations on the 10 mile Emergency Planning area maps located in the TSC and EOF. 3.0 ATTACHMENTS 3.1 Norksheets - Dose. Projections Based on Plant Data (15 pages) 3.2 Table 1 - System Flow Rates (2 pages) 33 Figure 1, Example of Meteorological Data Available in the Control Room (1 page) i f t e l l l i l l EP-2-050 Revision 1 9 Attachment 7.1 (fof/2) l l
I Date/ Time _ Print last name S10 nature
@ @ G U @ @ G U Release Rate (D @
Dose Rate FLOW Holease nate Dose flate lodine / DOSE MONITOR CONVERSION DOSE I s [gd7 p lTOR ng,p FACTOR ((N YghBxC) . FAClOR )xE3 lin (DxOMtiec FACTOR PRM-IRE-5032(LO l 4.72E-04 PRM-IRE-5032(MI )) 6.70E-04 3.02 E4 6.45 E-0 1.55 E9 PRM-IRE-5032 (III i 1.00E-03 3.02 E4 6 &S F-5 1.55 RQ PRM-IRE-5107Aor 3 4.72E-04 _ PRM-IRE-0100.1S 4.72E-04 PRM-IRE-0100.2S 4.72E-04 1.55 E9 6.70E-04 3.02 E4 6.45 E-0 PRM-IRE-0110(MI )) PRM-IRE-011001Il 1.00E-03
- 0) O @ @
Exposure Dose Rate Xu Wind Dose Rate Speed mR/hr Duration Projected Dose = @)x @ (mnem) l LOCATION FaClor an gmJ o mph (Hours) l @ gom n @x@ +@ mRemWimle Body (EAB) EAB-NoNe Gas l mRom Yl$w (EAB) EAB-iodine mnem Wimle Body (2mi) 2 mise -NoWe Gas 2 mise -sodine mnem i $u (2mi) mRom Wiele Body (5 mi) 6 mile -NoNe Gas mnem klyroid (5 mi) 6 mile -lodine mRom Whole Body (10mi) 10J nile-Noble Gas 10 mise -lodine mnoni Y$ (10mi)
, @ Xur) Table Vy]M.Q s.l. EAB 2 miles 5 miles 10 miles 1.3 06) 7.1 (-7) 7.1 F7)
<- l.0 A 1.105) l @ Wind Direction From 7.1FT)
-1.0 to -0.9 B 5 A 05) 4.506) 7.7 (-7)
" ' ~ "
FUEL HANDLING -0.8 to -0.3 D 1.8 04) 3.705) 1.1(-51 4.2 (-81 2.B ui elm 2.3<-s i*o ACCIDENT -0.3 io =
- 0.8 to +2.2 E
F 4.4 (-41 1.304) 5.005l 2.4 F5) O 7.3 (4) 2.4 (-4) 1.1 04) 5.405) S
- 2.2
" Arrachment 7.1 (5 of 22)
I
/ .
D 12/ Time ._ Pilot last name Sloc-ture 0 0 0 W @
, g O CONVERSION O
FtDW (D Holease Hate DOSE Dose Hale iodine / Gas nolease Hale DOSE Dose Rate N Mk $'p3 FAC10H w (DxON!sec FACTOR _ p lTOR TcPc? FACTOH @[MCl PRM-IRE-0110(ID) 4.72 E-04 PRM-IRE-0110(MID) 5.85 E-04 _ PRM-IRE-0110(III) . 5.81 E-04 4.86 E104 4.08 E-07 9.67 E108 PRM-IRE-0100.lS 4.72 E-04 l PRM-IRE-0100.2S 4.72 E-na i W @ @ @ G @ Wind Dose Rate Exposure Project 1 Dose Rate Xu Duration Dose = IJOCATION Factor o Speed mR/lir '
)x@ (mnem)
(Hours)
@%hM mpli h@+@
mnemwhose Body (EAB) EAB-tem oas (EAB) mnemML l EAB-iodine mnem wtum sody(2mi) mnom i ,5id (2mi) l 2 mile -sodine mRom wuAa, Dody(5 mi) a mile -Noble Gas ! . s mile -iodine mnemib (5mi) mnem wuse Body (10mi) to rnise-Notde Gas to mile-iodine mnom Yb (10mi)
@ Xu/O Table Dg'jaQ EAB 2 miles 5 miles 10 miles n . s.t.
- 7.1 (-7) 7.1 (-7)
<.1.0 A 1.1 (-5) 1.3 (-6)
@ Wind Direction From '
D 5 A (-5) 4.5 (-6) 7.7 (-7) 7.1 (-7)
-1.0 to -0.9
**'** '2"' " "' "" ""'
WASTE GAS -0.8 to -0.3 ~ D 1.8 (-4) 3.7 (-5) 1.1 (-5) 4.2 (-61 2.3a) i.0 i.5) SYSTEM FAILURE .o.3 ie .0.o e 2 a) 4.4 ( 4)
..S i-Si 1.3 (-4) 5.0 ( 51 2A(-5) 0.8 to +2.2 F G 7.3 (4) 2.4 (-4) 1.1 (-4) 5.4( 5)
>t2.2 ,
m 7-nso Rowinton 1 11 Attachment 7.1 (6 of 22)
i
# ._ _ .___ Data / Time ,
Paint last nam 3 Sv.anuo l U 0 0 0 W @ g O CONVEllSION O FlDW Floloase Rate Ib"A,",I DOSE FACTOil Dose flate Np3 lodine / shas I1olease flate (DxOfh,cc DOSE FACTOR Dose nate [M MONDOR nE@@ FACTOft fcM r PRM-IRE-0110 (LO) _id2E-04 6 J7E-04
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PRM-IRE-0110(HID) PRM-IRE-0110 (HI) M 2E-04 . 1.99E-04 1.78E409 3.33E104 PRH-IRE-0100.IS__ &_78R na ) PRM-IRE-0100.2S 4.78E-04 ; O @ G G :
- 0) O Dose Rate Exposure Projected Dose Rate Xu Wind i
LDCATION Factor o Speed pR/hr Duration Dose = G)x@ (mnemi mph (px@+@ (Hours)- l $ lm""m" fdt'.""J mnemwhose Body (EAB) EAB-Nobieom mnemY$'oid (EAB) EAB-iodine mnem wimse aody(2mi) 2 mile -Noble Gas (2mi) milem Nmid 2 mile -lodine mnem wione sody(S mi) > 5 mile -Noble Oas (5 mi) mnem I mold 5 mile -lodine milom Whole Body (10mi) l 10 mile-Noble Gas milom Noid (10mi) 10 mile-Iodine
@ Xu/O Table EAB 2 miles 6 miles 10 miles
%3g.Q s.t.
- 1.3 (-6) 7.1 (-7) 7.1 (-7)
<-? D A 1.1 (-5)
@ Wind Direction From 7.7 (-7) 7.1 (-7)
-1.0 to -0.9 0 5A(-5) 4.5 (-6)
~"'*" '""' ' '~ " " " "'
LlOUlD WASTE -0.8 10 -0.3 D 1.8 H) ~ 3.7 (-5) 1.l f-5) 4.2(-6)
..Sosi 2.3(-5> i.0 (-6) 2.0 H)
SYSTEM FAILURE .o.3 io .o.o
*0.8 to +2.2 7 e
4.4 04) 1.3(-41 5.005) 2 A F5) 2AF4) 1.1 H ) 5AES)
> t 2.2 0 7.3 (4) 12 Attachment 7.1 (7 of 22)
^a ara n , . 4 . 4 ,,.. I .
f Data / Time . Print last name Signatura
@ @ .O . 0 @ 0 Dose nate 0
lodne/ nolosse Rate 0 W Dose nate MONITOR FIDW neleaso nate DOSE DOSE { CONVEnSION 88 (OxGNbec gTg (p1hecxDnC) FACTOR Yx'F3 b FACTOR b7xl7 J MONITOR nepjNG FACTOR PRM-IRE-0110(LO) 3.92 E-04 1 ?! v n4.,__ l PRM-1RE-011RQilD1 i PRM-IRE-01100lI) . 3.65 E-04 1 3.42 E105 4.28 E-03 5.09 E408 PRM-IRE-0100.ls 4.02 E-04 i PRM-IRE-0100.2s 4.02 E-04 l
- (D 0 0 @ @ @
Wind Dose Rato Exposure Projected I Dose Rate Xu Speed mR/hr Duration Dose = (/)x@ (mnem) LOCATION Factor o (Hours)
@MMJ F mpl1 @@+@
mnem whose Body (EAB) EAB-Nobie Gas (EAB) EAB-iodine mnemV% l mnem Whole Body (2mi) , l 2 mile -NotAs Gas mnemS$ (2mi) ! 2 mile -iodine mnem exa oody(5 mi) .
- s mise -noin o mnem yb (5 mi) l s nee -iodine mnem wxe sody(lomi) 10 mile-Nobie Gas 10 mise-todkw mnem ib (10mi)
@ Xur) Table 2 miles 5 miles 10 miles M.Td s.t. EAB 7.1(-7) 7.1 (-7)
<.1.0 A 1.1 ( 5) 1.3(-6)
@ Wind Direction From 7.1 (-7) 8 5 A (-6) I 4.5 (-6) 7.7 (-7)
-1.0 to -0.9
" 5 '- " "'
-"'~" "' '- ' ~ " '
LOCA, MAJOR -0.8 to -0.3 D 1.8 (-4) 3.7 (-5) 1.1(-5) 4.2 (-6)
..si..) 2.3(.si i.o(-si FUEL FAILURE .o.3 ,o .o..
' ~~
e 2.o ai 4.4 (-4) 1.3 (-4) 6.0 (-61 2 A (-5)
*0.8to+2.2 F 7.3 (-41 2.4 (-4) 1.1 (-4) 5 Al-5)
> t 2.2 G 13 Attacliment 7.1 (8 of 22)
FP '/-050 Revision i
9
/ --
Dil2/ Time . Print last nam 3 Signature
@ @ O U @ 0 Dose Flate G
lodine / U Rolease Role W @ Dose Rate FLDW Release Role DOSE DOSE MONITOR NRSM i l MONITOR D REpt/@ FACTOR [cN I r I FAC10R NId th (oxojC) hec FACTOR f$
! PRM-IRE-0110(LO) 4.72 E-04 PRM-IRR-01IQ(MID) 4.7'2 E-O&
PRH-IRE-Oll0(llI) 1 72 E-04 6.17 Et04 1.04 E-04 1.65 Ef08 l PRM-IRE-0100.ls 4.72 E-04 ,' PRM-IRE-0100.25 4.72 E-04 - 4 W O @ @ @ O Dose Rate Wind Dose Rate Exposure Projected
- Xu Duration i
LDCATION Factor o Speed mR/hr Doso = @x@ (mrem)
@$* mph (Hours)
J @t",y @=0+G mRemWimle Body (EAB) (:AB-Noble Gas mrem WS (EAB) EAB-iodine mrem Wimle Body (2 mi) 2 mne -Noble oss mnem kb (2mi) 2 mee -lodine mnem Wlois Dody(5 mi) a mne -NotAs oss mRom Sjb (5 mi) 5 mile -lodine mnem Wimie Body (10mi) I a mse-Notge ons mnem yb (10mi) to mile-lodine
@ Xu/O Table s.l. EAB 2 miles 6 miles 10 miles
%IR.Td
<.1.0 A 1.1 (-5) 1.3(o) 7.1 (-7) 7.1 (-7)
@ Wind Direction From
-1.0 to -0.9 5.4 ( 5) 4.5 (-ol 7.7 (-7) 7.1 (-7)
~~
LOCA,<1% FAILED -0.0 to -0.3 D 1.0 (.4) 3.7 ( 5) 1.1(-5) 4.2(-ol
..ol.5)
FUEL .o.3 io .o.. E 2. ( 4> . 5( 5) 2.3(.5) 5.0 ( 51 2.4 (-5)
*0..to+2.2 ,
F _ 4.4 (-41 1.3 (-4) _
> t 2.2 G 7.3 (4) 2.4 (-4) 1.1 (-4) 5.4 l-5)
EP-2-050 Revialon i 14 Attachment 7.1 (9 of 22)
I D:12/Tisr:3 __ i ~ Print last name Signature O 0 G U (D @ g O CONVEnslON O FIDW neleaso nate DOSE FAcron Dose nale
%'ei Tiio lodine /
nelease Rate (oxOfliioc DOSE FAcron Dose nate M MONITOR M cP FAcTon fcM ($"M' 2BM:1RE 0110(IA) __L97 R-04 PRM-IRE-0110(HID) 4.27 E-04 8.56-E-06 5.09 E408 3.65 E-04 3.42 Eto.' PRM-IRE-0110(111) PRM-TRE-0100hS_ _A.D2 E-04 PRH-IRE-0100.28 4.02 E-04 pn'H-1aR-0001 ta> R-n4_ 8.56 E-05 5.09 E408 j 27 E-04_ 3.42 Et05 PRH-IRE-0002(HID) PRM-IRE-0002(HI) ~l.65 E-04 _ . W O @ Exposure Projected Dose Rate Xu Wind Dose Rate Speed mR/tr Duration Dose = (d)x@ (mnemi LOCATION Factor O mpli %+ i (Hours)
@l sm rom ggF mnem wioie Body (EAB)
EAB-NotAs Gas (EAB) mnom V& EAB-Iodine mnom wiole Body (2mi) 2 mue -NotAs Gas a mile -lodine mnemi b (2mi) mnom wtole Body (5 mi) 5 mile -Noble Oas mnem khold (5 mi) 5 mile -Bodine mnem Wlois Body (Omi) to mue-Noldo Gas mnem khold (0mi) 10 mile-lodine
@ Xu/O Table I 2 miles 5 miles 10 miles Dj!g.Td s.t. EAB
- i.3 (.8) 7. (-73 7. ( 7)
<.i.0 A i.i (.53
@ Wind Direction From '
7.7 (-7) 7.1 (-7)
-1.0 to -0.9 o 5.4 (-5) 4.5 (-6)
~" *" '2"' '- ' ' ' ' ' 5 ' * "'
S.G. TUBE RUPTURE -0.8 to -0.3 D 1.0 M) -- ~~ 3.7 (-51 - 1.1(-5) 4.2 (-e) 2.o Hi e.si.si 2.3i-si i.oi.si e MAJOR FUEL FAILURE 0.3 io.0.8 F 4.4 HI f.3 H) 5.0( 5) 2.4 (-5)
+ 0 .8 to
- 2. 2 2.4 H) 1.1 H ) 5.4l-5)
> t 2.2 G 7.3 (4)
~~" ~~
- 15 Attachment 7.1 (11 of 22)
i , 1 Dats/ Time _ ' Print last name Signature O O O @ 0 G U (D Q) JTOR CONVEnslON FIDW Helease Hale DOSE Dose Rate lodine / Gas Gelease Raio DOSE Dose Rate (OxGflhoc
@l@ HM@ FACTOR $M $*gDxC) FACTOR %I@ ig FACTOR fi7xNI PRM-1RE-0110 (LO) _4J2R-04 PRil-IRR-G110 (MID) 4 J2g.n4 6.17E104 4.17E-07 7.65E108 PRM-IRE-Otto (HI) 4.72E-04 ERM-1RR-01DQJ R _4J2R-na PRK-1RR-0100Ja 4.72R-na PRM-IRE-0001 _A 72R-na
_AJ2E-0&- - 6.17E904 4.17E-06 7.65E408 PRM-IRE-0002 (t(IDi PRM-IRE-D002 011) 4.72E-04 1
- 0) O G .@ @ G Dose Rate Wind Dose Rate Exposure Projectecl Xu LOCATION Factor o Speed mRAir Duration Dose = 6)x@ (mnemi U2lm""m"8ggj mph @@+0 (Hours) mRemWlxAe Body (EAB)
EAB-Noble Gas mnem y($ (EAB) EAB-iodine mnem WixAs Body.(2 mi) 2 mile -Noble Gas 2 mise -iodine mnem S $ (2mi) nAiem WlxAo Body (5 mi) 5 mile -Noble Gas mnem h Id (5 mi) 5 mise -lodine mRom WlxAs Body (10mi) 10 mile-NotWe Gas 10 mile -Iodine mnem SldEid (10mi)
@ Xwo Table s.t. EAB 2 miles 5 miles 10 miles
- DJla Y"'
,,, .o 7.1 (-7)
@ Wind Direction From 3 ,,, g.s1 1.3 ( si 7.1(-71
-1.0 to -0.9 B 5.4 (-5) 4.5 (-6) 7.7 (-7) 7.1 (-7)
-a" ' *
- I '""' '- ' ' ' * *' ' " '
. S.G. TUBE RUPTURE -0.0 to 0.3 0 1.8 (.4) 3.7 l-5) 1.1(-5) _ 4.2 (-el
..st-si 2.ai-si i.o i-si
< l% Failed Fuel -o.3 io .o.. "
e 2. si 5.0(-5) 2.4 (-5)
*0.8 to +2.2 F 4.4 (-4) 1.3 (-4)
G 7.3 (-41 2.4 (-4) 1.1 (-4) 5.4 L-5)
> e 2.2
"" ' "'" " '~' '
16 Attacliment 7.1 (12 of 22)
/ Dats/ Time Print last name Signaturs ; @ O O U @ 0 G U (D @
j - MONifoR CONVERslON FLOW Roloase Rate MSE Dose Rate lodine / Release Rale DOSE Dose Rale p lTOR RE^% mr FACTOR M I[i3"0xC) FACTOR $p3 {>as (OxOflhoc FACTOR bN PRM-IRE-5500A 5.55 E-06 5.1 E03 PRM-IRE-55005 5.55 E-06 5.1 E03 1.42 E105 8.56 E-03 5.09 E108 W O @ @ @ Dose Rate Xu Wind Dose @ Rate Exposure Projected LOCATION Factor o Speed ' R/hr Duration Dose = (/)x@ (mnom) te m fe = ! mph d"0+0 (Hours) EAB-NotAs Gas mrem Whole Dody(EAB) EAB-iodine -dliour mnom Ylb (EAB) 2 mise -NotAs Gas mRom WlxAo Body (2 mi) 2 mee -lodine o mRom i fjoid (2mi) 5 mile -Noble Gas mnem'WxAe Body (5 mi) 5 mile -lodine mnemYb (5 mi) 10 mile-Noble Gas mRom WlxAs Body (10mi) l 10 mile -lodine mRom Yb (10mi)
@ Xui) Table a
Dyi',ia Q EAB
- s.l. 2 miles 5 miles 10 miles
@ Wind Direction 'From <. t.0 A u (-5) 1.s (-6) 7. (-71 7.i (-7)
-1.0 to -0.9 5 5 A (-5) 4.5 (-6) 7.7 (-7) 7.1 (-7)
MAIN. STEAM -a. was c i.2a) ..a e5) 2.nei . .*7)
~""'~" " " ' "' "'~"' ~"'
STEAM LINE BREAK -0.31o.0.8 E 2.604) 6.5 (-5) 2.3F5) 1.0 05) Major Fuel Failure aa + 2.2 T u u) i.a s) s.*st ._ 2d esi
>+2.2 G 7.3 04) 2 A F4) 1.1 H )' 5405)
EP-2-.050 Revision 1 17 Attachment 7.1 (13 of 22)
/ _ Dals/Timo -
Pr!nt last name Signaturo
@ @ O U O O Dose Hale O
kxfine/ O nolease Raio (D @ MOtaTOR FtDW Holease Rate DOSE DOSE Dose Rate CONVERSION j MONITOR Rg9l@ FACTOR h}[$ IA[dC) FACTOR migE s (DxGfiboc FACTOR N PRM-IRE-5500A 5.55E-06 PRM-IRE-55005 5.55E-06 9 i 1 NOTE: .For steam released th1 ough HCES on stack,i se S.C. Tub t Rupture I arm. G) O @ @ @ G Dose Rate Xu Wind Dose Rate Exposure Projecte(I 4 LOCATION Factor o Speed mR/hr Duration Dose = (4)x@ (mnem) I
@ d ccgF mpli @=@ +@ (Hours) mrem Whole Dody(EAB)
EAB-NoNe Gas l EAB-kxnne mnom Vl,dyoki (EAB) mRom Wlolo Dody.(2 mi) 2 mHe -NoNo Gas 2 mile -lodine mnemSffokj (2mi) mrem'Whole Body (5 mi)
- 5 mile -NoWe Gas 5 mne -kxune mnem I'lyoid t (5 mi) mnem Whole Dody(10mi) l 10 mile-Noble Gas 10 mile -lodine mrem khroks (10mi) 1
@ Xu/O Table
%'ja k?,
. s.t. EAB 2 miles 5 miles 10 miles
@ Wind Direction From <. i.0 -
A i. E5) 1.s tel 7.i(-7) 7.s(-7)
-1.0 to -0.. D 5.4 05) 4.5 06) 7.7 (-7) 7.s (-7) i MAIN STEAM -aoie-ao C usi n eSi 2.5toi .. son d ' '- "'
' ""'"~" " " ' "~"' "'~5' RELIEF VALVE -0.3 to *0.8 E 2.6 (-4) 6.505) 2.3(-5) s.O(-5) Major Fuel Failure 0.8io.2.2 F 4.4 u i i.a u) 5.0o5i 2.4 eSi
> t 2.2 G 7.3 ( 4 ) 2.4 (-4) 1.1 F4) S A ES)
EP-2-050 Revision 1 18 Attachment 7.1 (13 of 22)
I _. _ Dst 2/ Time _._ Print last nene Signalute g O O O O O Dose nate G iodine / U Ilolease nate
- 0) @
Dose Rate FID W nolease Hale DOS, DOSE CONVERSION MONITOR ne,giya FAcTon J^r'uq gDxc) FAcTon %'p3 Tuo8 88 (DxGFiboc FAcron 5f,17 l PRM-IRE-5500A 5.55E-06 3.42E05 8.56E-0: 5.09E08 PRM-IRE-5500B 5.55E-J6 NOTE: For stearn released through l' CES or itack, use S.G. Tul. e Ruptura Forra, i I G) @ @ @ @ G Dose Rate Wind Dose Rate Exposure Projected Xu IJOCATION Factor o Speed mR/hr Duration Dose = (/)x@ (mnom)
@ l,'"om" M JF mph @a@+0 (Hours) .
mnem Wde Dody(EAB) EAB-Noble Gas l mnom Mb (EAB) l EAB-iodine mnom Ede Body (2 ml) i 2 mise -Noble Gas 2 mile -lodine ' ' mnem I hold (2mi) mriom'Nde Body (6 mi) f 5 mile -Noue Gas mnemSlb (5 mi) 5 mile -lodine mnem Wde Body (10mi) 10 mile-Noble Gas 10 mile-lodine mnem ib (10mi) '
@ Xwo Table giaQ . s.t. EAD 2 miles 5 miles 10 miles A 1.105) 1.3 08) 7.1(-7) 7.1 (-7)
@ Wind Direction From < - 1.0
-1.0 to -0.9 D 5A05) 4.5 06) 7.7 (-7) 7.1 F7) c '2"> ' a "> ' 2" = ">
MAIN STEAM -a io +=
-0.8 10 -0.3 D 1.8 H) 3.7 F5) 1.1 F5) 4.2 (-6)
,.o a, ATMOS. DUMP VALVE .o.3 ,0 .o e 2. a) . 5 al 2.3a)
'" ' . 2.2 T 4a ni i.3 si u si 24 ai Major Fuel Failure > t 2.2 O 7.3 04) 2.4E4) 1.104) 5.405) en > nrn n ., . 4 ,, s ~' ' 21 Attachment 7.1 (14 of 22)
I Dits/ Time __ Print last name Signature
@ @ G U @ 0 D se Dale G
lodine / U Release Rate (D @ Dose Rate MONiiOR FLOW Release Hate DOSE DOSE CONVERSION MONITOR gg y FACTOR M IgdC) C FACTOR $'p3 Gas io (DxGlC) hoc FACTOR N " PRM-IRE-5500A 5.55E-06 3.42E05 8.56E-0: 5.09E08 PRM-IRE-5500B 5.55E-06 l
~
O @ @ @ G Dose Rate Wind Doso Rate Exposure Projected Xu LOCATION Factor o Speed mR/hr Duration Doso = (/)x@ (mnem)
@ l,*
- M F mph @a@+0 (Hours) mrem Whole Body (EAB)
EAB-Noble Gas EAB-iodine . mnem Vl$ (EAB) mnem Whole Body.(2 mi) 2 mile -Noble Gas 2 mne -lodine mnemi L (2mi) miiem' Wide Dody(5 mi) 5 mile -Noble. Gas 5 mne -iodine mnem y['foid (5 mi) 10 mise-Noble Gas mDem Wide Bo4(10mi) 10 mile-iodine . mnem SI# moid (10mi) Xu/O Table M.Td s.l. EAB 2 miles 5 miles 10 miles
@ Wind Direction From <- 1.0 A U 05) 1.3 06) U FM M FM
-1.0 to -0.9 B 5 A ES) 4.5 00) 7.7 F7) 7.1F7)
MAIN STEAM -o.a io -0.8 T i.2 e4' i.3 e5) 2.5 tei a.3e7>
~ " ' ~" " " " ' *" "" "'
EFWP TURBINE -0.3 to *0.8 E 2.6F4) 6.505) 2.3E5) 1.0 e5) i 3 (-4) 5 oosi 2d E5' Major Fuel Failure *" 'o 2.2 e 4.4 (-45 1.1 04) 5AE5)
> + 2.2 0 7.3 (4) 2.4 (-4) vo 9-oso um,fataa 1 20 Attachment 7.1 (15 or 22)
/ _ _ . _
Dals/Tima - Pri.il fass name Segrialune
@ @ l O O O O O U 0) @
Dose nale MoNITon ' Fl_OW nelease nate DOSE lodm' e/ Heloase nale DOSE Dose nale CONVEnSION c p lTOR nE0M FAcTon M?u$ '$ife*c ) FAcTon Tx'p3 T.R"' (DxGFibec FACTon [$NI PRM-IRE-5500A 9.44E-05 6.17E404 4.17E-04 7.65EiO8 PRM-IRE-55008 9.44E-05
- 0) O @ @ @
Exposure Dose Rate Xu Wind Dose Rate Projectecl LOCATION FactW o Speed mRAy Duration Dose = (/)x@ (mnem)
@ l,"J" $ 7 % ar mph @x@+0 (Hours) mnem Wide Body (EAB)
EAB-Noble Gas g ' EAB-iodine isl'our mnem Wb (EAB) mnem Wide Body (2mi) 2 mile -Noble Gas 2 mne -lodine H ~ ' mnem9foid (2mi) mnem'Whole Dody(5 mi) 5 mile -Noble Gas 5 mile -lodine mnem YEoid (5 mi) mnem Wide Body (10mi) 10 mile-Noble Gas d' (10mi) to mile -Imline mnem Noid Xur) Table Dg.Tg, s.l. EAB 2 miles 5 miles 10 miles
@ Wind Direction From <.1.0 A 1.1 ES) 1.3 06) 7.1(-7) 7.1 (-7)
-1.0 to -0.9 U 5 A ES) 4.5 (-6) 7.7 (-7) 7.1(-7) c i.2a) . 3en
. Main Steam 0.o io .o.. i.3 e5) 2.S i-o>
" '~ *"""
Steam Line Break -0.3 to *0.8 E 2.604) 6.505) 2.305) 1.0 e5) T 4a ai i.3 ai 5.ooSi 24 e5)
< l% Failed Fuel o.s io .2.2 2 A F4) 1.1 (-4) SA05)
> + 2.2 0 7.3 (4)
]
EP-2-050 Revision 1 21 Attachment 7.1(Ifof22)
/ Dil::/thne Print last namo Si0natura ,
O G U (9 i @ O O @ Release Hate O D se nate lodine / nelease Hale Dose Hale MoNIToH CONVERSION FLOW DOSE DOSE MONITOR RE(@ m FACTon M I[if3*0xC) FACIOR Yxp3I g Gas (DxGFh FAClon $7 PRM-IRE-5500A 9.44E-05 7.65E08 4.17E-04 6.17E104 PRM-IRE-5500B 9.44E-05 NOTE: -For sterm released throuah MC ES or s :ack, use' S .G. Tulx Rupture form. (D 0 0 @ @ U Dose Rate Wind Doso Rato Exposure Projected Xu LOCATION Factor O Speed mR/hr Duration Dose = @x@ (mnem)
$2 l,'on" M$ mph @x@+0 (Hours) mHom Whole Dody(EAB)
EAB-Noble Gas mnem MEid (EAB)
- EAB-iodine '
mnem Wide Body.(2 mi) 2 mile -Noble Gas mnemi ,d 2 mue -iodine .
. $oid (2mi) ndiem'WIole Body (5 mi) 6 mile -Noble Gas mnom II",% (5 mi) 6 mise -lodine mnem WImie D06(10mi) 10 mile-Noble Gas 10 ndie -iodine mnomM$id (10mi)
@ Xui) Table EAD 2 miles 5 miles 10 miles QglaM s.t.
,,3 p.3 7,,g.73 7,, g.73
@ Wind Direction From <. i .o 3 ,,, p33
-1.o 10 -0.9 D 5.4 (-5) 4.5 08) 7.7 (-7) 7.1 F7) c i.3 e ) 2.5 toi . 3e7)
Main Steam -o. ie .o2 . 2 c4 > 3.7 F5) 1.1 F5) 4.2 (-6i gg -0.8 to -0.3
-0.31o.0.8 D
E 1.8 04) 2.604) 6.505) 2.3F5) 1.0 05)
<l% Failed Fuel 0.8io 2.2 T 4.4 o4i i.3 o4) Soe5, 2.4eSi
> t 2.2 G 7.3 04) 2.4 (-4) 1.1 04) 5.40SJ vp. Losn om,lainn 1 22 Attachment 7.1 (17 or 22)
i
/ . D:12/Tima _ . _
Print nas name 04,c.ature
@ O O O e e Dose Hale o
lodine / e nolense Hale
@ 60 Dose Hale MONITOR ^ COtWEnslON FlDW Holoase Hale DOSE DOSE MONITOR nEM FACTOn h^h Ih*gBxC) FACTOn $'8 INigas (DxGfhoc FAClOn [g$d7 PRM-IRE-5500A 9.44E-05 6.17El04 4.17E-04 7.65El08 PRM-IRE-55005 9.44E-05 i
i It0TE: For steam released thre ugh HCES or stack, us e S.C. Tube Rupture Fo rm i (D 0 0 @ @ Exposure ! Dose Rate Xu Wind Dose Rate Projected j LOCATION Factor o Speed mR/hr Duration Dose 6)x@ (mnem)
@ d @ @F mph @=0+0 (Hours) mnem Wiole Body (EAB) l EAB-Noth Gas
- EAB-iodine mnem %% (EAB) mnem Wiele Dody(2 mi) 2 mile -Noble Gas .
2 mile -lodine mnem Sfy%d (2mi) 5 mile -Neble Gas mnem'Wiele Body (5 mi) 5 mais -iodine mnem $"y%d (5 mi) i mnem Wimle Body (10mi) 10 mile-Noble Gas ~ 10 mise -iodine mnemS@oid (10mi)
@ Xu/O Table Dg.Td s.l. EAB 2 miles 5 miles 10 miles 7.1(-7) 7.1 (-7)
@ Wind Direction From <.1.0 A 1.105) 1.3 06)
-1.0 to -0.9 0 5.4 F5) 4.5 06) 7.7 (-7) 7.1 (-7) c 2.56ai a 367' Main Steam -o.a ie -o.a
-0.8 to -0.3 D i 2 e4>
f 8 (-4) i.a e5i 3.7 F5) 1.1 (-5) 4.2 (-6) i Atmos. Dump Valve .,,,,,., , ,.,,.,
. ., y ,, ,.,es, ,.,,.,,
*o a'o.2.2 4.4 t4) i.3 04) 5.oo5 2.4e5)
- <l% Failed Fuel > t 2.2 F
G 7.3(4) 2.4 (-4) 1.l (-4) 5.405) EP-2-050 Revison 1 23 Attachement 7.1 (18 of 22)
/ Dal2/Tims _
Paint last name Ssoalute
@ @ O U Release Raio O O Dose Rate G
lodine / Release Rate U W @ Dose Hale MONITOR NHSION FLOW DOSE DOSE mNh FACTOR M_ c IT3 FAC10R $xI{ Nun 88 (DxGNtec FACTOR @ PRM-IRE-5500A 9.44E-05 6.17El04 1.04E-04 7.65E08 PRM-IRE-5500B 9.44E-05
- 0) 0 0 @ @ G Dose Rate Wind Dose Rate Exposure Projected Xu Duration LOCATION Factor o Speed mR/hr Dose = @x@ (mRom)
@ l,*om
- F M3 rnph @x@+Q (Hours) mRomWhole Body (EAB)
EAB-Noble Gas mnem Vlb (EAB) EAB-lodine mrem Whole Dody.(2 mi) 2 mile -Noole Gas ' mnem S ihfoid (2.mi) . 2 mile -lodine ' mrem Whole Body (5 mi) 5 mile -Noble Gas mrem d (5 mi) 5 mile -lodine mnem Whole Body (10mi) to mile-Noble Gas m%m Sho;<$ (10mi) to mile-lodine
@ Xur) Table t 5 miles 10 miles
.I,gTd s.t. EAB 2 miles 7.8E7)
<.1.0 A 1.1 ES) 1.3 (-6) 7.1(-7)
.@ Wind Direction From
-- ' YO to -0.9
- 5 A E5) 4.5F6) 7.7 (-7) -
7.1 (-7) non ~ c - 2* - Mai6 Steam . aa m -aa .
-0.8 to -o 3 D i.2ai 1.8 H) i.3 eSi 3.7Esl.. 1.1(-51 4 2 06)
-0.3 to .0.8 E 2.6 (-4) 6.5(-51 2.3f-5) ~ s.O F5) 5*5 24 (-Si
<l% Failed Fuel ~
o a m .2.2
> t 2.2
;TF 4a ai 7.3 (4) i.3 s>
2 A (-4) 1.1 (-4) 5AE5)
~ ' ~ ~ ~
EP-2-050 Revisioit 1 24 Attachment 7.1 (19 of 22). y- _
SYSTEM FLOS RATES l TABLI1 1
- 1. The stacx flod rate will vary as follows:
s Normal RAB - 91,400 cfm Normal 'EAB + 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 g valve) should be used in; Column C. If an ADV is partially open,
'x _the flow is determined by . i lI; -
t '1bm flow rate x (3.99 E3 cfm) = cfm c J E6 lom/hr - '4 ; i b. Stuck-open S.G. Saf ety (Relief) Valve
,- a\, e - ); '
A flow rate' of 9. 08 'E3 cfm per safety valve should be used for Column C. It is unlikely that more than one valve.will be stuck. 1 valve = 9.08 E3 cfm 2 valves = 2(9.08 E3) cfm\ and so on
- :f-
?\ If the value is stuck partially open, use the flow rate from s Control Room and ratio the efm as follows:
.bm flow rate (9.08 E3 cfm) = cfm 36 Eb lbm/hr t- s f c. Emergency FW Pump Tu'rbine l Release 1 i- ;
The Emerg. FW Pump r$ leases 188.8 cfm; use, this number in Column s C. .' LN A r,
-s, *e l ,) 7 EP-2-050 Revision 1 -
25 Attachment 7.1 (2#of42-) o y t . _ /- g e - - - - - -- -
l [] ,. .
< - , \ .
'd I (, SYSTEM FLOW
- RATES d ,a
' ~
I d. I Ha1a} Steam Line 9reak -l l,
\ '
\ . kN G- .?s
~
a,The.kainSteamLiseBreakwillnotgiveacontinuingreleaserate
, e
. but will empty the S.G. in less than two minutes (assuming
):5
'j , .
feedwater is stopped). Subsequently,the only releases will be
/ !. s ?
the amount of primary to secondary Jeakage. The Engineering
- Technical Assessment Group must be consulted for a flow rate for the primary to secondary leakage fate.
d For Main Steam Line Break: '
- 1) Record the Main Steam Line Monitor reading trier to the break p (conversion factor will not be valid after break).
> 2) Use 5.1 El efm for flow rate.
- 3) Use 2 min (1/90-hsurl for, release duration.
a
- 4) After initial release (2 min'), request Engineering Technical Assessment Group t'o provida flow rate of release due to primary-to-secondary release and calculate release based on Reactor Coolant Concentration (let-down monitor, grab-
. samples, etc.).
EP-2-050 Revision 1 26 Attachment 7.1 C3lof)CD
DOSE PROJECTIONS BASED ON PLANT MONITORING DATA FIGURE 1 WATERFORD 3 POINT GROUP SGENVIRO 03/t6/83 12:00:00 NO. OF POINTS : 14 12:00:00 A48500 PRI METR TWR 33 FT WIND SPEED 3 58 M/S 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 -0.55 DEG C 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 1 27 Attachment 7 1 GCloS$$)
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 Health Physics Coordinator at the TSC or the Radiological Assessment Coordinator at the EOF when activated. 2.1.1 Record field monitoring data on the data sheet. 2.1.2 Calculate the Net Count Rate at each location 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. Record the dose rate on the Calculation Worksheet, Block B. i NOTE The factor 1.85 E9 includes the child thyroid i inhalation dose factor from Reg. Guide 1.109, l Rev.1, dated October 1977, Table E-9, and a l child breathing rate of 7.04 liters per minute and appropriate unit conversions. The Dose Equivalent Iodine (D.E.I.) Factor incorporates the dose from other iodine isotopes not accounted for in the field measurement of air samples. l I EP-2-050 Revision 1 28 Attachment 7.2(lof[) l
DOSE PROJECTIONS BASED ON FIELD MONITORING DATA NOTE The D.E.I. 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 window reading from the data sheet) and/or child thyroid dose rate at that location 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 7.5. NOTE For projections to be valid, the meteorological conditions must be nearly constant during the transit time from release point to monitoring l point. I l 2.2.b To determine the projected whole body dose at any other location: i 1 2.2.6.1 Record the location. l l 2.2.5.2 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 ( Blo ck A x D -h C ) . Record in Block E. l ! EP-2-050 Revision 1 29 Attachment 7.2()$of7)
DOSE PROJECTIONS BASED ON FIELD MONITORING DATA 2.2.5.4 Record the anticipated or projected exposure in hours in Block F. (Use two hours unless specific data is available.) 2.2.5.5 DeterminetheprojectedwholebodydosebymultiplYingthewhole body dose rate by the release duration (Block E x F). 2.2.6 To determine the projected child thyroid dose at any other loca-tion: 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 Block 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 3.1 Data Sheet - Dose Rate and Air Sample Data Log-3.2 Child Thyroid Dose Rate Worksheet 3.3 Calculation Worksheet 3.4 Figure 1 - Dose Equivalent Iodine Correction Factor EP-2-050 Revision 1 30 Attachment 7.2(j%of7)
's r n -
w-w m- -w &
a- - - - c . - %*
. s C .
. H 2:
- a.:
E r x i H & r.a c CJ m E N W . abJ Z s ed D aC ow UW
=c
>= m w
2ll c
- c e wm
- CG >= c
( Z= *
-J c E Q
<o WvN O O w O w w A d
% w 6 a 4
^
k Sr . C = 2m= m-M, < ZE
- ::D
- T <C O m O Wvw a o to .
g . g 0
$W= -
< G y y-c < m> - '
Z W
< g _= w o- %
M J aC H w sc z M W _J eoe L3 > C < n cc mg L 3
.c Z N w K LE
. E O *-=
! w 3 w l *
< cp 3 cc wo mo t.aJ oE M .J=
u3
=
.C b
eC w i y I O c a I C l A *= l - I e l
. W L i J w .c I gg E C3 mg CC 1 $ WN
~
l O m M O w N 8 m 2 A' D W E l l . l
i i G t CilII.D TilYR0lp DOSE HATE WORKSilEET ; f
;; SAMPLE A B C D E i F e4 a net Vol. of D.E.I.
k Number Time I.ocation CPM ( sample Factor Conversion Child Thyroid Dose-k (from ) cu. ft. (Fig. 2) Factor Rate (mrem /hr) . y data) (from data )
- 2.97E-02 1
i Hultiply A x B', divide by C & multiply by D x E to get F: (A x B/C) x D x E = mrem /hr. The conversion factor converts DPH to uC1, cu. ft. to cc, and uCL/cc to arem/hr.: (4.55E-07 uC1/DPH)(3.53E-05 cu. f t./cc)(1.85El09 mren/hr-cc/uC1) .
= 2.97E-02 arem/hr/DPH. -
El!-2-050 Revision 1 32 At tachment 7.2 (5 of 7 )
. . I
- s'
. .g*
DOSE PRO.1ECTIONS BASED ON FIEl.D.,HONITORING DATA g cal.Cill.ATION FORKSilEET la tti 1.ocation: Date: , Time: .. Field Hon 1Loring and Heteorological. Data (A) Whole Body Dose Rate: mR/hr gl's d W d-(B) Child Thyroid Dose Rute: mR/hr , (C) X/Q: __ sec/m (for Field Honitoring Data Iocation)
. Projected Whole Body Dose DA E F G 3
1.ocation of X/Q (sec/m ) for Dose Rate '
. Exposure Duration Dose mrem Interest 1.ocation of Interest A x (D C) Ilours ExF EAB .
- 2. mit.ES 5 mit,ES -
10 mi t,E S
. Projected Child Thyroid Done
. IIA I J K 3
1.ocation of X/Q (sec/m ) for Dose Rate Exposure Duration Child Thyroid Interest Locatlon of Interest Bx ( 11 C) llours Dose IxJ mrem EAT 3 . 2 Mi t.E 5 5 mlLES - 10 kliI E S 7.1 Dose
- D and ll are X/Qs for the' location of interest or concern and can be determined [ rom Attachment
' Projections Based on Plant Honitoring Datagand 7.5. Heteorological Data.
Cniculated by: .
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DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE 1.0 PURPOSE This attachment provides the methods for calculating 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 loca-tion is performed using Worksheet 1. 2.1.1 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 based 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 The dose factors are determined from Reg. Guide 1.109, Rev. 1, dated October 1977, Table B-1. Conversion factors of 1.14 x 108 to convert mrem-m3 /pCi-yr to mrem-ec/,uCi-hr; 472 to convert cfm to ec/sec; and 1 x 10' to convert cc to m'3 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 F. EP-2-USO Revision 1 35 Attachment 7.3 ([ orld )
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 determined in Attachment 7.5. 2.1.9 Multiply the sum of Block D, the flow rate and the Z/Q (Column F x G x H) to determine the whole body dose rate at that location in terms of mrem /hr. Record the result in Column J. This 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 or can be projected, enter the duration in hours in Column K. 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) 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. 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 concentrations are expressed in terms of p.C1/cc. 2.2.3 Multiply the concentrations recorded in Column B by the dose factor for that isotope (Column C) and record in Column D. EP-2-050 Revision 1 36 Attachment 7.3(2Loff)
DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE NOTE The dose factors are determined from Re5 Guide 1.109, Rev. 1, dated October 1977, Table E-9, and a child breathing rate of 7.04 liters per minute. Conversion factors of 472 to convert . cfm to cc/sec and 6 x 10 to convert liters /per minute to ec/hr are included in the dose factor. 2.2.4 Sum 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 lon5 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 7.3 or 7.4. 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 I 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 EP-2-050 Revision 1 37 Attachment 7.3 (2ior 6)
DOSE PROJECTIONS BASED ON KNOWN ISOTOPIC RELEASE RATE projected thyroid dose per hour exposed in terms of mrem /hr exposed. Record the result in Column K. 2.2.11 If the release duration is known or can be projected, enter the duration in hours in Column L. 2.2.12 Determine the projected dose by multiplying the dose per hour ex-posed by the release duration (Column K x L). Record the projected child thyroid dose in Column M. 3.0 ATTACHMENTS 3.1 Projected Whole Body Dose Worksheet 1 3.2 Projected Thyroid Dose (Child Thyroid) Worksheet 2 EP-2-050 Revision 1 38 Attachment 7.3 (iIof dh)
PROJECTED 'nHOLE BO,0Y DOSE ' WORKSHEET 1 ( . Wind Speed: ' mph Wind Direction: From: Date: Time: . a.m./p.m. A B- l C 0 Concentration Dose Isotooe (uCi/ce) Factor BxC Kr-85m l l 63. l l Kr-85 l l .624 l Kr-87 l 319.- l Kr-88 l l 791. l Kr-89 l S93. l Xe-131m l l 4.92 l Xe-133m l - l 13.5
'Xe-133 l l 15.8 l .
l Xe-135m 168.
, /- Xe-135 97.4 l -
. Xe-137 l 76.4 l Xe-138 l l 475. l Block D = -
E I F G l H J K L i Dose Rate Excosure Oose Flow Rate X/Q (mrem /hr) Duration (m m ) i Location Block 0 (CFM) (sec/m3 ) yxgxg '(hr) JxK ta l l -l 2 Miles l l .l
- 5 Miles l
- 10. Mil'es l ,
I l Calculated by: l EP-2-050 Revision l Attachment 7 3([of d) _ _ . _ . - - . _ ~ _
~ PROJECTEDTHYR01DCOSE(CHILDTHYR0ZD)
WORXSHEET 2 C. - Wind Speed: mph Wind Direction: from: Date: Time: a.m./p.m. CHILD THYROID -- A l B 'C l D . ..
~ ~ ~ '~
Concentration Dose Isotcoe uCi/cc Factor BxC I-131 l l S.75E5 I-132 l l 1.04E4 l I-133 l 2.08E5 l I-134 l l 2.74E3 l I-135 l 4.27E4- l Block D = (' E F G H J X l L l M Dese Ra'e t (=rernjhr Exposure Dese Flow Rate X/Q Release exposed) Duration (mem) J.ccation Block D (sec/.n3 ) Fraction (CFM) FxExHxJ (hr) ' Xxt ru I l l- . t 2 Miles l l l l 5 Miles l l 10 Miles l l 4 l l l I I I 1. Calculated by: e e EP-2-050 Revision l gp Attachment 7. (Ich)
DOSE PROJECTIONS BASED ON FSAR ACCIDENT DATA 1.0 PURPOSE 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 available. 2.0 PROCEDURE 2.1 From the nine accidents identified on the worksheet, select the type of accident based on the actual occurrence (Attachment 7.4, page 3, FSAR Accident Assumptions, provides background information for this selection and is used for additional data). If no selection is possible, choose the worst case accident. 2.2 Using the Short Form worksheet, develop the 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 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. 3.0 ATTACHMENT 3.1 FSAR Accident Assumptions l l EP-2-050 Revision 1 41 Attachment 7.4([ordf)
FSAR ACCIDENTS - DOSE PROJECTIONS WORKSHEET Wind Direction: Date: - Time: -- Dose Factor Dose Rem Whole Body Whole Body ACCIDENT
- X/Q' Child Thyrcid Child Thyroid Main Steam Line Break x 2.55 E-2 2.16 El Inadvertent Steam Dump 1.02 T1 5 73 33 CEA Ejection Accident x 8.71 E3 2.47 tb Letdown Line Break x 2.73 E1 0.30 E3 S/G Tube Rupture x - 4.91 -
4.bb El Waste Gas System Leak x 8.96 p.u9 Loss of Coolant Accident x 6.91- E2
- 7. 16 E6 -
Liquid Waste Release x 1.91-2.54 E2 Fuel Handling Accident x 8 55 c 3.64 El
'For Exclusion Area Boundary, 914 m. Calculated by: -
EP-2-050 Revision 1 42 Attachment 7.4 (2,ofj[) L
. 1 1
FSAR ACCIDENT ASSUMPTIONS j
\
l This attachment provides the basic assumptions and radiological l 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 AND RADIOLOGICAL 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 a 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 ihis accident assumes a loss of off-site power'at the time of turbine trip and a 6.5 pCi/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 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 1 43 Attachment 7.4(3(ofM) ~ ^
- - , . --w-,,=~., n-., -
,.r.,
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)
An LOCA provides a release path to the environment via containment leakage pathways.
- 7. Ra'dioactive Waste Gas System Leak or Failure 1his 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 release to the atmosphere and a release of all liquids in the Boron Management System (BMS) and Waste Management System (WMS) to the Reactor Aux-iliary Building (RAB). Off-site doses will occur as a consequence of released noble 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 1 44 Attachment 7.4 ( of h )
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) -- x (2.78 *C) = - - -
*C Wind Speed (10 m) x (2.24 mph /mps) =- mph (mps is meters per seconds; mph is miles per hour)
Wind Direction (10 m) NOTE If primary tower data is not available, instruct individual to go to backup tower. 2.1.2 Contact the National Weather Service (NWS) by commercial telephone at (504) 522-7330. Obtain the following information from the NWS: Weather forecast for next 12 hours EP-2-050 Revision 1 45 Attachment 7.5(/of[h)
METEOROLOGICAL DATA Temperature lapse rate = -- - Wind Speed = Wind Direction = - 2.1.3 Determine the appropriate Pasquill stability class from the following table based on data obtained in section 2.1 above. Class Deitn- T 160 m- 10 mi- -C A - Very Unstable <-1.0 B - Moderately Unstable -1.0 to -0.9 C - Slightly Unstable -0.9 to -0.8 D - Neutral -0.8 to -0.3 E - Slightly Stable -0.3 to 0.8 F - Moderately Stable 0.8 to 2.2 G - Very Stable >2.2 Stability Index . 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 calculsbed: 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 (from Attachment 7.1, section 2.4). If the wind speed and/or distance f alls between two values on the tables, use the distance with the higher X/Q value. Record below. EP-2-050 Revision 1 46 Attachment 7.5 (Tsor/S) .
METEOROLOGICAL DATA Downwind Stability Wind Ilma DJstance Cinss Steed-Tmoh) XLQ isec/m ) To determine X/Q at locations away from the center line of the plume, use the Emergency Planning 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 (neutral), 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. 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.) EP-2-050' Revision 1 47 Attachment 75(3Iof//p
METEOROLOGICAL DATA 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 speed (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 Attachments 7.2 (Dose Projections Based on Field Monitoring Data), 7.3 (Dose Projections Based on Known Isotopic Release Data) and 7.4, (Dose Projections Based on FSAR Accident Data). l 1 l l l l EP-2-050 Revision 1 48 Attachment 7.5(fof/j$) 1
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GROUND LE VIL RILE ASE $I PASSUILL SIABILIIV CLASSI'C w - 0 o .seIO Bt USED dllHe** 30 Fl. Livil WINDS 13tFI-30FI OfLIA I {f WIN 05 FROM All Dl9ECll0MS . F6 PLUM [ W10lH 4MCIER58 o b WIND SPEED ESCLUSION 80090ARY
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~ PLUML WIDIst IS CENI[R[O ON 1810 ATFECl[0 $[CIOR DIRECil0N 8 . .
a
1 WATERFORD 3 SES !
- PLANT OPERATING MANUAL -l LOUISIANA POWER & LIGHT Ml0CLE SOUTH UTIUT.ES SYSTEM
[.f[3Q POM '!0LUME 18 , POM SECTION 2 APPROVAL DATE: May 2, 1983 E2::.CTIVE DATE: r,,n 3 y ,, , a DIERGENCY PLAN IMPLDIENTING PROCEDURE PROTECTIVE ACTION GUIDELINES . LP&L W- 3 .M ' ' - CONTROL A - COPY NO O 3 - I , PORC Meeting No. f 3 i 9 ,, Reviewed: n,;,, k_ f ^ P C Chair 4 Approved: 9. Cd[ Plant Manager-Nuclear L_
, WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. Ef-2-os z- Title ShM ride / brd &clL{sries Effective Date f 54118% (if different from approval date)
Comniate 1. B. er C A. Change No. NM a B. Revision No. . C. Deletion N N-WrAgog poM cgAgcg, MEVIsreg. OR DgtgTrog , 2 nr N-ovco 6/.+*e lrz, &b $+st * { u S~e...A.cLA,:>u#s yn erms, QA ib d.;)) 2.'] *e-h 2, m / L n J:-de m PG .
/ g '
d' REOUTRED SICMATURF3 Originator
- dbb Date 3/2-/[8~f
--* Technical Review [ '
Date 3/22//3 d . . 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 l 4. Create a condition or conduct an operation which ex-l ceeds, or could result in exceeding, the limits in I Technical Specifications? If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Saf ty Evaluation checklist.
- Safety Evaluation ll>YO Date 3[22)P3 Group /Dep't. Head Review N b did I 2 Date 3-23-91 _
O Temporary Approval
- Date (NCS)
Temporary Approval
- Date 1
QC Review / ## d(/d Date & A W 6' 3 PORC Review II2,a Y- Date MM ' Meeting No. P3 -3 7 4 Plant MangerINuclear Approval ' I//1 @ Date Nh *
' 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(o l
Emsrgancy Plan Impismsnting Procsdure EP-2-052 _ Protective Action Guidelines Revi'sion 2 TABLE OF CONTENTS
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1.0 PURPOSE
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL C'NDITIONS O
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7.0 ATTACHMENTS 7.1 Protective Action Guidelines Worksheet (1 page) 7.2 Affected Sectors /Protectivb Response-Areas Chart (1 page)~ 7.3 Evacuation Time Estimate Table (1 page) . 7.4 Protective Response Areas (1 page) 7.5 Flow Chart for Protective Action Decision-Making Based on Core Conditions (1 page) LIST OF EFFECTIVE PAGES
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Title Revision 2 1-12 Revision 2 1
Emergency Plan Implementing Proctdure EP-2-052 _ Protective Action Guidelines Revision 2 1.0 PURPOSE
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To provide guidance for protective action decision-making with respect to the EPA Protective Action Guidelines (PAG's) and those severe conditions where potential hazar'ds exist but dose projections are not required.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 Waterford 3 SES Evacuation Time Study
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2.3 EPA-520, Manual of Protective Action Guides 2.4 EP-1-010, Notifications and Communica'tions , 2.5 EP-2-050, Offsite Dose Assessment (Manual) , t 2.6 EP-2-051, Offsite Dose Assessment (Computerized) 2.7 NUREG-0654 Appendix 1 - Example Initiating Conditions - General Emergency 3.0 RESPONSIBILITIES 3.1 The Emergency Coordinator or designee is responsible for the implementation of this procedure. 3.1.1 Upon activation of the Emergency Operations Facility (EOF), this responsibility may be transferred to the EOF Director or h'is designee. l-4.0 INITIATING CONDITIONS , This procedure shall be initiated upon reaching any of the. t following conditions: l 4.1 Declaration of a General Emergency 4.2 An emergency condition requiring dose assessment / projections has been decl a red at Waterford 3 SES 2
l Emsrgancy Plan Implcmanting Procaduro EP-2-052 _ Protective Action Guidelines Revision 2 i l 4.3 As instructed by other implementing procedures 4.4 At the direction of the Emergency Coordinator (or EOF Director) 5.0 PROCEDURE NOTE This portion of the procedure provides the instructions for using the Protective Action Guidelines Worksheet, Attachment 7.1, to determine the need for offsite protective actions with respect to dose projections. This worksheet is also the record of decisions
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made. t 5.1 Obtain the whole body and child thyroid dose rates for the locations of interest from the Health Physics Coordinator (for the Emergency Director) or the Radiological Assessment Coordinator (for the Emergency Operations Facility Director). 5.2 If the duration of the release is known, perform section 5.2. If the duration is unknown, proceed to section 5.3 and do not perform section 5.2. 5.2.1 Calculate the projected whole body and child thyroid doses by
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multiplying the dose rates by the release duration. 5.2.2 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 dose projections for protective actions determination. 5.2.3 If the calculated dose is less than 5 rems whole body or 5 to less than 25 rems child thyroid, recommend sheltering and access control to the affected areas as protective actions. 3
Emergency Plan Implementing Proceduro EP-2-052 ._. Protective Action Guidelines Revision 2 NOTE The affected area will be identified according to Attachments 7.2 and 7.4. If a major portion of the plume lies in any given protective response area, protective action recommendations are given for that entire area. I 5.2.4 If the projected dose is greater than. 5 rems whole body or 25 rems child thyroid, determine the protective actions based on the
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duration of the release. 5.2.4.1 If the release duration is greater than two (2) hours, recommend evacuation and access control of the affected areas as protective actions. l 5.2.4.2 If the release duration is less than two (2) hours, determine Plume Travel Time (PTT) and Estimated Evacuation Time (EET). s D 4
Emergency Plan Implementing Procedure EP-2-052 __ Protective Action Guidelines Revision 2 NOTE Determine the Estimated Evacuation Time by comparing the affected sectors with the protective response areas as shown in Attachment 7.4 and correlating these sectors to Attachment 7.3, Evacuation Time Estimate Table. In estimating evacuation times, local constraints such 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 popula-tion of interest) by the wind speed. ", 5.2.4.3 If the Plume Travel Time is less than the Estimated Evacuation i Time, recommend sheltering and access control to the affected areas as protective actions. 5.2.4.4 If the Plume Travel Time is greater than the Estimated Evacua-l tion Time, recommend evacuation and access control to the af-fected areas as protective actions. 5.3 Duration of Release is Unknown . NOTE The affected area will be identified according to 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 l
Emergency Plan Implementing Procedure EP-2-052 __ Protective Action Guidelines Revision 2 5.3.1 If whole body dose rate is less than 250 mrems/hr and the child thyroid dose rate is less than 1250 ~mrems/hr, no immediate protective actions are needed. 5.3.2 If whole body dose rate is greater than 250 mrems/hr-but less than 1250 mrems/hr, or if child thryoid dose rate is greater than 1250 mrems/hr but less than 6250 mrems/hr, recommend sheltering and ac-cess control to the affected protective response areas. 5.3.3 If whole body dose rate is greater than 1250 mrems/hr or if child thyroid dose rate is greater than 6250 mrems/hr, recommend evacuation and access control to the affected protective response - areas. 5.4 Protective Action Decision-Making Based on Core Conditions (Attachment 7.4) . 5.4.1 For core melt scquences 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 ex-posure Emergency Planning Zone under this circumstance. i 5.4.2 For core melt sequences where significant releases from , containment are not yet taking place; containment failure leading to a direct atmosphere release is likely in the sequence but not imminent; and large amounts of fission products in addition to no- , ! ble gases are in the containment atmosphere, consider precautionary evacuation to 5 miles and 10-mile downwind evacua-tion (45- to 90- degree sector). - 5.4.3 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 L
Emergency. Plan Implementing Procedura E'P-2-052
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Protective Action Guidelines Revision 2 those areas where evacuation cannot be completed before transport of activity to that location. . 6.0 FIN AL CONDITIONS 6.1 The radiological release has stopped or diminished and dose projections are below Protective Action Guidelines. 6.2 The emergency condition has been closed out and recovery actions are underway. 7.0 ATTACHMENTS 7.1 Protective Action Guidelines Worksheet 7.2 Affected Sectors / Protective ResponseA'reas Chart , 7.3 Evacuation Time Estimate Table . 7.4 Protective Response Areas 7.5 Flow Chart for Protective Action Decision-Making Based on Core Conditions f O 7
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. i PROTECTIVE ACTIONJ GUIDELINES. WORKSHEET .
d il .
- PROT. RESR AREA DATE
. .DETERMlHE , DISTANCE _
TIME , ' DOSE RATE l mR/tr. Wil BODY PTT USER , mR/hr. CllLD Tirt ! ETT
. s PROJECTED DOSE - DURATION OF NO ) 250 mR/hr. W B P NO NO IMMEDI AT E RELEASE' KNOW 7 R WHOLE BODY , PROTECTIVE ACTION ggq3 ' ' .) 1250 mR/hr. THY.P R CHILD THY. *
, . . . ,' '.. . YES s ,. .' ?
NO PROTECTIVE NO ) i R WilOLE BODY? ,
) 1250 mR/hr. W B P NO 08 '.' SiiELTER ACTIONS i
> SR CilLD TilY P , l .
> 6250 mR/hr. THYP YES .
, . YES NO ) 6 R WHOLE BODY? , , . ,-
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' . 1 YES DURATION EVACUATION I
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EVACUATION
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s, EP- 2 -052 REV. 2 ' i- s' L- ACHMENT 7.1
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( l OF i )l
AFFECTED SECTORS / PROTECTIVE RESPONSE AREAS CHART - AFFECTED SECTORS 0.2 mile 2-5 mile 5-10 mile A,B,C A1 A2, B2 A3, B4 B,C,D A1, B1 A2, B2 A3, B4 C,D,E B1, D1 B2, D2 B3, B4 . D,E,F C1, D1 B2, D2 B3, B4, D3 E,F,G D1 B2, D2 B3, B4, D3 F,G,H D1 D2 B3, D3, D4 G,H,J D1 D2 -D3, D4 H,J,K D1 D2 D4 J,K,L C1, D1 C2, D2 C4, D4 K,L,M C1, D1 C2, D2 C4, D4 L,M,N C1 C2 C4 M,N,P C1 C2 A4, C3, C4 . N,P,Q C1 C2 44, C3, C4 P,Q,R C1 A2, C2 A4, C3 , Q,R,A A1, C1 A2, C2 A3, A4 R,A,B A1, C1 A2, C2 A3, A4 , EP-2-052 Revision 2 9 Attachment 7.2 (1 of 1)
1 EVACUATION TIME ESTIMATE TABLE (#) - Clear Weather Adverse Weather ; Evacuation Sector Hours Minutes Hours Minutes 0-2 C1 1 45 1 45 D1 2 15 2 30. B1 No Population No Population A1 1 45 1 45 . Entire 2-Mile Area 2 15 2 30 0-5 C-2(SA) 2 15 2 30 D-2 3 30 4 30 B-2 3 30 4 15 C-2( NW) 5 15 7 30 Entire 5-Mile Area 5 15 7 30 0-10 C-4 2 15 3 00 D-4/D-3 4 45 6 00 . B-4 3 45 4 30 A-2,A-3,A-4 5 15 7 30 , Entire 10-Mile Area 5 15 7 30 , t
- Time to completely evacuate an evacuation area measured from the time of mobilization 1
l i ( EP-2-052 Revision 2 10 Attachment 7.3 (1 of 1) l l y,. . _ , - -
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RESPONSE AREAS - EP 2-052 Rev. A . jf Attachment 7.4 (1 of 1)
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FLOW CHART FOR PROTECTIVE- ACTION DECISION .- MAKING BASED ON CORE COND-ITIONS EMERGENCY DECLARED V SUBSTANTIAL CORE DAMAGE IN PROGRESS OF PROJECTED V
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LARGE NO FISSION PRODUCT YES
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ARRIVAL EVACUATED OTHERS . [g. y R ECOM M END . RECOMMEND EVACUATION OF EVACUATION OF. 2 MILES RADIUS & 5 MILES RADIUS & 5 MILES DOWNWIND 10 MILES DOWNWIND Y CONTINUED
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ASSESSMENT
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EP- 2 -0 5 2 R EV. 2 ATTACH M ENT 7. 5 ( l OF 1 ) g
WATERFORD 3 SES PLANT OPERATING MANDAL LOUISIANA MIDDLE SOUTH UTluTIES SYSTEM POM VOLUME 19 h'7jg0 1 POM SECTION ? APPROVAL DATE: EFFECTIVE DATE: DIERGENCY PLAN IMPLEMENTING PROCEDURE RADIOLOGICAL FIELD MONITORING Lpg W-3 BECORM
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E NO.- 1 PORC Meeting No. 8A-0Jdl Reviewed: kk 1 l0RCCharpa Approved: UN Plant Manager-Nuclear -*- = = - y ,- - m- 2----c.-- -,.,,m,-
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST - Procedure No. GP 1~C6o Title L-kir~ J' ?O %I Effective Data MLd (if different from approval date) f%= ni s ta 1. B. eC A. Change No. ' B. Revision No. I C. Deletion MIA WW1 MOM FOR CHANCE. RE7TSTON. OR DFLTTTOM 0&Mbw Dnkb% a n fYd$ (L M N
/ / l RKOUTMFD STCv1Tf1BF3 Originator- kDisc> U Date ' 4 l L'L- 8 -
Technical Review O>e-W & a w V p.g. dha. 6 5 . O SAFETT EVALUATION - Doss this change, revision, or deletion: TES No
- 1. Change the facility as described in the F3AR7 Y
- 2. Change the procedures as described in the F3AR7- _, Y 3 Conduct tests / experiments not described in the F3AR7
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- 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 Eare Evaluation checklist. Safety Evaluation de O Date T D ~ E 3 Group /Dep't. Head Review 4 N dd d Da te V -D- O - U Temporary Approval
- Date (NOS)
Temporary Approvals Date - -- QC Review / A4 eM/ L /u Date 4#- A f- E3 - PORC Review I I
- d W a 'f 4 M Meeting No. f3 - 174 PlantManhrMuclearApproval b 'b'l -
Date S//8 4
- Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2sh! --
th/r/b bu tb n h W ny. W ah/ ?b w A r /v n s h e T- - - - - - -
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7 ~/ 4 REOUTRED SIGNATUR}/ Originator 4
- Date k b I k 'O' ----
Technical Revie[--k b ~
- -- -- Date - ll-MO '- -
0 1 SAFETY EVALUATION
,. w Does this change, revision, or deletion: . YES NO -
./ 1. Change the facility as described in the FSAR? .&
Change the procedures as described in tne FSAR? u 2.
- 3. Conduct tests / experiments not described in the FSAR7 U_.'
Create a condition or conduct an operation which ex- 4. ceeds, 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 6Nd- -- - Date NO -- Group /Dep't. Head Review N badt --- Da te 'll-[7-A L- - V / Temporary Approval
- Da te - - -
- (NOS)
Temporary Approval * ' - -~ --- Date - QC Rev1eu & W & - e *-' - - r Date - J~ / 3 ' M- - - - - PORC Review N 'hM Da l-l i-I ? - -- Meeting No. bd1-8 M PlantManagerYuclearApproval M N4) - - -- - - Da te dM Q I-
' Temporary approval must be folicwed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 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 Dose Rate & Air Sample Dati Log (1 page)
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7.1 j 7.2 Radiological Field Monitoring Kit Location and Contents (1 - page) 7.3 Ludlum 2218 Switch / Meter Locations (2 pages) LIST OF EFFECTIVE PAGES Title Revision 1
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1-14 Revision 1 D i 1
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 1.0 PURPOSE To define the methods and techniques to be utilized in performing field monitoring following a suspected release of radioactive material. 2.0 RFFERENCES 2.1 EP-2-050, Offsite Dose Assessment (Manual) 2.2 EP-2-051, offsite Dose Assessment (Computerized)
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3.0 REs poN sIBILITIrs The Radiological Field Monitoring Teams are responsible for , implementing this procedure. 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 the event includes an actual or potential release of radioactive material to the atmosphere. 4.1.1.1 Alert 4.1.1.2 Site Emergency . 4.1.1.3 General Emergency 4.1.2 At the discretion of the Health Physics Coordinator (HPC) or the f[ , Radiological Assessment Coordinator (RAC). 5.0 PROCEDURE 5.1 Assignment of Radiological Field Monitoring Teams 5.1.1 The assignment of personnel to Radiological Field Monitoring Teams will be made by the Radiological Controls Coordinator at the direction of the Health Physics Coordinator. 2
i l Emergency Plan Implementing Procedure EP-2-060 ' I Radiological Field Monitoring Revision 1 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 j monitoring assignments upon initial notification of certain team i members. The Radiological Field Monitoring Teams, as assigned, will proceed to the nearest storage location for field monitoring kits as identified in Attachment 7 2. 5.3 The team shall obtain kit. Kits with broken seals should be avoided . unless necessary. , 5.4 Each kit will be opened and quickly inventoried. Inventory lists , are posted inside the individual kits. 5.5 In addition to the inventory, the following equipment checks shall be performed: 5.5.1 R0 Visual Check and Battery Check s 5.5.2 Ludlum 2218 ano Detector - Visual Check and Source Check with Barium-133 Source 3 i
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 NOTE
- 1. This check is nat 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 ! I by the Radiological Assessment Coordinator. g The onsite field monitoring teams will l remain under the direction of the HPC. ij ; i a 5.5.3 Radio Communications Check - Communications must be established prior to leaving the OSC. 5.b.3 1 For Alert emergencies (Technical Support Center activation), ' establish communications with the Dose Assessment Coordinator. 5.b.3 2 For Site and General emergencies (EOF activation) establish com-munications with the Field Monitoring Communicator at such time that responsibility for dose assessment has been transferred to the EOF. I 5.6 During initial communications check, each team will receive a team designation (Alpha, Bravo, etc.) from the HPC/DAC and initial - instructions, i 5.7 Each team shall leave the OSC and obtain their designated vehicle. 4
1 1
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- E.ergency Plan I=ple=enting Procedure E?-2-060
- +1aiological 7.1 eld Monitoring Revision 1 NOTE , ...
As soon as they leavb the'OSC, the dose rate instru=ent should be turned on and monitored continuously. The HPC/DAC or RAC should l be updated on dose rates and location frequently, about every 2-3 minutes. 1 5.0 Proceed to the location as identified by the HPC/DAC or RAC. At l that location, perfor= the following: 5 d.1 Ga==a survey with R0-2 5.3.2 Beta survey (open-window) with R0-2 . NOTE .. Surveys should be perfor=ed with R0-2 held vertically at one (1) =eter above ground level. The =enitor should slowly rotate 360 degrees and deter =ine the =axi=u= dose rate.
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I 50 Notify the H?C/DAC or RAC of tne levels =enitored. l 5.9 1 If levels are below the mini =u= sensitivity of the instrument, ' l report results as "less than" the mini =u= scale deflection. . eWLY Tv Mpc)DMC. UNLESS OTHERwSE EEQUEST. 5.9.2- Report a==a srd-beta levels 41s "nic d cia.se ;.. ;;;=; :nd 2 EE AEcoA( D EO BuT W oT C:,w /
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REPORTED. 5.iO Reccrd all data on Attach =en: 7.1. 1 5.11 Unless otherwise directed by the H?C/DAC or RAC, obtain an air sa=- ] ( pie at this locati;n as fcilows: 5
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 5.11.1 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 filter must be inserted so that air passes through in the direction of the arrow on the side of the filter. 5.11.2 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. 5.11.3 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. 5.11.4 While air sample is running, prepare two envelopes, labeling each with the following information: , l 5.11.4.1 Date and Time 1 5.11.4.2 Sample Number 5.11.4.3 Location l 5.11.4.4 Flow Rate (CFM) 5.11.4.5 Sampling Duration (minutes) 6
1 l Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 , l NOTE Samples will be given a sequential number preceded by the team designation, i.e., A1, A2, A3, or B1, B2, and so on. ; 5.11.5 After appropriate volume is collected, stop air sampler, remove particulate filter and silver zeolite cartridge and place into envelopes. . 5.11.6 Record all sample data on Attachment 7.1. 5.12 Unless otherwise directed by the HPC/DAC or RAC, analyze the air j 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. c NOTE i Background radiation levels may interfere with - l counting equipment. If dose rates exceed 5 l l mR/hr, do not attempt to count filters; proceed to low background area. 5.12.1 Verify (or set) the following settings on the Ludlum 2218 (see Attachment 7.3 for location of switches): Switch Position A. Stabilizer Toggle Switch On B. Channel 1 Toggle Switch In C. Channel 2 Toggle Switch Out D. Channel 1 Window 40 7
Emergency Plan Implementing Pro'cedure EP-2-060 Radiological Field Monitoring Revision 1 Switch Position . E. Channel 1 Threshold 344 F. Channel 1 Multiplier Bypass G. Channel 2 Multiplier Bypass H. Add-Off-Subtract Switch Channel 1 Add I. Add-Off-Subtract Switch Channel 2 Off J. Live-Clock Toggle Switch Live - K. Time-Multiplier Switch X1 L. F-S Toggle Switch S M. CH1-CH2-Sealer Switch CH1 N. Range X1K (Initially) O. Recycle Toggle Switch (on back) Off NOTE Range setting should be reduced during count-ing to give on-scale reading. 5.12.2 Detector Operation and Setup t 5.12.2.1 Verify that the NaI detector is connected to the Ludlum 2218. l. 5.12.2.2 Insert detector into shielded sample holder. 5.12.2.3 Place power selector switch to "BATT." Allow approximately 5 minutes for equipment to stabilize. 5.12.2.4 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. 8
Emergency Plan Impleme'nting Procedure E?-2-Gi0 I Radiological Field Monitoring Revision 1 5.12.2.5 Place silver zeolite cartridge in shielded sample holder with the inlet side of the cartridge facing the detector. 5.12.2.6 Reset count timer to 5 minutes and push the COUNT RESET button. Count sample for 5 minutes. Record on Attachment 7.1. ( 5.13 Notify the HPC/DAC or RAC of the results of sampling and analysis [ for I-131 including: 5.13.1 Team Designation 5.13.2 Sample Number - 5.13.3 Sample Location 5.13 4 Sample Duration , f 5.13.5 Sample Flow Rate 5.13.6 Total Sample counts (5-min, count) 5.13.7 Total Background Counts (2-min. count) 5.14 Proceed as directed by the HPC/DAC or RAC to additional monitoring points. Continue performing surveys and air sampling / analysis as l. directed. 5.15 While in transit to monitoring points, maintain continuous dose rate monitoring and notify the HPC/DAC or RAC of any significant l l findings, paying particular attention to the location of the highest measured dose rates. i 5.16 Retain all air samples in plastic bags. NOTE The HPC/DAC or RAC will designate a specified ! location where all samples and data sheets will
- be returned.
l l 9
Emergency Plan Implementing Procedure EP-2-060 Radiological Field Monitoring Revision 1 6.0- FINAL CONDITIONS 6.1 Releases have 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 All da ta sheets, particulate filters and silver zeolite cartridges have been returned to the location defined by the HPC/DAC or RAC. , 7.0 ATTACHMENTS 7.1 Dose Rate & Air Sample Data Log l 7.2 Radiological Field Monitoring Kit Location and Contents 7.3 Ludlum 2218 Switch / Meter Locatioh~s o N 10
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RADIOLOGICAL FIELD MONITORING KIT LOCATION AND CONTENTS l Kit Locations Operational Support Center 3 Kits , Kit Contents Item Number Particulate air sample filter 1 bx Silver zeolite sample cartridge 10 ea Portable radio 1 ea Stopwatch 1 ea Clipboard -1 ea
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Writing pen 1 ea Flashlight 1 ea Battery, D-cell 2 ea - Writing pad 1 ea , Sample bag 12 ea ' Survey maps Dose rate meter (RO-2 or R0-2A) 1 ea I 1 ea Air sampler, battery-powered Gamma analyzer, Ludlum 2218 and 1 ea NaI Detector w/ cable Shielded sample holder 1 ea 4 EP-2-060 Revision 1 12 Attachment 7.2 (lofl)
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WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA U vicci.! scurs UTutES SYSTEM EF-2-070 " i PCM VOLUME I8 REVISION y APPROVAL DATE: May 2, 1963 gjyf?
?CM SECTION 2 E.M CTIVE DATE: r. . ,, , r ,g DfERGENCY PLAN DIPLDIENTING PROCEDITRE - - . - . _ ..
FRCIECTED AREA EVACUATION LP&L W-3 RECOROS CON"RO'_ LED CO?Y NO.- fNf-
? CRC Mee: Lag no y y ., y Reviewed: 4 A,, , f [ ~[-{C
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APP rove Flant Manager-Nuclear l
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i j WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 8b 2-0 T Title [#h 2// O + f.mnudam Effective Date -b/ dd (if different from approval date) Cemolete A. B. e r- C A. Change No. / B. Revision No. 1 C. Deletion ///4 REASON FOR CHANGE. REVISION. OR DFLFTION Jn b M W n 1 C u c w ,f l y e. m L -t/s kl. ui vte , <v --80 y s i i
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REQUIREDSIGNATUles l originatorYfMfcGb Date E/ / Technical Review s Y[N/A $1M d' Date NAf 3[d v SAFETY EVALUATION Does this changa, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR7 /- '
- 2. Change the procedures as described in the FSAR7 v
- 3. Conduct tests / experiments not described in the FSAR7 6 '
- 4. Create a condition or conduct an operation which ex- //
ceeds, 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 Safe Evaluation checklist. Safety Evaluation $" Date b- 72 % Group /Dep't. HeadRevYew mad. Date 3 N ~8 3 y j - Temporary Approval
- Date (NOS)
Temporary Approval
- Date
_ _ . _ _ _ QC Revie IINOM Date #- f- # ? PORC Review M h M . Date f - i c -4 b Meeting No. F3 89 Plant ManagerbN uclear Approval NO Date W/M
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) l 2G
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. CP- 2 -O'70 71tze PM %ff Effective Date D ' ' en (if different from approval date) Cemolete A. B. e ra C A. Change No.YdN b B. RevisionNo.T[c 2. C. Deletion Md RFAMON FOR CMANOE. REVTSTOM. OR DFLFTION
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NRC REQUIRED STcNATURFs Originator- Oe Date h2 i !#7 Technical Review kv 8 b'bq Date 3 3 3 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- # ceeds, or could result in exceeding, the limits in Technical Specifications? If the answer to any of the above is yes, complete and at-
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tach a 10 CFR 50.59 Safety Evaluation checklist. Safety Evaluation OX Obatk Date 3 -:LI -3 ^*s Group /Dep't. Head Review h OSa b Date 3'2-I-83 w 4 Temporary Approvale Date (NCS) _ _ . Temporary Approval
- Date
.. .QC Review . MA All : A- Date 4' W 79 - PORC Review [ d [ h Data MM4 ' Meeting No. 13-'74 Plant Man d dNuclear Approval NN Y Date "N #8
' 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(a 1
Emergency Plan Implementing Procedure EP-2-070 Protected Area Evacuation Revision M TABLE. OF CQ!LIENTS ..,. .. .. . 1.0 PURPOSE 2.0 REFEREN CES 30 RES PONSIBILITIES 4.0 INITIATING CONDITIONS . 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS
?
7 .1 Owner Controlled Assembly Areas / Evacuation Points , LIST OF EFFECTIVE PAGES
- .- . g - g - -- a - - - .-- - --
1-6 Revision 1 l Jb C % I s*/1}Fb t-v cQ t 21993 h46 -
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Emergency Plan Implementing Procedure EP-2-070 Protected Area Evacuation- Revision /Jqjk{f/ 1.0 PURPGsE This procedure provides a method by wnich personnel are ex-peditiously evacuated from the protected area. 2.0 R EFO R EN CEs 2.1 Waterford 3 SES Emergency Plan . 2.2 EP-2-071, Site Evacuation 23 EP-1-030, Site Area Emergency f 2.4 NUREG 0654, FEMA. REP-1, Rev. 1 2.5 PS-16-103, Accountability of Personnel.'During Emergencies 2.6 EP-2-081, Search and Rescue 2.7 EP-2-190, Personnel Accountability. 30 REsRansisILITIEs The Emergency Coordinator is responsible for implementing this procedure. 4.0 INITIATING CONDITIONS
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4 .1 Declaration of a Site Area Emergency l 4.2 As directed by the Emergency Coordinator 5.0 RRoCEDURE 5 .1 The Emergency Coordinator shall direct that the appropriate alarm be sounded and that an announcement be made in accordance with EP-1-030, Site Area Emergency. l. i 5.2 All essential personnel shall report to their preassigned stations and carry out emergency duties in accordance with the Implementing Document. i l 2
l Emergency Plan Implementing Procedure EP-2-070 Protected Area Evacuation Revision JAl8# 'I f/416 1 . 5.3 The Emergency Coordinator shall inform Security of any hazardous (i.e., fire / smoke, radiological, toxic enemical) areas on site so 4 that they will take adequate steps to prevent evacuating personnel from entering these areas. 5.4 All personnel within radiation controlled areas shall perform the , following: 5.4.1 Stop work and place any machinery or equipment in a safe condi- ,, tion. 5.4.2 Follow normal Health Physics procedures for exiting radiation l controlled areas. 5.4.2.1 Nonessentisi oersonnai shall proceed as directed'by the HP Control Point Watch to the appropriate access point shown in At-tacament 7.1, or as directed by Security. 5.4.2.2 Essential oersonnel shall report to their preassigned station and carry out emergency duties in accordance with the Implementing Document. ) 5.4.3 Once nonessential personnel reach the access point, they shall drop their badge / key cards and thermoluminescent dosimeters into the access collection box. Personnel shall proceed to the Administration Building parking lot and obey instructions given by Security. 5.4.4 Accountability snall be performed in accordance with Security Procedure PS-16-103, Accountability of Personnel During Emergencies, and EP-2-190, Personnel Accountability. . 5.5 Nonessential personnel within the protected area and outside radia- . tion controlled areas shall do the following: 5.5.1 Personnel snall stop work and place machinery or equipment in a safe condition. i 3
Emergency Plan Implementing Procedure EP*2-070 ( Protected Area Evacuation RevisionJa/$k*9 TB,gh 5.5.2 Personnel shall proceed. to. Primar.y Access Point- shown on At- . -2 tachment 7.1, or as directed by Security. 5.5.3 Upon arrival at the Primary Access Point, personnel shall drop badge / key cards and thermoluminescent dosimeters into the access collection box. Personnel shall proceed to the Administration Building parking lot and obey instructions given by Security. 5.5.4 Accountability shall be performed in accordance with Security Procedure PS-16-103, Accountability of Personnel During Emergencies, and EP-2-190, Personnel Accountability. d' 5.6 Nonessential Personnel Within Administration Building and Trailer City 5.6.1 Personnel snall stop work and place any machinery or equipment in a safe condition.
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5.6.2 Personnel shall proceed to the appropriate access point shown on Attachment 7 1 and deposit their personnel accountability disks (PAD's) into the PAD collection container at the access point. 5.6.3 Personnel shall proceed to the Administration Building parking lot, or as directed by Security.
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5.6.4 ~ Upon arrival' at the main parking lot, personnel shall obey instructions given by Security. 5.6.5 Accountability shall be performed in accordance with Security j Procedure PS-16-103, Accountability of Personnel During Emergencies, and EP-2-190, Personnel Accountability. ! 57 Nonessential Personnel Within Construction Area - ! 571 Personnel within the Construction Area shall exit via the access point near the EBASCO Building shown on Attachment 7.1, and deposit their PAD's into the PAD collection container at the ac-cess point.
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Emergency Plan Implementing Procedure - EP-2-070 Protected Area Evacuation Revision /Alb4 *'# r/92 Personnel shall proceed tortha Administt atron-Building paricivigr--- 5.7.2 lot, or as directed by Security. 5.7.3 Upon arrival at the main parking lot, personnel shall obey instructions given by Security. 5.7 4 Accountability shall be performed in accordance with Security ) Procedure PS-16-103, Accountability of Personnel During Emergencies, and EP-2-190, Personnel Accountability. i 5.8 In the event a General Emergency is declared while personnel are in the process of evacuating the protected area, personnel shall obey instructions delivered over the public address system. 5.9 In the event the emergency is reclassified as an Alert or Unusual Event while personnel are in the process of evacuation, ac-countability shall be completed before they return to their work areas. 6.0 TMAL counTTinNs This procedure shall be complete when: 6.1 Evacuation to assembly areas is complete, and 6.2 Accountability results have been delivered to the Emergency' Coordinator, and 6.3 EP-2-081, Search and Rescue, has been implemented, or 6.4 Site Area Emergency has been escalated to a General Emergency, in which case EP-2-071, Site Evacuation, shall be implemented. 70 ATTACHMENTS . 71 owner controlled Assembly Areas / Evacuation Points 5
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WATERFORD 3 SES PLANT OPERATING MANUAL
," LaulSIANA POWER & LIGHT
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EP-2-071 efy/ PCM VOLUME 5e REVISION J May 2, 19 83 gjy3 FCM SEC* ION ' APPROVAL DATE: EFFECTIVE DATE: Fuel Load DIERGENCY PLAN IMPLEMENTING PROCEDURE SITE EVACUATION , LP&L W-3 RECORDS CONTRO;_!_EJ COPY ~ g no, 62'i PORC Maecing No. fd- /74 I Reviewed: ;~p4 I%
#PCRC Chair:: tan Approved:
- Planc Manager-
. Nuclear l
i - [ _ -- _ _ _ _ _ _ _ - _ - -
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. It 07/ 0 Title b 9. twe %dk Effective Date A d d-r-cl (if different from approval date) Comolete A. B. o r- C A. Change No. l B. Revision No. 1 . C. Deletion af4 RFASON FOR CHANGE. REVISION. OR DELFTION
$O MarYe tswenM 1m en dlJ k21 1 110 eV kJ OMH &$M f /
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REQUND SIGNIT4RES/ Originator Y - (C t'M bb c-<A Date Technical bview v
#M9 @8M v -
Date A//4 9u 8 d SAFETY 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 h
- 3. Conduct tests / experiments not described in the FSAR7 I-
- 4. Create a condition or conduct an operation which ex- h ceeds, 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 50.596Saf,e+y 7 Evaluation checklist. Safety Evaluation /r Date $~ 94 b l Group /Dep't. HeadRebew @ddoM 2 Date 5 ' 9 -E h U 1 Temporary Approval
- Date (NOS)
Temporary Approvals Date QC Review 8 W Y Awk Data S /3 PORC Revie k R/W b Oek Date F- 10 'U Meeting No. fi >f PlantManageNNuclearAppr4 val . Date M0/A 4 ( ' Temporary approval must i:e followed by Plant Manager-Nuclear approval within 14 days. UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 2G
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 69-2-OH Title AA Effective'Date E t 'can (if different frem approval date) Cemelete A. B. e* C $3 A. Change No. W* ga B. Revision No. D 1 Jpi ,IA g , C. Deletion ANd REASON FOR CHANCE. REVISION. OR DetETTON To fe Y Ar-- _h k [w MO A/A C NN G. ?- A MEOUTWED STOM ATU973 Originator hd Date. 8 3 Technical Review NMbibu - Date 3 U43 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 k'
- 3. Conduct tests / experiments not described in the FSA27 /
- 4. Create a condition or conduct an operation which ex-ceeds, 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 h OS A- Date 3 2.I -b'7 Group /Dep't. Head Review *
%McN Date L U,P T
. Q Temporary Approval
- Date (NCS)
Temporary Approval
- Date QC Revieu / WA WJ- Date _ A- WM "I -2 Y M ate 4MM PORC Revi Meeting No. T5-/74 PlantMana'gedNuclearApproval ' MFA Date O **'A
- Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) I fo
Emergency Plan Implementing Procedure EP-2-071 gy Site Evacuation Revision M M TABLE OF CONTENTS 1.C PU RP,0S E
2.0 REFERENCES
3.0 RESPONSI3ILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Owner Controlled Assembly Areas / Evacuation Points (1 page) 7.2 Assemo'.y Area Muster Sheet (1 page) 7.3 Site Evacuation Route (1 page) 7.4 Assembly Area Supervisor Checklist (1 page) LIST OF EFFE,CTIVE PAGES Title Revision 1 Revision 1 M,9 1-C /v~-sf I s/sJ u I"1 C.&.1 fjSlp 1
l l Emergency Plan Implementing Procedure EP-2-071 : Site Evacuation Revision I.Lf'7%3 4 1.0 PtfRPOSE This procedure provides a method with which the Emergency Coordinator can ensure that personnel are safely and expeditiously evacuated from the site area to an offsite assembly area. 2.0 RecrRCNCES Waterford 3 SES Emergency Plan 2.1 2.2 EP-2-070, Protected Area Evacuation ,s
% 1 , , , ,
2.3 EP-1-040, General Emergency Le- s 3 NUREG 0654, FEMA, REP-1, Rev. 1
~
- R, 2.4 2.5 PS-16-103, Accountability of Personnel During Emergenci,es ,
2.6 EP-2-032, Monitoring and Decontamination 2.7 EP-2-190, Personnel Accountability ' RES Roff S IBILITIES .s 3.0 , 3.1 The Emergency Coordinator is responsible for initiating this procedure.
't '
s 3 3 3.2 The Assembly Area Supervisor is responsible for implementingsthis procedure. , -s 4.0 I?lTT T ATT!!G CO NDITIO!!S , s g 4.1 Declaration of a General Emergency . t As directed by the Emergency Coordinator w+ 4.2 _ s. m .; ) s. we a e g g kk I I% , 2 .._,
Emergency Plan Implementing Procedure EP-2-071 Site Evacuation RevisionjP/sMlpI*H 5.0 PROCEDURE 5.1 The Emergency Coordinator shall direct that the appropriate alarm be sounded, at the end of which an announcement shall be made over the public address system in accordance with EP-1-040, General Emergency. 5.2 The Assembly Area Supervisor shall proceed to the Adminstration Building Assembly Area and assemble and transport the personnel in accordance with Attachment 7.4, Assembly Area Supervisor Checklist. 5.3 Personnel shall stop work and place any machinery or equipment in a safe condition. 5.4 The Emergency Coordinator shall inform Security of any hazardous (i.e., fire / smoke, radiological, toxic chemical) areas on site so that they will take adequate steps to prevent evacuating personnel from entering these areas. 5.5 Members of the emergency organization shall proceed to their J- stations and perf orm duties in accordance with the Implementing Document.
. s
, 5.6 Personnel in Radiation Controlled Areas shall proceed i= mediately to their appropriate Health Physics control points and follow normal
. Health Physics procedures for exiting.
5.6.1 Nonessential personnel shall proceed as directed via the Access Control Point and Security. 5 .,6[.2 Ess)entialpersonnelshallreporttotheirpreassignedstationsand
- carry out emergency duties in accordance with the Implementing 5
. I Document. -
N
- 5.7,. All personnel exiting the Protected Area shall do so via the Primary ib L-I Access Point (PAP), shown on Attachment 7.1, and shall drop their
.' badges / key cards and thermoluminescent dosimeters (TLD'S) into the access collection box at the PAP. They shall then proceed to their 3
~ I' '
! 3
--- , .- - , ,---,,,n - - . . - . , - - - - - - -r -
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Emergency Plan Implementing Procedure EP-2-071 Site Evacuation Revision /Al4*/
.h/f3 personal vehicles and drive to the offsite assembly area (shown on Attachment 7.3) announced over the public address system.
5.8 All personnel Within the Administration Building and. Trailer City Area shall exit via the appropriate access point, shown on At-tachment 7.1, and deposit their Personnel Accountability Disks (PAD's) into the PAD collection container. They shall then proceed to their personal vehicles and drive to the offsite assembly area (shown on Attachment 7 3) announced over the public address system. 5.9 All personnel within the Construction Area shall exit via the access point near the ESASCO Building, shown on Attachment 7.1, and deposit their PAD's into the PAD collection co.ntainer. They shall then proceed to their personal vehicles and drive to the offsite assembly area (shown on Attachment 7.3) announced over the public address system. 5 . 9 .1 EBASCO shall provide to the OSC Supervisor an Assembly Area Supervisor and an alternate for each shift. These individuals will work with the OSC Supervisor and be responsible for the evacuation of all construction personnel to the designated offsite assembly area. 5.10 Accountability shall be performed in accordance with Security l Procedure PS-16-103, Accountability of Personnel During Emergencies, and EP-2-190, Personnel Accountability. 5.11 After arrival at the offsite assembly area, the following shall be l performed: I 5.11.1 The Assembly Area Supervisor shall account for all personnel using Attachment 7.2, Assembly Area Muster Sheet. l 5.11.2 All personnel and vehicles shall be monitored for contamination ! and decontaminated in accordance with EP-2-032, Monitoring and Decontamination. l 4 l
Emergency Plan Implementing Pr.ocedure EP-2-071 Site Evacuation Revision /'A{'**f 5.11.3 Muster results shall be forwarded to the Emergency Coordinator by the Assembly Area Supervisor. 6.0 FINAL CONDITIONS This procedure shall be considered complete when muster has been completed and results forwarded to the Emergency Coordinator and the Emer.gency Coordinator disbands the mustered personnel. 7.0 ATTACHMENTS 7.1 Owner Controlled Assembly Areas / Evacuation Points 7.2 Assembly Area Muster Sheet 7.3 Site Evacuation Route 7.4 Assembly Area Supervisor Checklist 5
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ASSEMBLY AREA M'JSTER SHEET Supervisor's !!ame: Group: Date: Time: Location: Print the names of personnel in your group, that have assembled, in Section A. Print the names of those personnel not accounted for in Section B. Present completed form (s) immediately to LP&L Assembly Area Supervisor. A. B. EP-2-071 Revisionf1lOlv*y' 7 Attachment 7.2 (1 of 1) 114/ 13
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PARISilCATil0LIC ClluRCll siTg..gyACUF JN EDUTE N h g.. s. .9 attachment 7,1 (1 of n)
ASSEMBLY AREA SUPERVISOR CHECKLIST
- 1. The Assembly Area Supervisor shall proceed to the Administration Building Assembly Area and establish radio co=munications with the OSC.
- 2. The Assembly Area Supervisor shall assemble all evacuated personnel and brief thec about the offsite assembly area that is to be used.
3 The Assembly Area Supervisor shall arrange transportation for all evacuated personnel. NOTE This transportation will include both LP&L vehicles and private vehicles (see Attachment 7.4 of EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation. 4 Upon arrival at the offsite assembly area, the Assembly Area Supervisor shall muster his personnel using Attachment 7.2, Assembly Area Muster Sheet. 5 The Assembly Area Supervisor shall direct the HP technician to monitor all personnel and vehicles for contamination in accordance with EF-2-032, Monitoring and Decontamination.
- 6. The Assembly Area Supervisor shall maintain continuous communications with the OSC Supervisor until disbanded, l
l l l l EP-2-071 C l'"323 9 Attachment 7.4 (1 of 1) Revision /1l thIss
WATERFORD 3 SES PLANT OPERATING MANDAL si *
# LouislANA POWER & LIGHT
"$ONSY U
PCM VOLUME 3a Ib5I5NN 1 PCM SECTION e APPROVAL DATE: EFFECTIVE DATE: Fuel Load , DERGENCY PLAN IMPLEMENTING PROCEDURE SEARCH Ah"J RESCLT
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LP&L W-3 RECORDS
~
COhTROI .L_ ,_D COPY NO. ] PORC Meeca;;r No. 71-G 4 \ Reviewed: k
?JRC Chairman Approved: 1 A Plant Manager-Nuclear l
l l 1 l L..
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. M l'Oh Title lbwl cd Oc.!.-<.<.J Effective Date EuELtoAo (if different from approval date) Camelete 1. B. or C A. Change No. I -- B. Revision No. ' C. Deletion /d/ RFAMON FOR CHANOE. REVISION. OR DELFTION 7 k w.- Mr C~weimn t- 4 b-v-o c<A M ($Q e , vRr C .< t& Ca. ,~.. h REOUTRED STONATUREM Originator [" OdU~ Date bl ? Technical Review N Y b A Date 3 'll '8 ' O [ SAFETI EVALUATION 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 FSAR7 -
- 3. Conduct tests / experiments not described in the FSAR? #
- 4. Create a condition or conduct an operation which ex- A #
ceeds, 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 kN b Date 3 ~11'I.3 Group /Dep't. Head Review " 4 bbA Date 7- 2J-23 , 0 l Temporary Approval' Date (NOS) Temporary Approval' Date QC Review 4'4 i Cftb-l- Date 4 - # - P's PORC Reviev N Nu b M Date k-I P S 3 Meeting No. P3 - n~# PlantManage[-NuclearApprgval Nbd bwY 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 (o
Emergency Plan I=plementing ?rocedure EP-2-081 Search and Rescue Revision 1 ] TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
30 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5.1 OSC Supervisor Actions 5.2 Search and Rescue Team Leader Emergency Actions 6.0 FINAL CONDITIONS 70 ATTACHMENTS 71 First Responder Kit /First Aid Equipment Location List (1 page) (N Search and Rescue Team Emergency Actions (2 pages) 72 LIST OF EFFECTIVE PAGES Title Revision 1 "bdF 4. 5 , 7 , ? Revision 1 l-3, 6 %q; t r 1
WATERFORD 3 SES A PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST n Procedure No. e -O-d[/ Titie - Wrd d*t/ '!c'e6- - - - - - Effective Date (if different from PM-N approval date) Camolete A.- B. or C A. Change No. N/4 B. Revision No. / C. Deletion N/4
#rASON' TOR Cunnge, orVISION. OR DELETION l" h *//'A n w l tktt"w tbi///S - hy y;./--db- frehl,; ,W/py}g7~-f t'-bVW: bht r k W h is l b o ~ng M c W $ 7 y y1ih-7 -/gy;E,h - e!0 -- - -
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-f DEOUIFED SIGNATURES Originator M h -
Date I J -l's= $h - --- Technical Review --k hbi - -
- Da te - N-I NL - --
U SAFETY EVALUATION
,s Does this change, revision, or deletion: YES NO I 1. Change the facility as described in the FSAR?
L L
- 2. Change the procedures as described in the FSAR?
Conduct tests / experiments not described in the FSAR? 3. 4 Create a condition or conduct an operation which ex-ceeds, 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 S e y Evaluation checklist. Safety Evaluation O- --
~ Date N'-/-h' b --
Group /Dep't. Head Review bkbbe --- Date - / /-/ b C L '~ U l Temporary Approval *
-- -- - -- Da te -
- (NOS)
Temporary Approval * - -- -- -- -- Date - - QC Revieu - d W <-. hM- - ~ ------- Date - N *3*f E -~~-- PORC Review hbhbI Date - I-I ff -id -- Meeting No. M-v2 8
- Plant ManagehNuclear AppSval - bO2h- Date '!XIO /
' Temporary approval must be followed by Plant Manager-Nuclear approval j within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emargency Plan Implemcnting Procedure EP-2-081 Search and Rescue Revision 1 l TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5.1 OSC Supervisor Actions 5.2 Search and Rescue Team Leader Emergency Actions 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 First Responder Kit /First Aid Equipment Location List (1 page) 7,2 search and Rescue Team Emergency Actions (2 pages) LIST OF EFFECTIVE PAGES Title Revision 1 1-8 Revision 1 1 c.. ,. y y--m _ - - , -_ -, e r ,
i Emergency Plan !=plementing Proceduro EP-2-081 Search and Rescue Revision 1 1.0 PURPOSE To provide guidance to the Operational Support Center Supervisor and Search and Rescue Team Leaders for the search and rescue of person-nel who may be missing, trapped, or injured.
2.0 REFERENCES
2.1 EP-2-031, In-Plant Radiological Controls During Emergencies 2.2 EP-2-020, Contaminated Injured /Ill Personnel 2.3 EP-2-150, Emergency Records 2.4 EP-2-101, Operational. Support Center (OSC) Activation, Operation, and Deactivation eg 2.5 EP-2-032, Monitoring and Decontamination g ( 1E GP-- 2 -190, esw.W (%QM l gjg"J,, 3.0 RES PON SIBILITTES 'J The Operational Support Center (OSC) Supervisor and the Search and Rescue Team Leader are responsible for implementing the appropriate steps of this procedure. NOTE Search and Rescue Team (s) should consist of at " least a total of three volunteers from Operations, Maintenance, Health Physics, and/or Security (individuals with current first aid training should be selected, if possible). If Healtn Physics assistance is not necessary, then it is not necessary for Health Physics personnel to be on the team. i 2
Emergency Plan Implementing Procedure EP-2-081 Search and Rescue Revision 1 1 1 4.0 INITIATING C0"DITIO95 4.1 This procedure shall be implemented when: l 4.1.1 Individual (s) has (have) not been accounted for as directed by the w -
^"" '
[L l Security procedurP;n,-las u st-2-190 PxM kJW.or accountaoility curing a site or Ge~n9Y Emergency and cannot be contacted. 4.1.2 Individual (s) is (are) unable to exit an area without assistance.
- .. 4.1 3 . Directed by.the. Emergency Coordinator.or.oSC. Supervisor. __
5.0 nocerDunE 5.1 OSC SUPERVISOR ACTIONS 5.1.1 Select three or more volunteers as required. Assign one individual as team leader. 5.1.2 Ensure team is briefed in accordance with this procedure, prior to departure from OSC; fill in applicable portions of Attachment 7 3 of EP-2-101, and make it available to the team leader. Also, ensure team is briefed on radiological hazards in accordance with EP-2-031, In-Plant Radiological Controls During Emergencies. 5.1.3 Record team member names, duties, and departure and return times l in the OSC Facility log. 7W "-~ o W" 44@ v.,, m s ,-u sM 69 ~ 2. -l s c . . ?s M W OQ 5.1.4 Notify the Emergency Coordinator when the team has been M,vlv4/
/
dispatched. 5.1.5 If persons are injured and contaminated or if offsite medical assistance is requested, refer to EP-2-020, Contaminated Injured /Ill Personnel. 5.1.6 Provide assistance to team as necessary. 5.1.7 After search and rescue is complete, ensure team members are l
- debriefed in accordance with Attachment 7 4 of EP-2-101. Inform
\
l the TSC of the results of search and rescue operations. 3
Emargancy Plan Impismanting Procsdure EP-2-081 Search and Rescue Revision 1 5.2 SEARCH AND RESCUE TEAM LEADER EMERFENCY ACTIONS 5.2.1 Obtain completed Attachment 7.3 of EP-2-101 from OSC Supervisor, and brief team members on search and rescue task. Discuss with the Radiological Controls Coordinator any radiological hazards that are present in the affected areas. 5.2.2 Designate a team member as communicator and direct him/her to obtain communications equipment.
.. .5.2.3. . Direct .a team . member ..to. obtain any . safe.ty. equipmenth t at may. be ---- --
required. 5.2.4 Direct a team member to be responsible for obtaining first aid equipment from one'of the locations on Attachment 7.1. 5.2.5 Ensure that all equipment to be used by the team is functional. Perform a radio check between Search and Rescue Team and OSC. 5.2.6 Ensure OSC Supervisor logs team members out of OSC. Ensure dose rate meters are turned on before team leaves OSC. 5.2.7 Conduct search and rescue operations by completing those actions listed on Attachment 7.2. 5.2.8 After search and rescue is complete, debrief the Search and Rescue j Team in accordance with Attachment 7.4 of EP-2-101. 5.2.9 After debriefing, 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 Records. , 5.2.10 Inform OSC Supervisor that the team is secured and stand by for further instructions. The OSC Supervisor shall direct the OSC Communicator to inform the TSC of the results of the search E.nd rescue task. 4 t
Emsrgency Plan Impicmanting Procedure EP-2-081 Search and Rescue Revision 1 6.0 FINAL CONDITIONS 6.1 Missing individual (s) located and removed from ha:ardous area, and necessary first aid administered. 6.2 Secured when directed by the Emergency Coordinator. 7.0 ATTACHMENTS 7.1 First Responder Kit /First Aid Equipment Location List 7.2 Search.and Rescue Team Emergency Actions 5
FIRST RESPONDER KIT /FIRST AID EQUIPMElT LOCATICN LIST
- 1. First Responder Kits ' -,
A. M Fi .- a v A.u: An. . .a,,----img r---k i t- =.-P 414-E +- 3 ,l m 'A W.C e to2 b _q -_ 1 - ~ - - - = - - - _ , , , , u,,.__., o 1- Centrol Mnn- (TSG W Ai D ~T'". ' ' 4 '~ DP-- M::1- ~, -_--- A --la. - Security Administratiendr~ea:1-t bg.' ~ tw3t~.. E, kie ' u.wu- " . . . b4Up-aut-iting-EOF ii=6: kit G ___ Maintenance-Service SP11 ding 1tSC) - ki t - Fr.c. Ev"es-y "-
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L ^'v. EP-2-081 Revision 1 6 Attachment 7 1 (1 of 1)
SEARCH AND RESCUE TEAM EMERGENCY ACTIONS
- 1. Proceed to designated area (s) with radiation survey meter turned on. Use radiological controls precautions.
NOTE If radiological hazards are not present, Health Physics personnel do not have to accompany the team.
- 2. Ensure that communications are maintained with the Operational Support Center at predetermined intervals.
3 Ensure that the Operational Support Center is kept informed of team's location, observations, and survey results.
- 4. If radiological hazards exist, ensure that:
(a) The Health Physics Technician monitors radiation levels and that any unanticipated radiation levels are reported to the Operations Support Center Supervisor. (b) Team members check dosimeters regularly. (c) Dose limits specified in 10CFR20 are not exceeded without the Emergency Coordinator's permission (see EP-2-032). (d) Stay times established by the Radiological Controls Coordinator are not exceeded. 5 When an individual is located, check the persrn for injuries and I contamination. Administer first aid, as necessary. l l
- 6. Report the following findings to the Operational Support Center as soon as possible:
(a) Location (b) Extent of injuries (c) Contamination levels l (d) First aid administered EP-2-081 Revision 1 7 Attachment 7 2 ( lof 2) I l L
. SEARCH AND RESCUE TEAM EMERGENCX ACTIONS 7 Request assistance from the Operational Support Center Supervisor for transport of any injured or contaminated individuals.
- 8. If offsite medical personnel arrive at scene, inform them of known injuries and contamination levels. Aid the offsite medical person-nel, as requested.
9 Upon completion of search and rescue operations, report to the Operational Support Center for debriefing. < EP-2-081 Revision 1 8 Attachment 7.2 (QLof 2) i
WATERFORD 3 SES PLANT OPERATING MANDAL LOUISIANA MICDLE SOUTH UtuT;ES SYSTEM
~
POM VOLUME 18 ISION 1 ION 2 APPROVAL DATE: EFFECTIVE DATE: EMERGENCY PLAN IMPLEMENTING PROCEDURE ACCIDENT ASSESSMENT ' LP&L W-3 RECORDS CONTROLLED COPY NO. Ob PORC Meeting No. 7.iL C 2 d i Reviewed: l . .[ ' ORC Chairman Approve'd: ]\1 ) OlA Plant Manager-Nuclear
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1 WATERFORD 3 SES
*N PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. O ~6 & Title - ' t i!bd -/ < w=rw-et - -- -
Effective Date __ (if different from PM-N approval date) Ce melete 1. B. o r- C A. Change No. dd B. Revision No. / C. Deletion a/4
'4E ASON FOR CM-A MG E . REVISION. OR DELETION
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REOUTRED SIGNATURES Originator M Mz* Web - Date /> - /#i ~ 2 * ---- Technical Rev[ew -S' bb - -
-- Date ~l M - D - --
o' J SAFETY EVALUATION
,. Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR?
h
- 2. Change the procedures as described in the FSAR? M
- 3. Conduct tests / experiments not described in the FSAR?
L-
- 4. Create a condition or conduct an operation which ex- L" ceeds, 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 Saf y Evaluation checklist. Safety Evaluation d - -- - Date - l N 9-3 ' -- Group /Dep't. HeadRevhew bbb --- Date N -l TP '- V I Temporary Approval * -----Date- - (NOS) Temporary Approval * --- Date - - QC Revieu -JW Yb-10uH * - - - - - - Da te - - l^~ / J -- E S * *- PORC Review k Y b b Date / -) 'l-Il- - Meeting No. h-t# --Y PlantManagerhNuclearApprpval l Y s dhh.t5 E- Date OhIh-
' Temporary approval must be folicwed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 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 I 7.1 Plant Status Checklist (2 pages) 7.2 Containment Radiation Plots (1 page) 7.3 Containment Radiation Plots General Guidelines - Containment Radiation Plots Table (2 pages) LIST OF EFFECTIVE PAGES Title Revision 1 1-12 Revision 1 1
f Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 1.0 PURPOSE 1.1 This procedure describes necessary actions to be taken by the technical and engineering emergency response personnel following a major off-normal event at Waterford 3 involving the reactor systems. 1.2 This procedure provides a Plant Status Checklist to assist in the coordination of the shift in responsibilities from the Control Room to the Technical Support Center. 1.3 This procedure provides guidelines for the-use of the Emergency Plan Containment Radiation Plots.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.3 Waterford 3 SES Final Safety Analysis Report 30 RESPONSIBILITIES 3.1 The Technical Support Center (TSC) Supervisor shall be responsible for the implementation of this procedure under the Emergency Coordinator. 3.2 The TSC Lead Engineer shall provide recommendations on technical assessment to the TSC Supervisor. 33 The Technical Support Center Engineers shall provide recommendations to the TSC Lead Engineer involving problems affecting plant safety or operation during an emergency, including all areas related to design and operation of Waterford 3 which pertain to mechanical, electrical, fluid systems, reactor physics, chemistry and metallurgy evaluations. l l l 2
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 4.0 INITIATING CONDITIONS 4.1 Any of the following emergencies has been declared: Alert, Site 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. 4.2 As determined by the TSC Supervisor or the Emergency Coordinator. 5.0 PROCEDURE 5.1 At the direction of the TSC Supervisor, the TSC Lead Engineer will supervise the technical and engineering response personnel and establish an operations / engineering assessment group in the TSC Technical Assessment Area. This assessment group should: 5.1.1 Determine overall plant status and the extent of the particular problems, including: 5.1.1.1 Primary Plant condition 5.1.1.2 Secondary Plant condition 5.1.1.3 Equipment operability 5.1.1.4 Instrumentation operability 5.1.1.5 operations staff diagnosis of off-normal conditions 5.1.1.6 Degradations in the interactions between components, systems and safety trains and/or functions 3
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 NOTE A Plant Status Checklist is provided as Attachment 7 1 to assist in the initial transfer of information between the Control Room and the Technical Support Center. If not previously accomplished, request that the Control Room fill out this checklist and provide the information to the TSC.via sound-powered phone. 5.1.2 Evaluate the condition of the reactor, essential safety-related systems, and any significant problem areas identified in step 5.1.1 above, using, as necessary: 5.1.2.1 Piping and Instrumentation Diagrams, including pipfng system isometrics, general arrangement drawings and electrical schematics 5.1.2.2 Applicable plant operating and/or maintenance procedures 5.1.2 3 Parameters as given through the Safety Parameter Display System (SPDS), computer printouts or trend recorders 5.1.2.4 The '43 SES Final Safety Analysis Report 5.1.2.5 Applicable equipment technica manuals 4
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 NOTE 1 Applicable d'awings, r manuals and procedures can be obtained from the Records Storage Area within the Technical Support Center. NOTE 2 If additional information from the Control Room is required, access to the Control Room should be gained through a request to the TSC Supervisor and performed in accordance with Control Room access provisions. General access to the Control Room is restricted at all times. 5.1.3 Assist the Control Room staff by relieving the reactor operators of peripheral duties such as: 5.1.3.1 Plotting cooldown curves, radiation levels or other key parameters to back up or assist in trend analysis 5.1.3.2 Verifying and logging instrument indications where continuous technical assessment and monitoring are required to provide notice when degradation is or may be occurring 5.1 3.3 Evaluating the perfunctory adequacy of natural circulation flow or heat sink efficiency. 5.1.4 Design and coordinate the installation of short-term instrument and control modifications, including preparation of the respective installation or abnormal operating procedures necessary to support the evolution. 5
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 5.1.5 Inform the TSC Supervisor of engineering related areas where support from the Emergency Operations Facility's engineering staff is necessary, such as for: . 5.1.5.1 Supplemental transient or accident analysis, which may include event tree analyses or computer calculations necessary to provide particular event possibilities that could occur and which should be preparatorily considered 5.1.5.2 Engineering development of system modifications necessary to ensure the immediate safe shutdown of the reactor and any system additions necessary to maintain long-term shutdown capabilities. 5.1.6 Inform the TSC Supervisor of equipment conditions that indicate the necessity to establish and dispatch an Emergency Repair / Operations Team from the Operational Support Center to ef-fect necessary damage control measures within the plant. 5.1.7 Provide recommendations or data to the TSC Superviser as necessary to assure that the protection of station personnel and the public can be maintained. 5.2 Analyses of plant conditions should be performed to determine l reactor core status, including the estimated source term of a potential release of radioactive material from within containment. Determination of the approximate source and damage estimate can be as follows: 5.2.1 Use the Containment Radiation Plots, Attachments 7.2 and 7.3, in the following manner: 5.2.1.1 Determine the time since the reactor shut down. 5.2.1.2 Determine the containment radiation monitoring reading. 5.2.1.3 Locate the radiation reading (from step 5.2.1.2 above) on the graph of the plots (Attachment 7 2) at the appropriate time coordinate (from step 5.2.1.1 above). 6 vp7 T -w-e' uss g3-- w-y.ry- - -us- y- -- y- %-e.--%y e m e .a., , a ,.m-.-pp-y.
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, ' - . 3, 5.2.2 Inform the TSC Lead Engineer of the determined value for the x ,
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-4 5.2.1, including any modifications to, or assumpti.ons in, th'e I 3,
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p - EP-2-090 . Revision 0 8 Attachment 7.1 ( / o f 'l)
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CONTAINMENT RADIATION PLOTS GENERAL GUIDELINES Theoretical curves of gross gamma dose rate versus time are given for the range of potential source terms in Attachment 7.2. The curves represent direct readings for the containment monitors located inside the containment. The calculation of monitor response did not include any particulates or iodine since the noble gases are the most significant cor.tributors to dose rate in the containment. At the worst, neglecting the particulates adds a slight amount of conservatism since the actual presence of particulates would result in a higher monitor reading. NOTES
- 1. The curves account for the finite containment volume seen by the detector but do not account for any monitor physical or shielding characteristics or calibration uncertainties.
- 2. The curves assume that only airborne noble gases are significant. Sprays (if used) would make the iodine and any particulate contribution insignificant. However, particulate plateout on surfaces and direct shine doses from components may make the readings unreliable.
3 Curve uncertainties are on the order of a factor of 2 to 5. ( , I EP-2-090 Revision 0 11 Attachment 7.3 ( / o f .A)
CONTAINMENT RADIATION PLOTS CONTAINMENT RADIATION PLOTS TABLE Percent of Fuel Inventory Airborne in the Containment vs. Approximate Source and Damage Estimate
% Fuel Case Inventory
- Hg. Released Aeoroximate Source and Damare Estimatg 1 100 100%: Regulatory Guide 1.4, 100% Fuel Damage, potential core melt 2 10 10%: Regulatory Guide 1.4 (or 100% NRC Gap i Activity, Regulatory Guide 1.25), total clad failures, core partially uncovered 3 1 1%: Regulatory Guide 1.4 (or 10% NRC Gap Activity), approximately 105 clad failure 4 -
100% coolant release
- 100% Fuel Inventory = 100% Noble Gas EP-2-090 Revision 0 12 Attachment 7 3 ( J1of o2 )
= .
WATERFORD 3 SES _ PLANT OPERATING MANGAL LOUISIANA POWER & LIGHT UNE:NSY *- EP-2-091 O PCM VOLUME IR REVISION POM SECTION ' APPROVAL DATE: May 2, 1983 EETTCTIVE DATE: " *" """ O!ERGENCY PLAN IMPLEMENTING PROCEDURE , EMERGENCY' CHEMISTRY l LP&L W-3 RF.CC: 15 CONTRO;ii- . COPY NO. O FORC Meeting No 73 -/ ~) 4 Reviewed: ~; f ~~
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/PORC Cha r-nan App roved: J31 /ST -
Plant Manager-
. Nuclear l
i - - - - - _. - -- . _ _ _ _ _ _ . _ _ ._ _
, WATERFORD 3 SES PLANT OPERATING MANUAL REVIEW COVER SHEET !
PROCEDURE NO. 8 8- 2 -d 7 / TYPg EMEdd; d~/t/% N/- h*/A)G : TITLE 8"#"#de y C//9Fl'5 7 PROCEDURE EFFECTIVE DATE NEl 4246 (If differ t from PM-N approval ~ AUTHOR O / b /4- / ~ TECHNICAL REVIEW [ [M# vi
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ur M -/bD Signature, Technical Reviewer Date PORC REVIEW REQUIRED TES / NO ._ SAFETT EVALUATION Does this procedure:
- 1. Change the facility as described in the FSAR7 YES NO._.
- 2. Change the procedures as described in the FSAR7 TES No _7-
- 3. Conduct tests / experiments not described in the TES NOE
.4H7 . .
- 4. Create a condition or conduct an operation TES NO_
which exceeds, or could result in exceeding, - the limits in Technical Specifications? If any question 1 through 4 has been answered TES, complete and at-tach a 10 CFR 50.59 SAFETT EV UAT ON. SAFETY EVALUATION " ^ d' ~
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Signature,TecgioelReviewer te GROUP / DEPARTMENT HEAD REVIEW kEM h bG dtlf - Nignakure Date QC REVIEW A'A [N6 M ^ A N1
- el' ude%/ignatugQCEngineer Da e f -
PORC REVIEW W/<G [ Signature,PORCChairman 'Date PORC MEETING NO. @-W UNT-1-003 Revision 5 30 Attachment 6.5 (1 of 1)
I Emergency Plan Implementing Procedure EP-2-091 __ Emergency Chemistry Revision 0 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 Post Accident Sampling and Analysis Procedures (LATER) LIST OF EFFECTIVE PAGES . Title Revision 0 1-5 Revision 0 E 1
r - Emergency Plan Implementing Procedure EP-2-091 __ Emergency' Chemistry Revision 0 1.0 PURPOSE 1.1 This procedure describes actions to be taken by the Chemistry . Engineer, Radiochemist, Radiochemistry Supervisor and Chemistry Technicians following a major off-normal event at Waterford 3 wnich requires chemistry considerations as part of the emergency response effort. 1.2 This procedure integrates the emergency Chemistry operating procedures into the overall emergency response efforts to arrive at a unified approach to accident management.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan
~
2.2 LP&L Procedures 2.2.1 CE-3-900, Operation of Post Accident Sampling System, Draft 2.2.2 CE-3-901, Post Accident Sampling of Containment Atmosphere, Draft 2.2.3 CE-3-902, Post Accident Boron Analysis, Rev. 0 2.2.4 CE-3-903, Post Accident Gamma Spectroscopic Analysis, Rev. 0 . 2.2.5 CE-3-904, Post Accident Analysis of Dissolved Hydrogen in the Reactor Coolant, Rev. 0 2.2.6 EP-2-150, Emergency Records, Rev. 1 2.2.7 EP-2-031, In-Plant Radiological Controls During Emergencie's, Rev. 1 2.3 NUREG 0737 - II.B.3 30 RESPONSIBILITIES 3.1 The Chemistry' Engineer shall have responsibility for implementing and maintaining this procedure. 2
Emergency Plan Implementing Procedure EP-2-091 __ Emergency Chemistry Revision 0 3.2 The Chemistry Engineer or his alternate, the Radiochemist, reports to the TSC and takes direction from the TSC Supervisor during emergency situations in which the TSC is activated. 33 The Chemistry Supervisor will be in charge of, and be located in, the RAB Laboratory or the Emergency Laboratory during emergency chemistry operations. This individual will provice direction anc - control of the Chemistry Technicians in performance of their tasks. 3.4 The Radiochemist or Radiochemistry Supervisor, in consultation with the HP Coordinator, will determine if the hAB Laboratory will be evacuated. 3.5 The Chemistry Engineer or the Radiochemist, after consultation with the HP Coordinator, will determine if'the Normal Primary Sample Panel can be used instead of the Post Accident Sampling System" (PASS) Panel. ;. 4.0 INITIATING CONDITIONS 4.1 Any of the following emergencies has been declared: ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY; or an event has occurred that dictates the necessity to implement emergency Chemistry procedures. . 4.2 As determined by the TSC Supervisor or the Emergency Coordinator. 5.0 PROCEDURE 5.1 At the declaration of an ALERT, SITE AREA EMERGENCY or GENERAL
~
EMERGENCY that results in Containment isolation, or when utilization of the Normal Primary Sample Panel cannot be made within ALARA Guidelines, the PASS procedures, Reference 2.2.1, will be in effect until determined otherwise per step 3.5 above. 3
I Emergency Plan Implementing Procedure EP-2-091 __ Emergency Chemistry Revision 0 NOTE If preliminary results show that the Normal - Primary Sample Panel can be utilized within ALARA guidelines, the Chemistry Engineer or the Radiochemist can transfer the sample function from the PASS panel to this system. This cetermination would ordinarily be made based upon the first set of samples. 5.2 At the direction of the TSC Supervisor, the Chemistry Engineer , should establish the level of involvement of the Chemistry Staff in support of the response actions underway and ensure adequate Chemistry personnel are available to support anticipated actio'ns. At a minimum, adequate personnel must be available to operate the Post Accident Sampling System (PASS) equipment, and to produce the data defined by NUREG 0737 II.B.3 within the prescribed time limits. 5.3 The Chemistry Engineer should maintain an awareness, through the TSC Supervisor, of the emergency situation as it progresses and provide information pertaining to the current chemical status of primary and . secondary water, and of Containment air, as required by the TSC Supervisor. 5.4 The Chemistry Engineer should ensure that all actions taken in conducting analyser or carrying out actions delineated in Post Ac-cident Sampling Procedures are accomplished in accordance with EP-2-031 of this document, and should ensure that such actions are undertaken only after receiving direction and approval from the TSC Supervisor or the Emergency Coordinator. 5.5 All data collected from chemical analyses conducted in support of the emergency response should be reviewed and verified by the Radiochemistry Supervisor, the Radicchemist and the Chemistry Engineer and forwarded to the TSC Supervisor except as described in step 5.5.1. 4
Emergency Plan Implementing Procedure EP-2-091 __ Emergency Chemistry Revision 0 5 . 5 .1 Initial' Chemistry results obtained before the TSC is activated will be conveyed to the Control Rcom by the Radiochemistry Supervisor or the Chemistry Technician in consultation with the - Radiochemistry Supervisor or the Radiochemist. - 5.5.2 Logs of actions taken, analytical results, and recommendations msde should be kept in accordance with the requirements of EP-2-150 of this document and with Chemistry procedure requirements. 6.0 FINAL CONDITIONS 6.1 Abnormal plant conditions have been terminated or de-escalated below . the ALERT level classification, and 6.2 Chemistry analyses and actions have been completed or transferred to the Recovery Organization, or , 6.3 The Technical Support Center is deactivated per EP-2-100. 7.0 ATTACHMENTS 7.1 Post Accident Sampling and Analysis Procedures (LATER) O e h 5
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i PCM VOLQ'.E 1A NsNO 2 Ma'y 2, 1983 PCM SECTION 2 APPROVAL DATI: EFFECTIVE DATE: e. . i r -. a l EMERGENCY PLAN IMPLEMENTING PROCEDURE TECHNICAL SUPPORT CENTER (TSC) ACTIVATION, OPERATION, AMD DEACTIVATION L?&L W-3 RZ' 'G Obq.,,ap!';,'.x I g i 3 :;- w t , i . ,, ,- . .. w %.) fh,j 3 s NO. O
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'L f N Approved: J', 9__ %
Plant Manager-
. Nuclear 9
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WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST l Procedure No. CP-1~ Ich Title ~rM W % (~ts4 M i l Effective Date EOFL Lo AC (if different from approval date) Cemelete A. B. or C Or u & . A. Change No. W M -
- 3. Revision No.?d # 1 C. Deletion *l' M 9EiMON FOR CHANCE. REVISTON. OR DET.ETION
~To 9- % am uu 'm w m1 w ,,uTA %
JRC C 1Dem & REQUTRED STCMATURES Originator Oe N Date 3ftifM Technical Review V N bn h Date 3 ' 4 4 '3 0 . SAFETT EVALUATION Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR? #
- 2. Change the procedures as described in the FSAR7 V
- 3. Conduct tests / experiments not described in the FSAR7
- 4. Create a condition or conduct an operation which ex-ceeds, 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 b b bA Date 3'2J -S3 Group /Dep't.HeadRevYew % Date 7-21 -ts3 a a Temporary Approvale Date (NOS) Temporary Approval
- Date
~
QC Review J - WA Ol'l'l Y u Date M- A P M - PORC Review I I o u b - Date #/IM Meeting No. Plant MarprgerINuclear Approval MM Y Date Mh *
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) 26
r-Emsrgsney Plan Impicmsnting Procsdure EP-2-100
~~
Technical Support Center (TSC) Activation, Revision 2 Operation, and Deactivation TABLE OF CONTENTS . 1.0 PURPOSE
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5.1 Activation 5.2 Operation - 5.3 Deactivation
' ~
6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 TSC Floor Plan and Equipment Locations (1 page) 7.2 TSC Deficiency Log (2 pages) 7.3 Support Emergency Response Organization (3 pages) LIST OF EFFECTIVE PAGES . Title Revision 2 i 1-12 Revision 2 l l
+
1
Emergency Plan Implementing Procsduro EP-2-100 Technical Support Center (TSC) Activation, Revision 2 Operation, and Deactivation 1.0 PURPOSE . This procedure provides guidance for the Technical Support Center (TSC) staff in the activation, operation and deactivation of the Technical Support Center.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-010, Notifications and Communications 2.3 EP-2-050, Offsite Dose Assessment (Manual) -
~
2.4 EP-2-051, Offsite Dose Assessment (Computerized) 2.5 EP-2-150, Emergency Records , 2.6 EP-2-090, Accident Assessment 2.7 EP-2-190, Personnel Accountability 3.0 RESPONSIBILITIES The Technical Support Center Supervisor is responsible for ensuring - that actions outlined in this procedure are completed, as appropriate. 4.0 INITIATING CONDITIONS
~
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 (optional) 4.2.2 Alert 4.2.3 Site Area Emergency 2
1 1 l 4
. Emergency Plan Impl(msnting Procsduro EP-2-100
~~
Technical Support Center (TSC) Activation, Revision 2 Operation, and Deactivation l 4.2.4 General Emergency , 5.0 PROCEDURE 5.1 ACTIVATION 5.1.1 Energire/make ready emergency equipment in the Technical Support Center (TSC) shown on Attachment 7.1, TSC Floor Plan and Equipment Locations, as appropriate. Conduct initial personnel ac-countability, if appropriate, in accordance with EP-2-190, Person-nel Accountability. 5.1.2 Make an assessment of TSC staff available in the TSC and inform the Emergency Coordinator that the TSC is prepared to assume TSC responsibilities. NOTE Some circumstances dictate that personnel may arrive at the TSC before the TSC Supervisor or Emergency Coordinator. In these situations, the Nuclear Operations Supervisor-Shift Supervisor (NOS-SS) may - begin shifting some responsibilities to personnel in l the TSC prior to the arrival of the TSC Supervisor or ! Emergency Coordinator. 5.1.3 At the direction of the Emergency Coordinator, transfer TSC responsibilities frcm the on-shift staff to the TSC staff. 5.1.4 As conditions permit, shift communicatiens from the Control Room to the TSC in accordance with EP-2-010, Attachment 7.11. 5.1.5 After shifting TSC responsibilities to the TSC, inform the Emergency Coordinator that the TSC has been activated. I l 3 l
1 Emergency Plan Implementing Procsdure EP-2-100 Technical Support Center (TSC) Activation, Revision 2 -- Operation, and Deactivation 5.1.6 When TSC is activated and the NOS-SS has been relieved as the Emergency Coordinator, ensure that the following announcement is made over the plant PA system. ATTENTION ALL PERSONNEL! ATTENTION ALL PERSONNEL! THE TSC HAS BEEN ACTIVATED. THE SHIFT SUPERVISOR HAS EEEN RELIEVED AS THE EMERGENCY C00RDINAT-OR BY __ Name THE TSC IS NOW PERFORMING DOSE ASSESSMENT AND COMMUNICATING WITH OFF-SITE AGENCIES. . 5.2 OPERATION NOTE 1 - The responsibilities that may be transferred to the EOF Director by the TSC Emergency Coord-inator are:
- 1. Request for assistance from off-site agencies
- 2. Protective action recommendations to off-site agencies l
[ NOTE 2
~
l The responsibilities that remain with the TSC ( Emergency Coordinator and will not be transferred to the EOF Director are:
- 1. Classification and declaration of an emergency
- 2. Authorization of radiation exposure in excess of 10CFR 20 limits 5.2.1 Ensure TCS Communicators conduct communications in accordance with EP-2-010.
4
Emergency Plan Implemsnting Procsdure EP-2-100 Technical Support Center (TSC) Activation, Revision 2 Operation, and Deactivation 5.2.2 Periodically check with the' Health Physics Coordinator to ensure - all TSC dose assessment equipment is operational. 5.2.3 Obtain engineering support personnel from the Operational Support Center (OSC), if necessary, to staff the technical assessment area of the TSC. Verify that ISC Lead Engineer has initiated the coordination efforts of the TSC Engineers to ensure an assessment of reactor and plant-related system conditions by ensuring EP-2-090, Accident Assessment, is implemented. 5.2.4 Ensure TSC personnel maintain records in accordance with EP-2-150. -
^
5.2.5 When the EOF is fully activated and can perform dose assessment, off-site communications and off-site protective action recom" - mendations, the Emergency Coordinator shall transfer theca T responsibilities to the EOF Director. 5.2.5.1 The shift of communications from the TSC to the Emergency
\
Operations Facility (EOF) shall be in accordance with EP-2-010, 4 Attachment 7.12.
~
5.2.6 If extended operation of the TSC is required, provide continuous manning capability. 5.2.7 Maintain continuous personnel accountability in accordance with EP-2-190, Personnel Accountability.
~
i 5.3 DEACTIVATION 5.3.1 When informed by the Emergency Coordinator to deactivate the TSC, l ^ make preparations with the NOS-SS to transfer remaining responsibilities to the on-shift organization. l 5.3.2 After shifting responsibilities, inform the NOS-SS that the TSC has been deactivated. i 5 i
Emsrgoney Plan Implcmsnting Procsdure EP-2-100 Technical Support Center _(TSC) Activation, Revision 2 Operation, and Deactivation 5.3.3 Deenergize and restore emergency equipment shown on Attachment 7.1, TSC Floor Plan and Equipment Locations, to preactivation conditions. 5.3.4 Complete Attachment 7.2, TSC Deficiency Log. 6.0 FINAI CONDITI0flS 6.1 Asse;s the status of the TSC and ensure the following actions have been completed: 6.1.1 All records generated during the operation of the TSC have been . handled in accordance with EP-2-150. 6.1.2 All. functional equipment / supplies have been restored to . preactivation conditions, as appropriate, and Attac'hment 7.2 has been completed and forwarded to the Emergency Planning 4 Coordinator. 6.1.3 The' entire TSC staff has been relieved of all duties associated with the operation of the TSC. 7.0 ATTACMMENTS . 7.1 TSC Floor Plan and Equipment Locations 7.2 TSC Deficiency Log i 7.3 Support Emergency Response Organization . L i i 6 i L
. TSC FLOOR PLAN AND EQUIPMENT LOCATIONS
- 1 I
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.j l -. .- i EP-2-100RevisionJ- f Attachment 7.1 (1 of 1)
TSC DEFICIENCY LOG _ A. SUPPLIES: Deoleted Kit- Tn ke n From/Lecation 1. 2. 3. 4 5. 6. 7. B. MALFUNCTIONING EQUIPMENT: - . Ecuirment Affected Nature of- Malfunction L o' cati on , ,i 1. 2. 3. 4 5. 6. 7. 8. 9. 10. t EP-2-100 Revision 1 8 Attachment 7.2 ( / of 2) i
.TSC DEFICIENCY LOG' C. . IMPLEMENTING PROCEDURES:
Procedure- Number Problem- Area l 1. 2. 3. 4 4 t 4
. 1 i
I l l
- l l EP-2-100 Revision 1 9 Attachment 7 2 (/.,of 2) l
r SUPPORT EMERGENCY RESPONSE ORGANIZATION i NE AR-SIT E EMERGEMCY OPERATIONS FACILITY ORGANIZATION i
~~~~~~
LOOMEEPER ADV SOR DIRECTOR l I
' ' ' ' OPERATIONS LICENSING COMMUNICATIONS ASSESSMENT RELATION LOGISTICS ADYlSOR -
COOROINATOR COORDINATOR COORDINATOR CCC TECimtCAL ADVISOR - ST. CHARLES EOC TECHNICAL i ADVISOR - i FIELD DOSE COMMUNICA10R STATUS BOARD NGMEERiple TECHNICAL RECOROER/ COMMUNICAT OR N COORDINATOR COORD N ATOM COOftDINA ADVISOR -
. OFF -SITE CORPORATE COMMANO CENTER ORGANIZATION EMERGENCY DIRECTOR s ,
e ADM1NtSTRATIVE / OOYERNMENT / LPSL INF9RMATION SUPPOftT TREASURY AND ACCOUNTING LO0tSTICS PUBLIC AFFAIRS CENTER ENGINEEftlNG MANAGER MANAGEft MANAGEft MANAGER MANAGER SECUftlTY EM REEEY COOROINATOR S AF EP-2-100 Revinf ori 2 10 At tacheit t 7.3 (1 M 3) I .h . - - .
g . i EMERGEt.'C TEAM / GROUP ORGANIZATION a TSC TECitNICAL RESFON E ASSESSMENT MANPOWER POUL OROUP 60 MEMBERS ISC ELECTRICAL HEALTH FttYSICS SEARCH AND ftESCUE M AIN TEN ANCE fM-PLANT, ON-Stit, MANPOWER POOL - S MEMBERS OFF-SITE TEAM AS NEEDED . MECHANICAL MONITORING ; ENGINEERS II #EU8ER8 FIRE BRIGADE RAINTENANCE R 00L AS NEEDED S MEMBERS TS TRAINED CHEMICAL , ENGINEERS SC FIRST AIO MANPOWER POOL
, MAINTENANCE AS NEEDED 8 MEMBERS 54 TRAINED NUCLEAN EN0tNEERS COMPUTER SUPPLY / LOGISTICS MAlHTENANCE TEAM e McMsERS 2 MEMBERS ELECT RICAL ENotNEERS RAD / CHEMISTRY RADWASTE HELPERS H WEunERS s MEMeERs COMPUTER ENGINEERS ST(S e MEMeERS
[ RADWASTE ENGINEEft1 El' 100 " " inion 2 11 Attachment 7.3 (2 of 3)
$ hb,W-lbb h W & ff5h kk $$$' M $ 'NW, l , .. , . * ' ' .
. ~ .
l s ON -SITE EMERGENCY RESPONSE ORGANIZATION , TSC E MER9ENCY LOOKEEPER ADYlSOR COORDINATOR 7 ffEALTH PHY SICS TSC LEAD TSC SECURITV OPERATIONS COORDINATOR COMMUNICATOR SUPERVISOR SUPERVISOR COORDINATOR 1 TSC SECURITY COMMUNICATUft SillPT SUPV.
#I RUTRTMS SIFTS i DOSE RADIOLOGICAL TSC TSC OPERATIONS OPS DEPT.
OSC ASSESSMENT CONTROLS LEAD SUPV. C00mlulHCATOR NOS-SS ON-SMIFT SUPERVISOR COMg T RAINING, RE LIEF COORDINATOR CO3RDINATOR ENGINEER TSC COMMUNICATOR ,
*E l l l IN-PtJLMT IIP TSC TECitPCAL EMERGENCY OSC AIIE"8lY OSC ROTATING ASSESSMENT RESPONSE LOOMEEPER (XMMUNICAT0fl AEA SlitPTS OnOUP TEAMS SUPERvl80R e
s Or r-SITE ON -SITE
- LOOKEEPER MONITORING MONITORING ROTATN09erTS RUTRTP80 StePTS LOGISTICS SEARCH
! ELECTRICAL MECHANICAL Inc FiftST FRE COMPU1ER REmIR REf%fR REPAIR AlD BRIGA0E REPAIR SUPPORT g EP-2-LOO Revision 2 12 Attachment 7.3 (3 of 3) ,
4
t , a
' 4. , 9 l
y s. : WATERFORD 3 SES . PLANT OPERATING MANG L N '
= i c .
R LOUISIANA 1 POWER & LIGHT MICCLE SCUTH ' UT1UT.ES SYSTEM 3 EP-2-101 2 PCM VOLT;ME IEVISICN , PCM SECTICN - AF?x0 VAL DATE: Mav 2, 19 8 E87ECTIVE DATE: Fuel Load . 6 .
.s.
t DfERGENCY PLAN IMPLEMENTING PROCEDURE . OPERATIONAL SUPPCRT CENTER (OSC) ACTIVATION, ' OPERATION, AND DEACTIVATION LP&L W-0 ' e. s = '
% j ~$ p -i'S.e
- A ..
C."g'~'~g no. Ch)Q .
,1 PCRC Meeting No. f 3-s 74 Raviewed: ,, he/e.8 % -
ORC' Ch$,1rman \ ' . App roved :s. - Plant Manager-l . Nuclear s L b
4
' 7
. i s h . s WATERFORD 3 SES [' PLJNT OPERATING MANUAL i
, CHANGE / REVISION / DELETION REQUEST
~ ' Procedure No. G P W D Title d'WTIML 5%%RT ccW7Cn(Osc\ Ac7sM7og CPGotTist
~ Effective Date' (if different frca approval date) M 06AC78W'7'M Gy . -
3 j camel te 1. n; er4lc
/- A. Change No. 'M.
Y B. Revision No 4 M i C. Deletion N x RFAMOM FOR cMANCE. REVISTOM. OR DFLFTTOM __ fA n_: _
; *- A- __M a -J % w d u kRC rw i e N3 ~ .,_ _ _ . _
REQUTRED SICMATU Originator M/ M Date 8 O b Date I- 38 T 3 Technical Rev(ew [9Y bob g< //// . SAFETY EVALUATION 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 FSAR7 _ f
- 3. Conduct 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 Sa sty Evaluation checklist. Safety Evaluation b b m O w Date "b - 1 M 3 Group /Dep't. Head RMyiew 4 M 10w Date 3'l!"71 U g Temporary Approvale Date (NCS) Temporary Approva18 Date ! QC Review / #4 N8M- Date 6AN? PORC Review I d w e Y - Date Md Meeting No. M -> M PlantMander[NuclearApprova1 'I/4"'A Date uh *M
' 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 l l 4
*= . _ . . - _ , _ _ _ _ . . _ . , . , _ _ . _ , . _ . - _ - _ . - . , , , , - . _ _ . _ _ _ _ _ _ _ - _.
Em;rgency Plan Inplementing Procoduro EP-2-101 Operational Support Center (OSC) Activation, Revision 2 Operation, and Deactivation [ TABLE OF CONTENTS 1.0 PURPOSE - d
2.0 REFERENCES
^ 4 3.0 RESONSIBILITIES 4.0 INITIATING CONDITIONS , l 5.0 PROCEDURE 5 .1 Activation 5.2 operation 5.3 Deactivation - 6.0 FINAL CONDITIONS '
. . e
- 7.0 ATTACHMENTS ,
71 OSC Floor Plan and Equipment Locations (1 page) I 7.2 OSC Deficiency Log (2 pages) 7.3 Emergency Team Briefing and Debriefing Sheets (3 pages) f 74 Emergency Field Monitoring Vehicles (2 pages) ' 75 Support Emergency Response Organization (3 piges) LIST OF EFFECTIVE PAGES I j Title Revision 2 1-16 Revision 2 1 _-.,,,.----,_.--__.,e,., v... , ., , , . - - , _ - , , , _ , , , ,
Emsrgsney Plan Impismsnting Preccdure EF-2-101 Operational Support Center (OSC) Activation, Revision 2 Operation, and Deactivation 1.0 PU R POS E This procedure provides guidance for the Operational Support Center - (OSC) staff in the activation, operation and deactivation of the Operational Support Center.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-010, Notifications and Communications 23 EP-2-150, Emergency Records 2.4 EP-2-190, Personnel Accountability 3.0 R ES PON SIB IL ITIES . . The Operational Support Center Supervisor is responsible for
- ensuring that actions outlined in this procedure are carried out.
4.0 INITIATING CONDITIONS This procedure is to be initiated upon any of t.he following conditions: 4.1 At the direction of the Emergency Coordinator; or 4.2 Declaration of any of the following emergency conditions; 4.2.1 Unusual Event (Optional) 4.2.2 Alert l 4.2 3 Site Area Emergency 4.2.4 General Emergency 5.0 PROCEDURE 5.1 ACTIVATION 5.1.1 Activate / set up emergency equipment in the Operational Support Center (OSC) as shown on Attachment 7.1, OSC Floor Plan and i l l \ -
EmsegGncy Plan Implcmanting Procsdure EP-2-101 Operational Support Center (OSC) Activation, Revision 2
~~
Operation, and Deactivation Equipment Locations, as appropriate. Conduct initial personnel accountability, if appropriate, in accordance with EP-2-190, , Personnel Accountability. 5.1.1.1 Activate the emergency vehicles in accordance with Attachment 7.4, Emergency Field Monitoring Vehicles. . 5.1.1.2 The Assembly Area Supervisor shall make preparations to evacuate personnel off site in the event that a site evacuation is declared. 5.1.2 If hazards prevent personnel from conducting operations in the OSC, evacuate personnel to the alternate OSC in the Administration ~ Building Meeting Room.
" ~
5.1.2.1 Take records and equipment if time / conditions permit. 5.1.2.2 Avoid hazardous areas enroute to the alternate OSC.
- 5.1.2 3 While at the alternate OSC, set up equipment and reestablish communications.
i 5.1.3 Make an assessment of OSC staff and support personnel available in ' the OSC; report the results to the Technical Support Center (TSC) - Supervisor and indicate that the OSC has been activated. i 5.2 OPERATION 5.2.1 Conduct all communications at the OSC in accordance with EP,2-010, Notifications and Communications. l l 5.2.2 Assemble, brief and dispatch support personnel as directed by the TSC. Briefings and debriefings shall be conducted in accordance - with Attachment 7.3, Emergency Team Briefing and Debriefing l Sheets. i ( 3 n ._
Emergency Plan Implementing Procedure EP-2-101 Operational Support Center (OSC) Activation. Revision 2 Operation, and Deactivation NOTE 1 , Ensure that at least one (1) individual is authorized to have access to areas the teams will be entering. NOTE 2 The OSC Supervisor must assemble the firefighting team, if necessary. 5.2.3 Handle all records generated in the operation of the OSC in ac-
~
cordance with EP-2-150, Emergen'cy Records. 5.2.4 If extended operation of the OSC is required, provide continuous = manning capability. 5.2.5 Maintain continuous personnel accountability in accordance with EP-2-190, Personnel Accountability. - l 5.3 DEACTIVATION - 5.3 1 The Emergency Coordinator will inform the OSC Supervisor when to deactivate the OSC. 5.3.2 Make preparations with the TSC Supervisor to transfer remaining responsibilities to the TSC. 5.3.3 After shifting responsibilities, inform the TSC Supervisor that the OSC has been deactivated. 5.3.4 Deactivate and restore emergency equipment and supplies shown on Attachment 7 1, OSC Floor Plan and Equipment Locations, to preactivation conditions. 5.3.5 Complete Attachment 7 2, OSC Deficiency Log. 4
~ Emsrgsney Plan Impicmsnting Procsduro EP-2-101 .
~~
Operational Support Center (OSC) Activation, Revision 2 Operation, and Deactivation 6.0 FINAL CONDITIONS Assess the status of the OSC and ensure that the following actions have been completed: 6.1 All records generated during the operation Cf the OSC have been handled in accordance with EP-2-150. 6.2 All functional equipme'nt/ supplies have been restored to preactiva- - tion conditions, as appropriate, and Attachment 7.2 has been completed and forwarded to the Emergency Planning Coordinator. 6.3 The entire OSC staff has been relieved of all duties associated with ,, the operation of the OSC. 7.0 ATTACMMENTS - - 7 .1 OSC Floor Plan and Equipment Locations 7.2 OSC Deficiency Log 7.3 Emergency Team Briefing and Debriefing Sheets 74 Emergency Field Monitoring Vehicles 7.5 Support Emergency Response Organization 5
OSC FLOOR PLAN AND EQUIPMENT LOCATIONS 4 ( LA~5 ?.J L L VMILA~T SON AQom STATUS Soma S a osc . Sons *R s pxr Aio c.44pur %~ g - dio HP P ~ :E u"aae . .- huER - i EP-2-101 Revision 1 6 Attachment 7.1 ( / of l )
OSC DEFICIENCY LOG , A. SU PPLIES : 1 Deeleted Kit Taken From/ Location 1. 2.
, I
- 3. - 1 4.
5. 6. B. MALFUNCTIONING EQUIPMENT: Ecuiement Affected Nature of Malfunction Location 1. 2. i 3. 4.
~ ~
i 5. l
- 6.
- 7 8.
9. 10. l t l l l l EP-2-101 Revision 2 7 Attachment 7.2 (/ of 2)
OSC DEFICIENCY LOG _ C. IMPLEMENTING PROCEDURES Procedure Number Problem Area 1. 2. 3. 4 l l EP-2-101 Revision 2 8 Attachment 7.2 ($of 2)
' . mto
' (HFy "Jt C'[' lMLBMjgfl SuitT yg o g gg,,
t _ A. F se of Yeen n Search and Beecue In-Flent Redfeleqfeet Controlm Yeek to be performed . First Aid Energency Repair /breratione , Fire righting Field Honitoring other (specify) Personnet j B. Teen Ifes6ers: Bedae # Destmetry ISueb6r Reposure (sRD) Centenimetten l 1) vee No
~
- 2) Tee No +
- 3) . v.e no ,J
- 4) i.e no
- 5) ,
Yes No C. AccessRouteidentified,emergencycultidentitle) F. Equipment $seueds l , Redfologicat l.
. D. Commicetione Frimary Hethod Alterieste 2. SCSA's/Seepiratore
! R*rorting Frequency,(Tine Interval) 3. Fire Fighting Steytime/ 4. NefetyI.Ines/Repes E. Isrosure limites
- contaminetton Beresure S. First Aid I.ocation Redleetlog 8.evalg I.evale allowed
- 6. Other I
- 7. ,Freper respiratory protection leeued.
S. Proper dose-rate instrument (s) (adequate ! range, bettery ekoeked, cettbrated).
- 9. Freyer.pretective clothing feeued.
l ! H. NOTE: If everemyosure is anticipated, C. Comente complete Attachment 7.1 to EF-2430. i . F.P-2 tiovinion 8 sclusent 7. of 3)
EMERGENCY TEAM BRIEFING AND DEBRIEFING SHEETS __ Date Return Time PART I EMERGENCY TEAM DEBRIEFING SHEET , Results of Operations (s): - Were plant conditions different than expected? (Circle) Yes No If yes, explain: Did any injuries occur during the entr.y? (Circle) Yes No . If yes, describe: , t Did all equipment / tools work properly? (Circle) Yes No If no, explain: Were safety precautions (including radiological) adequate? Yes No (Circle) If no, explain: l Comments: __ l -- . EP-2-101 Revision 2 10 Attachment 7 3 ( 2-of 3)
EMERGENCY TEAM BRIEFING AND DEBRIEFING SHEETS __ PART II RADIOLOGICAL DEBRIEFING (To be completed if radiological concerns encountered) Initial -' A. Exposure entered into computerized exposure tracking system. B. TLD's collected and forwarded for processing (circle). , Yes Not Required C. Breathing zone air samples collected. D. Dose rates encounter-2d identified and documented. E. Personnel require bioassay supervisor (circle). ,_ Yes Not Required
~
F. Other radiological concerns encountered: . H.P. Technician EP-2-101 Revision 2 11 Attachment 7 3 (3" of 3)
EMERGENCY FIELD MONITORING VEHICLES __
- 1) All vehicles listed in this attachment are available for use by the Waterford 3 Emergency Organization during drills, exercises or actual emergencies. ,
- 2) The Security Shift Supervisor maintains a spare set of keys for each vehicle listed.
- 3) The following vehicles are dedicated as primary transportation for ,
the off site Field Monitoring Teams during all drills, exercises or emergencies: - Model LP&L Serini Danantment Assignment Number A) 1982 Chevrolet Pickup 9356 Health Physics --
- 8) 1982 Chevrolet Pickup 9357 Admin. / Warehouse C) 1982 Chevrolet Pickup 9359 -
These vehicles are equipped with camper shells and mobile radios , on the Luling District frequency.
- 4) In the event of a drill, exercise or emergency, these vehicles shall be delivered to the OSC Supervisor, located in the Service Building. If any of these vehicles are off site, they will be recalled via the Luling District Radio. Instructions are posted -
in each vehicle in the event a recall is initiated. l 5) Page 2 of this attachment lists all the vehicles assigned to Waterford 3 SES that are available for use during drills, ex-l ercises or emergencies. . l EP-2-101 Revision 2 12 Attachment 7 4 (/ of 2)
EMERGENCY FIELD MONITORING VEHICLES __' LP&L Serial License Model Number Number Decartment/ Assignment
- 1) 1979 Chev. 9067 7778321 D. Lester ,
- 2) 1979 Ford 9076 221F019 C. Decaraux
- 3) 1980 Ford 9118 273X612 L. Maurin
- 4) 1980 Chev. 9122 284X932 R. Barkhurst
- 5) 1979 Ford 9175 790B286 L. Bass
- 6) 1980 Ply. 9186 864B219 S. Alleman
- 7) 1981 Dodge 9205 394X425 P. Prasankumar
- 8) 1982 Ford 9206 972B115 R. Burski
- 9) 1982 Dodge 9209 984B591 J. Sleger
- 10) 1982 Ply. 9210 398X169 Z. Sabri ,_
- 11) 1982 Chev. 9264 93 8B631 D. Lester
- 12) 1981 Chev. 9266 938B630 0. D. Hayes
- 13) 1980 Ford 9326 T663447 K. Riggins P. Prasankumar
- 14) 1979 Chev. 9344 T57282
- 15) 1982 Chev. 9356 T817278 R. Kenning
- 16) 1982 Chev. 9357 T817248 C. Taravella
- 17) 1982 Chev. 9359 T817586 T. Armington
- 18) 1982 Ford 9360 T817575 R. Lailheugue
- 19) 1982 Ford 9361 T817571 R. Lailheugue
- 20) 1983 Chev. 9349 P. Prasankumar i
l l l EP-2-101 Revision 2 13 Attachment 7.4 (2 Eof 2) l
SUPPORT EMERGENCY RESPONSE ORGANIZATION NE AR-SITE EMERGENCY OPERATIONS FACILITY ORGANIZATION
~ ~ ~ ~ ~ ~ ~
LOOKEEPER ADV SOR DIRECTOR l I
' ' COMMUNICATIONS OPERATIONS LICENSING '
~
COORDINATOR COORDINATOR COORDIN ATOR CCC COORDINATOR COORDINATOR COORDINATOR TE CHNICAL ADVISOR - ST. CHARLES EOC TECNNICAL l ADVISOR - FIELD DOSE STATUS BOARO ENGINEERING TECHNICAL RECORDER / COMMUNICATOR COMMUNICATOR COORD N ATOR COORDtNA COORDINATOR ADVISOR -
. OFF- SITE CORPORATE COMMAND CENTER ORGANIZATION
( EMERGENCY OIRECTOR l l l ADMINISTRATIVE / GOVERNMENT / LPSL INFORMATION SUPPORT ( TREASURY AND ACCOUNTING LOGISTICS PUBLIC AFFAIRS CENTER ENGINE ERING MANAGER MANAGER MANAGER MANAGER MANAGER SECURITY EMERGENCY COORDINATOR SY F EP-2-101 Revision 2 14 Attachment 7.5 T , , . . . , l l
ON -SITE EMERGENCY RESPONSE ORGANIZATION TSC E MERGENCY LOOKEEPER ADVISOR COORDINATOR HEALTH PHYSICS TSC LEAD TSC SECURITY OPERATIONS COORDINATOR COMMUNICATOR SUPERVISOR SUPERVISOR COOROINATOR TSC SEcunt TY COMMUNICA1DR SHIPT SUPV. WI MOIATDeG SSFTS DOSE RADIOLOGICAL TSC OSC TSC OPERATIONS OPS bEPT. ASSESSMENT CONTROLS LEAD SUPERylSOR SUPV. COladuMICATOR NOS-SS ON-SHIFT COORDINATOR COORDINATOR E NGINEER COMea T RAINING, RE LIEF TSC LOMMUN4CATOR s i ea l I I IN-PLANT HP TSC TEQHCAL EMERGENCY OSC ASSEUSLY OSC ROTATING ASSESSMENT RESPONSE COMidtlNICATOR AREA LOOKEEPER SHIPTS GROUP TEAMS SUPERVISOR OFF -SITE O N -SITE LOGI(EEPER MONITORING MONITORING MOTATING9tPT1 ROTATBdG St4PT5 LOGISTICS SEARCH ELECTRICAL MECHANICAL ISC FIRST FNtE COMPUTER REPAIR REPA4R REPAIR ABO BRIGADE REPAIR SUPPORT RES EP-2-101 Revision 2 15
,,, Attachment 7.5 ;- -
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l e t e EMERGENC TEAM / GROUP ORGAMZATION , EMERGENCY TSC TECHNICAL
RESPONSE
ASSESSMENT Manpowtn poot OROUP 60 NEMBERS ISC ELECTRICAL SEALTH PflVSICS SEAMCH AND RESCUE M AINT E N ANCE fM-PLANT, ON-SITE, MANPOWER POOL 6 NEMBERS OFF-SITE TEAM AS NEEDED NECHANtCAL MONITORING ENotNEERS II E M8EN8 FIRE BRIGADE j WINTENANCE M WR 0% AS NEEDED 8 MEM8ERS TS TRAIDfEO CHEMICAL , ENotNEERS FIRST AID SC WANPOWER POOL WAfMTENANCE AS NEEOED 4 MEMMERS 54 TRAINED NUCLEAR ENotNEERS p SUPPLY / LOGIS TICS WAINTENANCE lEAM S wtweERS e wEmeERS ELECTRICAL ENGINEEft S RAD / CHEMtSTRy RADWASTE HELPERS n mEusERS S wtueERS COttrUTER ENGINEEftS ST(S S Eu.ERS RADWASTE ENGINEERS EP-2-101 Revision 2 16 At tacliment 7.5
. Y.k , t I: -'
- WATERFORD 3 SES -
" . _ .,1 PLANT OPERATING MANDAL LOUISIANA POWE A & LIGHT ~~
NYS SY . EP-2-102 PCM VOLUME vo REVISION e POM SECTION , APPROVAL DATE: May 2, 1983 EFFECTIVE DATE: Fuel Load T EMERGENCY PLAN IMPLEME:iTING PROCEDURE EMERGECY OPERATIONS FACILITY (EOF) ACTIVATION, < OPERATION AND DEACTIVATION , (;;;pg *,4l- 0 - 3 s i 'h h"1'- ..
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- no._p 9 G -
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1 I PORC Meeting No. f 3-e 7 4 Reviewed:
/ -,,, t . I,,s PCRC Chai gan App roved: t _'l _ 'JM Planf Manager-Nuclear l
1 .
- l WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. GP-1~ lo t Title QM M (82) M, -
Effective Date FUEL LOAO (if different from approval date) - op ?4. W 6 .- D E h . Cemelete 1. B. or C . A. Change No. W N B. RevisionNoMN' 2 ' C. Deletion efb/I WFAMON FOR CHAMCE. REVISION. OR DFLFTION ~
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nm . 1 , . . n 'w wa9m 8 & JRC rno .-0 e. -.%. REQUIRED SICNATURES Originator b Uh Date M7s!PT Technical Review bY - Date 3/h I 8 3 t . SAFETT EVALUATION Does 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 '
- 3. Conduct tests / experiments not described in the FSAR7
- 4. Create a condition or conduct an operation which ex- '
ceeds, 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 Safe y Evaluation checklist. Safety Evaluation 9f . Date 3 '31-f 3 Group /Dep't. Head Review N O b& Date 3-26 0 , 4 Temporary Approvale Date (NOS) Temporary Approval
- Date .
QC Review s . HA Oft'/. >-7/ , Date & L7-PT M E m d -Date M Meeting No. f 3-814 PORCReview[duelearApproval PlantManadr
' A$1"M Date N/f *
- 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
r Emergency Plan Implementing Procedure EP-2-102- __ Emergency' Operations Facility (EOF) Activation, Revision 2 l Operation and Deactivation
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TABLE OF CONTENTS 1.0 PURPOSE 2.0 REFEREN CES 3.0 RES PONSIBILITIES 4.0 INITIATING CONDITIONS .. , 5.0 PROCEDURE 5 .1 EOF Activation 5.2 EOF Operation ' 5.3 EOF Deactivation 6.0 FINAL CONDITIONS . . 7.0 ATTACHMENTS - 7 .1 EOF Floor Plan and Equipment Locations (2 pages) 7.2 EOF Deficiency Log (1 page) 73 EOF Personnel Dosimetry Log (1 page) 7.4 Support Emergency Response Organization (3 pages) LIST OF EFFECTIVE PAGES . Title Revision 2 1-19 Revision 2 f 1
Emergency Plan Implementing Procedure EP-2-102 -- Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation
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1.0 PURPOSE This procedure provides guidance for the Emergency Operations Facility (EOF) staff in the activation, operation and deactivation of the Emergency Operations Facility.
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2.0 REFERENCES
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2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-010, Notifications and Communications 2.3 EP-2-050, Offsite Dose Assessment (Manual) 2.4 EP-2-051, Off site Dose Assessment (Computerized)
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2.5 EP-2-052, Protective Action Guidelines 2.6 EP-2-150, Emergency Records l 2.7 EP-2-170, Recovery 2.8 EP-1-010, Unusual Event 2.9 EP-1-020, Alert. 2.10 EP-1-030, Site Area Emergency l 2.11 EP-1-040, General Emergency 2.12 EP-3-050, Emergency Response Call List 2.13 EP-1-001, Recognition and Classification of Emergency Conditions 2.14 EP-2-090, Accident Assessment 2.15 EP-2-060, Radiological Field Monitoring 2.16 EP-2-190, Personnel Accountability l 2
Emergency Plan Implementing Procedure EP-2-102 _ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation
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3.0 RES PON SIB ILITIES The EOF Director is responsible for ensuring that actions outlined in this procedure are carried out. 4.0 IMITIATIMG CONDIT70MS . This procedure is to be initiated upon any of the following conditions: 4.1 At the direction of the EOF Director. 4.2 Declaration of any of the following emergency conditions: .. 4.2.1 Unusual Event (Optional) .
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4.2.2 Alert (Optional) 4.2.3 Site Area Emergency t 4.2.4 General Emergency 5.0 PROCEDURE 5.1 EOF ACTIVATION 5.1.1 Ascertain the conditions of the site and make a determination as to the possible hazards to the EOF staff should a near-site EOF activation occur. l 5 .1.1.1 If it is too hazardous to have personnel report to the site due l to natural disaster, toxic chemical or radiation release problems, activate the Backup EOF at the Gretna Green Office. { 5.1.1.2 If conditions exist that will permit personnel to respond to the site without jeopardizing their safety, then activate the primary EOF on site. i l I l 3
Emergency Plan Implementing Procedure EP-2-102 _ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation NOTE EOF staff personnel should be informed as to which EOF location is being activated when they are notified of the emergency in - accordance with the phone tree recall and alerting system discussed in EP-3-050. _, 5 .1. 2 Activate and set up necessary work spaces, communications, and emergency equipment in appropriate areas of the EOF as required.
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(See Attachment 7.1 for a floor plan of the primary EOF location.) 5.1.3 Ensure the Radiological Assessment Coordinator issues pocket . dosimeters and/or TLD's to all personnel in the EOF. Record all information corresponding to TLD issuance on Attachment 7.3, EOF , Personnel Dosimetry Log. Also ensure that frisking equipment is set up and operating at the security area near the entrance to the f EOF. k
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NOTE All personnel reporting to the EOF must frisk, i as necessary (i.e., if tney have passed through plume pathway on way to EOF, come from plant contaminated area, etc.). All personnel shall . f 1 l frisk when leaving the EOF area (at the security control point), for whatever reason. 5.1.4 Ensure a second frisking instrument is set up and operable in the l Dose Projection Area. This instrument will be monitored by Dose Projection Area personnel. If a significant increase in count l rate is detected, the Radiological Assessment Coordinator will be I notified. The Radiological Assessment Coordinator will cause such radiation level and airborne radioactivity level surveys to be 4
Emergency Plan Implementing Procedure EP-2-102 __ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation taken as are necessary. OSC Health Physics personnel will be 1~' called on as necessary for performing surveys and/or counting air samples. 5.1.5 The EOF Director shall direct that communications be established with the Technical Support Center (TSC) Emergency Coordinator and - determine which responsibilities are to be transferred to the EOF. 5.1.6 When the EOF Operations Room, Communications Room and Dose Assessment Area are fully functional, coordinate the transfer of responsibilities from the TSC to the EOF. 5.1.6.1 Ensure the EOF Communications Coordinator coordinates the transfer of communications to the EOF per EP-2-010, Attachment F'
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7.12. i 5.1 7 When the EOF is activated and Dose Assessment, off-site com- t munications and off-site Protective Action Recommendations have I been transferred, the EOF Director shall make the following an-f nouncement: ATTENTION ALL PERSONNEL ATTENTION ALL PERSONNEL THE EMERGENCY OPERATIONS FACILITY HAS BEEN ACTIVIATED. THE EOF DIRECTOR IS Name THE EOF IS NOW PERFORMING DOSE ASSESSMENT, COMMUNICATIONS WITH ; 0FF-SITE AGENCIES AND OFF-SITE PROTECTIVE ACTION RECOMMENDATIONS. ! 5.1.8 When the EOF is activated and ready to assume the transfer of responsibilities, inform the Emergency Director. 5
Emcrgoney Plan Implementing Procedure EP-2-102 - Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation NOTE ~1 The responsibilities that may be transferred to the EOF Director by the TSC Emergency Coord- f inator are:
- 1. Request for assistance of off-site agencies . k~
- 2. Protective action recommendations of off- _,
site agencies k NOTE [' The responsibilities that remain with the TSC t j
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Emergency Coordinator and will not be trans-ferred to the EOF Director are:
- 1. Classification and declaration of an g i
emergency ,
- 2. Authorization of radiation exposure in excess of 10CFR20 limits. .
t i 5.2 EOF OPERATION 5.2.1 The EOF Director shall ensure tnat the procedural steps from applicable Implementing Instructions are performed as follows: ( 5.2.1.1 Ensure the proper emergency classification has been designated by reviewing EP-1-001, Recognition and Classification of Emergency Conditions. i 5.2.1.2 Ensure that all necessary actions are taken for the designated emergency classification in accordance with EP-1-010, Unusual Event; EP-1-020, Alert; EP-1-030, Site Area Emergency; or l EP-1-040, General Emergency. 5.2.1.3 If extended operation of the EOF is required, provide continuous l manning capability. l 6
Emergency Plan Implementing Procedure EP-2-102 __ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation
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5.2.2 EOF communicators conduct communications' at the direction of the EOF Communications Coordinator and EOF Director per EP-2-010, Notifications and Communications. 5.2.2.1 The EOF Communications Coordinator shall ensure that the Followup Notification Form and Notification Checklist, At- g-tachments 7 7 and 7.13 of EP-2-010, are promptly dnd properly l utilized as approved by the EOF Director, with the exception of j'~ the NRC (ENS and HPN) reports, which will not be transferred to the EOF. 5.2.2.2 Necessary plant data shall be transferred via the sound-powered .- phone circuit using the Plant Status Checklist, Attachment 7 1 . of EP-2-090, as a basis of information. . 5.2.3 The EOF Dose Projection Coordinator shall conduct dose assessment - calculations under the direction of the EOF Radiological ' Assessment Coordinator in accordance with EP-2-050, offsite Dose Assessment (Manual), and EP-2-051, Offsite Dose Assessment (Computerized). 5.2.4 The Radiological Assessment Coordinator shall review the offsite . dose assessment findings and provide recommendations to the EOF Director with respect to warranted protective actions per EP-2-052, Protective Action Guidelines. 5.2.4.1 Field Monitoring Teams shall be directed by the Radiological Assessment Coordinator via the EOF Field Team Communicator ac-cording to EP-2-060, Radiological Field Monitoring. 5.2.5 Engineering Support personnel shall conduct accident assessment and provide technical support to the onsite organization under the direction of the Technical Services Coordinator and Engineering Coordinator. 5.2.5.1 The Engineering Support personnel shall evaluate engineering-related problems of the reactor, essential safety-related 7 _ _ . - ~ .
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Emergency Plan Implementing Procedure EP-2-102- __ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation systems, and any other significant problem areas identified by the Technical Support Center using, as necessary: A. Piping and Instrumentation Diagrams, including piping system isometrics, general arrangement drawings and electrical schematics
- 3. Applicable plant operating and/or maintenance procedures C. Parameters as given through the Safety Parameter Display System (SPDS)
D. The W3 SES Final Safety Analysis Repcrt E. Applicable equipment technical manual 5.2.5.2 Instrument and/or systems modifications shall be designed as - necessary to support off-normal plant situations in coordination with both the Technical Support Center engineering efforts and those efforts made available through requests to scpport organizations such as E3ASCO, Combustion Engineering and the Institute of Nuclear Power Operations. 5.2.5.3 Engineering Support personnel shall provide engineering recom-mendations for system modifications necessary to ensure the im-mediate safe shutdown of the reactor and any system additions necessary to maintain long-term shutdown capabilities. 5.2.5.4 Engineering Support personnel shall conduct, as requested, supplemental transient or accident analysis, including event tree analyses or computer calculations necessary to determine possible events that could occur and which should be anticipated by the emergency response organizations. 5 2.6 Procedures or guidelines shall be prepared as necessary for the installation, modification or emergency operating methodologies of plant related off-normal systems or conditions. , 5.2.7 Maintain continuous personnel accountability in accordance with EP-2-190, Personnel Accountability. 8
s Emsrgency Plan Implcm nting Proceduro EP-2-102 __ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation t , NOTE 'l As necessary, a technical review group shall be identified from the EOF and TSC staff to review and approve temporary procedures, procedure modifications and/or provisional guidelines l prepared for the immediate and timely installation .. , and/or operation of systems necessary to maintain the safety of reactor operation. When time and s conditions permit, these documents shall be sent i through the normal station review process (e.g., . the Plant Operations Review Committee [PORC), the Quality Assurance Department, and Plant . Manager-Nuclear) to review their technical validity, remaining applicability, and/or subsequent incorporation into the Plant Operations Manual. 5.2.7 The EOF Public Relations Coordinator shall prepare draft news
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releases as necessary. He shall insure that the following occu'rs: 5.2.71 News releases shall be approved by the EOF Director prior to their release. l l 5.2.7.2 Dissemination of news releases shall be made by the Emergency l News Director per the LP&L Public Information Plan. 5.2.8 Special provisions for personnel, equipment, transportation, administrative processing, procurement or parts, etc. shall be handled by the EOF Logistics Coordinator. l 5.2.9 Access control to the EOF shall be maintained by the Station 1 Security Force as requested by the EOF Director. 9
y . . . ____ . _ _ _ _ _ . _ . - _ . . _ ._ Ii Emergency Plan.Implemsnting Procedure EP-2-102
- Emergency Operations Facility-(EOF) Activation, Revis' ion 2 fI9 Operation and Deactivation 5
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5.2.10 If/ hazards (i.e., high radiation level or plume direction)
'~ < s prevent personnel from conducting operations in the EOF, evacuate personnel to the Backup EOF at the Gretna Green Office.
5.2.10.'1 Notify the Technical Support Center of the need to evacuate. 9), ~~ 5.2'.10'.2'= Transfer EOF responsibilities (such as Protective Action Recom-
' mendations, communications with offsite agencies, dose ,
' assessment, etc.) to the TSC during transit to the Backup EOF.
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5.2.10.3; Af ter responsibilities are shif ted to the TSC, ensure personnel collect all records and transportable materials. Request the
- l TSC Communicator to notify St. Charles Parish if a-police escort is needed.from the site to the Backup EOF.
\ . .
522i10.4 Proceed to private vehicles via the Construction Area gate. Take necessary radiological precautions.
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5.2.10.5 Car pool >to the Backup EOF.- Maintain communications with the Emergency Coordinator via mobile telephone. o 5.2.10.6 Once at the Backup EOF, break out all equipment and reestablish communications with the TSC. . 1 5.2.10 7 Transfer responsibilities from the TSC to the Backup EOF, as l necessary. Commence EOF activities. 4 9 l P l 10 r- -p 7 *w-9W- -ywyw-. -t-g--,'T-yea- w+,-- T-rr- ,r 5- - + - - +-T-,4. e-Tv4
Emergency Plan Imple=enting Procedure EP-2-102 __ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation NOTE 'l Consideration should be given to evacuting the EOF when radiation levels are 100 mrem /hr or greater and/or total weighted , mpe airborne concentration levels are 10 mpc or greater and there is no indica, tion 7-. that these levels will significantly decrease during the next four hours. The EOF shall be evacuated when radiation levels are 500 crem/ hour and/or total -- weighted mpe airborne concentration . levels are 100 mpc. Personnel should . evacuate the EOF if wind speed is greater i than 30 mph and there is less risk of ; E personnel injury by evacuating the EOF than by remaining at the EOF, and/or ( on-site flooding causes the EOF to be , uninhabitable. j 5.2.11 Handle all records generated in the operation of the EOF in ac-cordance with EP-2-150, Emergency Records. 53 EOF DEACTIVATION 5.3.1 Obtain joint concurrence from the Emergency Director and Emergency Coordinator to deactivate the EOF. 532 Make preparations with the Emergency Coordinator to transfer any responsibilities to the Onsite Organization or the Recovery Organization in accordance with EP-2-170, Recovery. 5.3 3 Upon completion of the transfer of responsibilities, inform the l Nuclear Operations Supervisor-Shift Supervisor (NOS-SS) that the EOF has been deactivated. 11
1 Emergency Plan Impicmsnting Proceduro EP-2-102 __ Emergency Operations Facility (EOF) Activation, Revision 2 Operation and Deactivation
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534 Deactivate and restore emergency equipment shown on Attachment 7.1 to preactivation conditions. -J 535 complete Attachment 7.2. 6.0 FINAL CONDITIONS Assess the' status of the EOF and ensure the following actions have ,
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been completed. - 6.1 All records generated during the operation of the EOF have been handled per EP-2-150, Emergency Records.
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6.2 All functional equipment / supplies have been restored to preactiva-tion conditions, as appropriate, and Attachment 7.2 has been
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completed and forwarded to the Edergency Planning Coordinator. 6.3 The entire EOF staff has been relieved of all duties associated with the operation of the EOF. 7.0 ATTACHMENTS 7 .1 EOF Floor Plan and Equipment Locations
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7.2 EOF Deficiency Log 7.3 EOF Personnel Dosimetry Log 7.4 Support Emergency Response Organizaton I 12
EOF Ft.CCR Pt.AN AND EQUIPMENT LOCATIONS . l Enem e wM SUP*CRT WCRK AREA ACCmOMAL WCRK AREA , 1 f
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; -j EOF FLOOR PLAN AND EQUIPMENT LOCATIONS o D I EOF DOSE ASSESSMENT TWX l l d.
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FACSIMILE FOR TABLE ENGINEERS EOF COMMUNICATIONS ENGINEERING ROOM - / -- STAFF HP LOCKERS
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l N RADIOLOGICAL EOF ASSESSMENT EC DIRECTOR C00RDINATORf LNED P.R. . COORDINATOR I OPERATIONS ENGINEERING COORDINATOR COORDINATOR N EOF DIRECTORS OFFICE ADMIN / TECHNICAL , LOGISTICS SERVICES 3 COORDINATOR COORDINATOR 3 t
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EOF DEFICIENCY LOG _ A. DEPLETED SUPPLIES: IIEi Kit Taken From/ Location
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3 4. 5. B. MALFUNCTIONING EQUIPMENT: ._ Ecuiement Affected Nature of Malfunction Location 1.
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5. C. IMPLEMENTING PROCEDURES Procedure Number Problem Area 1. 2. 3 , i 4. EP-2-102 Revision 1 15 Attachment 7.2 (1 of 1)
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ON -SITE EMERGENCY RESPONSE ORGANIZATION TSC EMERGENCY LOOKEEPER ADVISOR COOROIN AT OR HEALTH PHYSICS TSC LEAD TSC SECURITY OPERATIONS COORDINATOR COMMUNICATOR SUPERVISOR SUPERVISOR COORDINATOR S TSC SECURIT Y COMMUNICATOR SHIPT SUPV. dei nOTAING SitPT3 DOSE RADIOLOGICAL TSC O SC TSC OPERATIONS OPS 'EPT. D ASSESSMENT CONTROLS LEAD SUPV. COMMUNICATOR NOS-SS OH-SHIFT SUPERVISOR T RAINING, REllEF COOROINATOR COOROINATOR ENGINEER COMM TSC COMMUNICATOR
= l l I IN-PLANT HP TSC TECapaCAL EMERGENCY ASSEMBLY OSC OSC ROTATING ASSESSMENT RESPONSE LOGKEEPER COMMUNICATOR AREA SHIPTS GROUP TE AMS SUPERVISOR OFF-SITE O N -SITE LOOKEEPER MONITORING WONITORING ROTATpdG SFTS MHRTedG SitPTS MECHANICAL ISC FIRST FIRE COMPUTER LOGtSTICS SEARCH ELECTRICAL REPA!R REPAIR REPAIR AlD BRIOADE REPAIR SUPPORT RESCUE EP-2-102 Revision 2 17 . Attachment 7.4 (1 of 3) g .-
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SUPPORT EMERGENCY RESPONSE ORGANIZATION NEAR-SITE EMERGENCY OPERAllOHS FACLITY ORGANIZATION
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LOGMEEPER ADV SOR DIRECTOR l I DIONCAL NBUC ' ' LICENSING COMMUNICATIONS OPERATIONS ASSESSMENT RELATION LOGISTICS COORDIN ATOR CCC COORDINATOR COORDINATOR COORDINATOR TECHNICAL ADVISOR - ST. CHARLES EOC TECHulCAL ADVISOR - FIELO DOSE RECORDER / COMMLNCATOR COMMUNICATOR STATUS BOARD E11GINEERING TECHNICAL LOGEEEPER WI W2 NEEPER COORDINATOR COoRD N ATOR CO RDI A COORDIN ATOR ADVISOR - -
. OFF - SITE CORPORATE COMMAND CENTER ORGANIZA:lON EMERGENCY DIRECTOR i
i TREASURY AND ADMINISTRATIVE / GOVERNMENT / LPSL INFDRMATION SUPPORT ACCOUNTING LOGISitCS PUBLIC AFFAIRS CENTER ENGINE ERING MANAGER MANAGER MANAGER MANAGER MANAGER SECURITY EMERGENCY pORDINATOR ST El' 102 Revision 2 13 ALtachment 7.4 (2 of 3) b S h k l
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l l i I l i 9 EMERGENC TEAM / GROUP ORGANIZATION , TSC TECHNICAL RE E ASSESSMENT MANPOWER POOL GROUP 80 MEMBERS ISC ELECTRICAL HEALTH PHYSICS SEARCH AND RESCUE M AINT E N ANCE IN-PLANT, ON-SITE, WANPOWER POOL 6 MEMBERS Orr-SITE TEAM AS NEEDED MECHANICAL MONITORING ENGINEERS "E" FIRE BRIGADE INTEN NCE EDED ; 6 MEMBERS TS TRAINED CHEMICAL , l g ENGINEERS ' 18C FIRST AID M AINT EN ANCE MANPOWER POOL AS NEEDED l 8 NEMRERS 54 TRAINED NUCLEAR ENotNMRS COMPUTER SUPPLY / LOGISilCS MAIN TEN ANCE TEAM S MEMBERS 2 MEMBERS ELECTRICAL ENGINEERS RAD / CHEMISTRY RADWASTE liELPERS 11 MEMBERS S NEMBERS COMPUTER ENGINEERS ST(S 8 MEMBERS RADWASTE ENGINEERS EP-2-102 Revision 2 I9 ' " " "
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WATERFORD 3 SES 1 PLANT OPERATING MANUAL LaulSIANA POWER & LIGHT NSYS EP-2-110 POM VOLUME 19 REVISION 1 POM SECTION 2 APPROVAL DATE: ! EFFECTIVE DATE: DIERGENCY PLAN IMPLEMENTING PROCEDURE MAN-CAUSED EMERGENCIES LP&L W-3 RECCROS CONTRO_;_ED COPY NO. dO PORC Meeting No. f3 -918 Reviewed: h4 ORC Chairman Approved: a. /. J Plant Manager-Nuclear
WATERFORD 3 SES m PLANT OPERATING MANUAL CHANGE / REVISION /DELETIONiREQUEST Procedure No. A'O Title ~ lI :-c ' 0 c?:-b- : Vn'OF Effective Date (if different from FM-N apphoval date) Camniate 1. B. or C A. Change No. N/4 S. Revision No. / C. Deletion h/4 9e ASON- FOR CM1NGE. REVTSTON. OR DELETION ' Sh-t Yi m Y b ru.i (f ///<- b y Jib 4--k -.lk /;)- - O:f6cini- -- ikO-r N F.T_ d o/ S l/,.O e/>?h /NIV,s>;D;-Y W..-Y 1- N - -- -
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9EcuT?ED SIGNATURES Originator 52 bb@bn0 - Date U ' NOA -- - - - - Technical Review " kv b& a
- Da te U-19-T * - ~-
SAFETY EVALUATION
,- Does this change, revision, or deletion: YES NO
>1. Change the facility as descrioed in the FSAR? L-
- 2. Change the procedures as described in the FSAR?
- 3.
Conduct tests / experiments not described in the FSAR? V
- 4. Create a condition or conduct an operation which ex-ceeds, 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 % -- - Date !!~l+ 3 ' - Group /Dep't. Head Review N a Ibh n Date Id-IT@ - Temporary Approval * - - - - - - D a te - (NOS) Temporary Approvaii - -' - -
- - - Date - -
QC Review M d v4 7 -- - ------- Date - /--/ .3 - / - - - - PORC Review hbb k Date I -1 7 -EI
- - Mee tin g No . -fr- va # --
PlantManagerkuclearAppr$ val O h baDb-~- Date - N8i - - - -
- Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
. . - -- _ e. .-.
Emergency Plan Implementing Procedure EP-2-110 Man-Caused Emergencies Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5 .1 Evaluation 5.2 Response Actions 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Major Industrial Properties Within 10 Miles of Waterford 3 (1 page) 7.2 St. Charles Parish Emergency Operations Center Emergency Hotline Report (1 page) 7.3 St. Charles Parish Emergency Preparedness / Industrial Hot Line System (12 pages) l LIST OF EFFECTIVE PAGES Title Revision 1 1-18 Revision 1 1
Emergency Plan Implementing Procedure EP-2-110 Man-Caused Emergencies Revision 1 1.0 PURPGsE This procedure provides guidance in response to man-caused emergencies either from onsite or offsite sources which may affect the operation of the plant and/or the safety of station personnel.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 DOT-P-5800.2, Hazardous Materials Emergency Response Book 2.3 EP-1-001, Recognition and Classification of Emergency Conditions 2.4 EP-2-070, Protected Area Evacuation 2.5 EP-2-071, Site Evacuation 3.0 RESPONSIBILITIES The Nuclear Operations Supervisor (NOS) or the Emergency Coordinator is responsible for ensuring that actions outlined in this procedure are carried out. 4.0 INITIATING CONDITIONS This procedure is to be initiated upon being notified of a man-caused emergency in any of the following ways: 4.1 A report from station personnel 4.2 Indication from plant instrumentation 4.3 A report from offsite agencies or individuals (e.g., Industrial Hotline) . 5.0 PROCEDURE i 5.1 EVALUATION 5.1.1 Evaluate the situation; request /obtain information in the following areas: 2
Emergency Plan Implementing Procedure EP-2-110 Man-Caused Emergencies Revision 1 5.1.1.1 Location 5.1.1.2 Nature of hazardous materials involved 5.1.1 3 Severity of the incident 5.1.1.4 Protective actions necessary 5.1.2 Obtain meteorological data and use Attachment 7.1 to assess the l impact of any airborne hazards. 5.1.3 Use Reference 2.2, DOT-P-5800.2, Hazardous Materials Emergency Response Book, to evaluate the nature of the hazard where appropriate. 5.1.4 Classify the incident in accordance with Reference 2 3, EP-1-001, Recognition and Classification of Emergency Conditions, and carry ! out the immediate actions listed. 5.2 RESPONSE ACTIONS 5.2.1 Based on the results of the evaluation and in addition to the actions outlined in Reference 2.3, EP-1-001, Recognition and Classification of Emergency Conditions, carry out the following actions as appropriate: 5.2.1.1 Verify / initiate Control Room HVAC Protective Functions. 5.2.1.2 Initiate sheltering or evacuation of station personnel in ac-cordance with Reference 2.4, EP-2-070, Protected Area Evacua-tion, and Reference 2.5, EP-2-071, Site Evacuation. 5.2.1.3 If the incident is onsite, dispatch the appropriate response teams to the scene of the incident (ensure that appropriate respiratory and protective clothing are worn) to control the incident. 5.2.1.4 Request offsite assistance to aid onsite response personnel. 5.2.1.5 For train derailments / mishaps onsite, notify the Missouri-Pacific Railroad. 3
Emargsney Plan Implementing Proceduro EP-2-110 Man-Caused Emergencies Revision 1 5.2.1.6 For an aircraft crash onsite, notify the Federal Aviation Administration. 5.2.1.7 For trucking mishaps, not'ify the trucking firm (s) involved. 5.2.1.8 Maintain communications with offsite agencies. 5.2.1.9 Continue to evaluate the situation and monitor meteorological information for changing conditions until the situation is resolved. 6.0 FINAL CONDITIONS 6.1 Direct the restoration of equipment and systems to pre-activation conditions. 6.2 Close out offsite communications. 6.3 Complete any actions which may have been initiated under Reference 2.3, EP-1-001, Recognition and Classification of Emergency Conditions. 7.0 ATTACHMENTS 7.1 Major Industrial Properties Within 10 Miles of Waterford 3 7.2 St. Charles Parish Emergency Operations Center Emergency Hotline Report 7.3 St. Charles Parish Emergency Preparedness / Industrial Hot Line System 4
MAJOR INDUE AL PROPERTIES ' WITHIN 10 MILES sF WATERFORD 3
. s
\\
\
_ py, , ' , Pontchartrain Mt Air *
@ t-floserve O /
Garyville g 0 / s' N d 0 N, LEGEND - MMOR INDUSTRIES g nlltiva ,/ - f ! h afd ' ' O ARGUSCHEMICALC0%. Af JJ O BEKER INDUSTRIES \E / . - ' O BIG TilREE INDUSTRIES (AIR h f REDUCTION) r {l O BONNET CARRE OIL & GAS FIELD 1 pj Norc O CHEVRON OIL CO. .
. I g Killo' al O E.I. DUPONT de NEMOURS & CD. r- - .,
O GENERAL AMERICAN TRANSPORTATION l Q00' Hope CO. l O GOOD ll0PE OIL & GAS FIELD 1 g OG , [a[L O GOOD 110PE REFINERY l @ U00 owSar y
@ ilANVILLE OIL FIELD l e l @ ll00KER CHEMICAL CO. /' Ha l f 11
@ OCCIDENTAL CHEMICAL CO.
/ I O I ,
@ INTERNATIONAL TANK TERMINAL ,.. e I Destrellall O KAISER ALUMINUM C0KE CALCINER / $ \ *
! @ LUCY OIL & GAS FIELD ( - . l is St Rose l G MARATl10N OIL CO.
\
I
@ MONSANTO COMPANY
@ NORCO OIL & GAS FIELD
- l l 6 ll Lull g j
'(Lac Des Allemands ; F-
@ SEWELL PLASTICS CO. 1 I M ^= '
G SHELL CilEMICAL CO. N') '- l iI r G SHELL OIL CO. 6 SHELL OIL CO. CRAWFISH PLANTg r j / l l Ir -Mim sa ark [
& SOUTH LUCY OIL & GAS FIELD outte
,. b l
@ TAFT GAS FIELD O -
G TEXACO REFINERY .- \ D UNION CARBIDE CO. '\, aradla - G USAMEX j ,G WITCO CHEMICAL CO. #-
} #'] # (
, ,, , , n attachmant 7 1 (1 of 11
ST. CHARLES PARISH EMERGENCY OPERATIONS CENTER EMERGENCY HOTLINE REPORT This is the St. Charles Parish Emergency Operations Center with an Industry Hotline Initial Notification Message. Please obtain a copy of the Industrial Hotline Initial Notification Message Report and stand by to copy. Due to the following circumstances, an incident has been reported by: AGENCY / PLANT / Member Industry /NAME OF. PERSON PROVIDING INFORMATION/ TELEPHONE This incident'/ emergency is a: (circle one) CODE 1 - ALERT (Lowest Priority) CODE 2 - SITE EMERGENCY (Higher Priority) CODE 3 - GENERAL ALARM (Highest Priority) NOTIFICATION TIME: hours DATE: INCIDENT DETAILS: (circle one) FIRE GAS RELEASE EXPLOSION LIQUID OTHER: SUBSTANCE INVOLVED: I.D. GUIDE GUIDE NUMBER
- FLAMMABLE T0XIC
- OTHER j METEOROLOGICAL CONDITIONS
WIND SPEED WIND DIRECTION FROM RECOMMENDED PROTECTIVE ACTIONS: ANTICIPATED DURATION OF INCIDENT: ESTIMATED: ACTUAL AFFECTED PLANTS / INDUSTRIES / SECTORS: EP-2-110 Revision 0 6 Attachment 7 2 (1 cf 1)
ST. CHARLES PARISH EMERGENCY PREPAREDNESS / INDUSTRIAL HOT LINE SYSTEM f OPERATING PROCEDURE MANUAL l l l \ EP-2-110 Revision 1 7 At tachment 7.3 (1 of 12)
INDEX
- l. PURPOSE - - - - - - - - - - - ----------- 1
- 11. SYSTEMS DESCRIPTION - - - - - - - - - - - - - - - - - 2 III. ADMINISTRATI VE - - - - - - - - - - - - - - - - - - - 3 IV. OPERATING PROCEDURE - - - - - - - .- - - - - - - - - 4
- V. SYSTE'A REPAIR SERVICE - - - - - - - - - - - - - - - 8 ATTACHMENTS ATTACHMENT i: REPATR SERVICE LISTINGS ATTACHMENT 11: SIMPLIFIED SYSTE'A SCHEMATIC ATTACHMENT 111: EMERGENCY COMMUNICATICNS CHECKLIST l
l I I i l l r l EP-2-110 Revision 1 8 Attachment 7.3 (2 of 12) a
ST. CHARLES PARISH BIERGENCY PREPAREDNESS /INCUSTRIAL HOT LINE SYSTUI
- 1. PURPOSE This system p.tovides a centtali:ed ccmmunication ne,tec.tk whe.te emetgency info.tmation can be ccmmunicated betceen the ECC and membe.1 indu.stries . The ECC will coc.tdinate all c.ther civil agency assist 1nce that may be necessety to .tespond to an emetgency. The Hot Line System is to be used ht conjuction with existing membet indastty emetgency p.tccedu.tes .
The basic objective'is to p.tavide quick, ef fective and acca. tate info.tmation to the Emetgency Opetatica Cente,t (ECC) and membet i>tdustties of an impending 01 actual eme,tgency. EP-2-110 Revision 1 9 Attachment 7.3 (3 of 12)
II. SYSTEM DESCRIPTICN A. This system is a private tie Lbte betocen the Eme.tgency (peration Center located at the St. Chattes Parish Courthouse in Hahnville and each member hdustty. It is a too-way automatic . tinging cLtcuit, using South Central Belt equipment located in their Hahnvine Exchange Building, and dedicated Eell System cable facilities betveen all locations. The system can not be accessed by anyone cuer than member industtles and de ECC in Hahnville. It is activated by either de ECC or membet hdustty lifting de handset from delt HOT LINE telephone. Ringing voltage wiu be immediately applied to de called station and a . tinging tone will be hea.td by de caUing station. When de caued station hea.ts his phone ringhg he Lifts de handset on his HOT LINE telephone. Ringing will den be discontinued and a message o.t information can be exchanged a.t this point. The ECC has the capability to initiate, answer or add any or all of the sepztate HOT LINES an .a:cen{ere.nce type call if required. A noticeable stansmission toss betceen membe.t industries on t.his type can should be e.xpected. B. The system has a 24 hour monitoring capability with consoles in the following locations:
- 1. Commartications Room of EOC
- 2. ECC Secretzty's Office
- 3. She. tiff's Office - Radio Dispatcher's Room C. The attached sketch ( Attachment 171 shoe -the basic . design .and
.touthg of HOT L1HE circuits beheecn menber indastties and de EOC.
EP-2-110 Revision 1 10 Attachment 7.3 (4 of 12)
III. ADMINISTRATIVE PROCEDURE A. MStBERSHIP:
- 1. Applications are obtained from de ECC Office
- 2. Applications approved by t.he DLtector of Emergency Prepstedness are sulmitted to Soud Centtal Bell Mxrheting Division fat processing
- 3. Survey to be made by Ma.theting Division and cost of hstn19atinn and monthly cha.tge proposai subunitted to GPplicad
- 4. Member Industries will receive a copy of de St. Chattes Emegency Preparedness /Industtial Hot Line System Procedure Manual and are responsible for Seir internai personnet stain.ing in the opeution of the system B. SYSTEM TEST
- 1. Each Thursday, beginning at 9s15A'd, except holidays
- 2. ECC or Sherif f *s Office will initiate a call to each member industty and each member industty will coit back immediately to provide a too-nzy system test t
- 3. The system conference capability wit.l be tested weekly with random member industtles by ECC or Sheriff's Office i
f EP-2-110 Revision 1 11 Attachment 7.3 (5 of 12) {
* *: CPERATING PRCCEDURE A. SYSTEM USE AUTHORTZATION The Hot Line System is to be used by authori:ed personnei of member industties only and sclely for emergency communication between said industty and de Energency Operation Ceder. Member o.tgani:ations shall develop internal p.tocedu,tes designating 40t Line usage cathari:ation and responsibdity.
B. SYSTEM USAGE GUIDELINES
- 1. GENERAL lt is intended dat de Hot Line System be used for emergency situations in a membet organi:ation's facilities which have o.1 are anticipated to have visibility or impact beyond the affected facility's prope. tty Lines. These situations may include, but are. not finlied to:
- a. Unusual noises, odors, abnor. mat and/or extended ftaring activity, etc. which 'may be pe.tceived as atypical by de general public.
- b. In.tetnat eme.tgencies such as fLtes, explosions, gas o.t liquid releases, etc. which may be constalled by the affected industty and is unlikely to extend beyond deit fenceline, but may be visible to de public.
- c. Intetnal emetgencies such as fLtes, explosions, gas or Liquid releases, etc. wh.ich may extend beyond de affected industry's faciltties.
- d. Exte.tnat emetgencies such as ha:ardous material ttaessportation accidents, pipeline Leaks /r.upture.1, etc.
EP-2-110 Revision 1 12 Attachment 7.3 (6 of 12)
C. SYSTEM OPERATING PROCEDURE
- 1. INDUSTRY-TO-ECC Any situation or emergency meeting Ste guidelines described in 8.1.a.b.c.d above should be ptomptly reported to ECC, and adubed if any assistance is needed. The authorized affected industty
.tepresentative should clearig advise de ECC of the ptoper emergency code and apptopriate detalis, utiLicing de Emetgency Communica, tion Checkiist (Attachment III). As a requirement, when de EOC is notified of any incided, die af fected industry shali advise the EOC when the condition or emergency has cleated. In de event of a CODE 2 SITE EMERGENCY or CODE 3 GENERAL ALARM, 3te affected industty should convey to de ECC DLtector ute necessary information, details, and recomendations to assure the proper and apptopt.iate civil agency support is ptovided.
- 2. EOC-TO-INOUSTRY An industty or extennai emetgency of a CODE 2 SITE EMERGENCY or CODE 3 GENERAL ALARM nature may necessitate de ECC alerting a neighboring, dowiscind or onte.uaise potentially affected industty of die nature of the emergency so proper portective measures may be planned and/or initiated. The EOC shouid provide the necessary l details suf fielent to assure die ptoper prote.ctive measu,1es can l
be taken.
- 3. INOUSTRY-TC-1NDUSTRY The Hot Line System is capabie of ptoviding indust:y-to-industty communications. When an emergency or situation necessitates industuj-to-industty communication, de EOC should be requested by
$1e affected industty to contact Bte requested cuer industty on the Hot Line confetence Line. This mode unil enabie ditect, 400 for more) way commun.ication behoeen indust ~ies and 6te ECC.
I l EP-2-110 Revision 1 13 Attachment 7.3 (7 of 12) i
.t. EMERGENCY COM%NICATIONS CCDES The follotcing emergency communication codes should be u. sea when a membet hdustty deems it necessety to use the Hot Line Systen:
CCOE 1 ALERT - Lowest level of priority. A minor emetgency or problem such as a fire, explosion, gas or Liqu.id release, unusual noise, unusual ador, abno.wat and/c.t extended fizzing activity or other internal event has occurted which may be visible or de.tectable by offsite people but for which no extetnat action or assistance is necessaty. The emergency is undet conttal or expected to be brought under cod. tot in a short time. CCDE 2 SITE EMERGENCY - Higher level of priditity - standby. A mode, tate eme,1gency such as a fite, explosion, gas or Liquid release, or other event has occursed which affects plant operation and for which protective action for offsite may be necessary. The emergency is not ye,t under conttot and may extend or has extended beyond the indussty's conttot. Offsite enetgency assist.ance wouid be placed in standby condition. CCOE 3 GENERAL ALARM - Highest level of priority - emergency assis-tance needed. A severe emergency such as a majd fite, explosion, gas or Liquid .telease, or other event has occurted which sericusly af fects plant l opera. tion, jeopardizes offsite atcas and for which protective actions of fsite will be necessa,ty. Emergency affsite assistance would be activated and the affected public and nestby indust ~J.es would be Mdfid. EP-2-110 Revision 1 14 Attachment 7.3 (8 of 12)
S. EMERGENCY CCMMUNICATIONS CHECKLIST Membet industries are expected .to complete the Emergency Communications Checklist iAttachment 111) a.t the time of an incident to assure clear and accurate information is stansmitted to the ECC. This information should be conveyed in the sequence listed on the checklist. Member industties are encouraged to subsequently atilize tJ is completed form as may be needed by intetnal reqaltements for documentation. l l l l l EP-2-110 Revision 1 15 Attachment 7.3 (9 of 12)
. _ _, __. _ .- - _- - - . . = .
\
V. SYSTEM RiiPA1R SERVICE A. REPAll! SERVICE
- 1. Sgt. tem breakdowns or mechanical difficallies should be ptcmpt.ty .teported to tite ECC. The ECC wit.t coordinate repai.1s mLtJt South Cen.t%al Bell. Roatine minor .tepai.ts or eme.tgency
.tepair.s can also be coordina.ted by the affected membe.1 indusety by calling tJte appropia.it Scath Centtal Bett Repai.t Se.tvice numbe.t listed in Attachment 1.
- 5. SYSTEM MC0lFICATION
- 2. Any modification to the. Hot Line System must be clea.ted tJt.tcugh tite OLtector of Eme.tgency Preparedness to assure system integrity and reliability ate maintzined. The ECC DLtect .1 will coa.tdbtate any .tequest.s for system changes between tJte membe.t industty and th appropriate Sou.ch Centtal Bell Marketbtg 9.toup.
a b e t r' 4 EP-2-110 Revision 1 16 , Attachmen't 7 s 3 (10 of 12)'
ATTACHMENT 1 ST. CHARLES PARISH EMERGENCY PREPAREC4ESS/tNQUSTRY HCT LINE SYSTEM REPATR SERVICE MEUSER TNDUSTRY REPA1R SERVICE N0. CIRCU1T NC_.
' 652-9011 60PL 8406 SUNGE CCRPORATION IKEY LUCAS (rCMEl 652-9011 60PL 8418 652-9011 60PL 8420 GCCO HCPE REFINERIES GATX TEP.'.(INA L ( 44 3- 2 5 ! ! ; 652~90II
? ; 6005 1131 SHELL CTL (NCRCC) 652-9011 60PL 8401 60PL . 8399 TNTERNATICNAL .vATEX 652-9011 60PL 8398 ST. CHARLES GRAIN 652-9011 652-9011 60PL' 8514 SHELL CHEMICAL (NCRCC) 60?L 8402 AMERICAN CYANAMi9 822-1435 822-1435 60PL 8473 FARMERS EXPCRT CCHPANY 60PL 0423 TEXACC 870-1122 62PL 18012 MONSANTO 870-1122 UNICN CARSIDE 870-1122
, 62PL 18013 WITCC 870-1122
, 62PL 18011 870-1122 62PL 18010 SEKER SHELL (TAFTl 870-1122 62PL 18009 i 870-1122 62PL 18008 MCCKER UNION CARSTCE STAR PLANT 870-1122 62PL 18057 !! s 870-1122 62PL 18058 SHELL " CRAYFISH" UNION CARSIDE Ll?.TE 870-1122
< : 62PL 12246 870-1122 62PL 1802t WATERFCRD 111 4
' 652-9011 60PL 8525 LTTTLE GYPSV 60PL 8625 SHELL P:PELINE 652-9011 EP-2-110 Revision 1 17 Attachment 7.3 (11 of 12)
ATTACHMENT 11 ST. CHARLES PARISH EMERGENCY PREPAREDNESS / INDUSTRIAL ^ HOT LINE SYSTEM SIMPLIFIED SYSTEM SCHEMATIC UNION CARBIDE WITCO BEKER SHELL TAFT HOOKER STAR PLANT SHELL " CRAWFISH" LINDE WATERFORD lit h if CONTROL f;l C
~
HAHNVILLE TELEPHONE NORCO EOC EXCHANGE TELEPHONE 7 1 I]I HAHNVILLE : EU NT EXCHANGE ( C IO A A i f if BOUTTE GATX H OIL TELEPHONE EXCHANGE IKEY LUCAS a GOOD HOPE 1I BUNGE ST. CHARLES GRAIN MONSANTO SHELL CHEMICAL TEXACO UTTLE GYPSY FARMERS EXPORT BIG THREE AM. CYANAMID EP-2-110 Revision 1 18 Attachment 7.3 (12 of 12) l
l WATERFORD 3 SES
- PLANT OPERATING MANDAL LOUISIANA MICCLE SOUTH UT1uTIES SYSTEM EP-2-102 POM VOLUME 18 REVISION 1 PCM SECTION 2 APPROVAL DATE:
EFFECTIVE DATE: DIERGENCY PLAN IMPLDIENTING PROCEDURE DIERGE' ICY OPERATIONS FACILITY (EOF) ACTIVATION, OPERATION AND DEACTIVATION LP&L W-3 RECCRDS CONTROI_ LED COPY NO. 4 1 l PORC Meeting No. [3 - C) 8 _ \ Reviewed: $__ m RC Chairman \ Approved: I ?. . Nu. t Plant Manager-Nuclear l
WATERFORD 3 SES
** N PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST e
( z$1., y e.. g lg/.'albhu
~ 7e* r:ivb N - hT~h
,-d)idWMdh Procedure No. c -O-/6' -
Title - h 4- d Effective Date (if different from PM-N approval date) Cemniete A. B. or C A. Change No. N/4 B. Revision No. I C. Deletion ^/4 97AMON' TOR CHA* ICE. REVISION. OR DELETION Y -rl] ,im.d ioh.,o r),V/g
/tns/- A :-l sJY ;- 9,/Ev>,1l- --
Cb't.rd f: n ijc! rh, 'I 07 s a n?, y' $ . w, '. .- &= ne,' ?,?- - - U - - - - -
<( / #7 -j REOUIRED SIGNATURES Originator E [11dNui -
Date I b N 1 -- ---- Technical Review o- k h d Ar - -- -- Date -'Ihl9 W - - SAFETY EVALUATION
,s Does this change, revision, or deletion:
- YES NO
'1. Change the f acility as described in the FSAR? U
- 2. Change the procedures as described in the FSAR? 1-3.
Conduct tests / experiments not described in the FSAR? ' C- "
]
- 4. Create a condition or conduct an operation which ex- D ceeds, or could result in exceeding, the limits in Technical Specifications?
l If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist. Safety Evaluation 6 / b Gd4 - -- - Date - ll-t 9 % - Group /Dep't. Head Review $ 0 b h 4 , -- Date I I - I 9 - 21.- - v a Temporary Approval * -- -- - -- Da te -
- (NOS)
Temporary Approval
- Date - -'
QC Review & W bi.s wV-- - ----*-- Date - H 3 * ? S---- PORC Review N N NI Date l - M -M3 ' - - Mee ting No . -P T -M 4 --' l Plant Manager kuclear Appbval - 2bbcbM-- Date Un /O ----
' Temporary approval must be followed by Plant Manager-Nuclear approval l
within 14 days, l j UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 ! Operation and Deactivation TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE , 5.1 EOF Activation 5.2 EOF Operation 53 EOF Deactivation 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS f 7.1 EOF Floor Plan and Equipment Locations (2 pages) 7.2 EOF Deficiency Log (1 page) 73 Transfering Communications Responsibilities to the EOF (2 pages) 7.4 EOF Personnel Dosimetry Log (1 page) l LIST OF EFFECTIVE PAGES i Title Revision 1 1-17 Revision 1 1 1
Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation 1.0 PURPOSE This procedure provides guidance for the Emergency Operations Facility (EOF) staff in the activation, operation and deactivation of the Emergency Operations Facility.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-010, Notifications and Communications 2.3 EP-2-050, Offsite Dose Assessment (Manual) 2.4 EP-2-051, Offsite Dose Assessment (Computerized) 1 2.5 EP-2-052, Protective Action Guidelines 2.6 EP-2-150, Emergency Records 2.7 EP-2-170, Recovery 2.8 EP-1-010, Unusual Event 2.9 EP-1-020, Alert 2.10 EP-1-030, Site Emergency 2.11 EP-1-040, General Emergency 2.12 EP-3-050, Emergency Response Call List 2.13 EP-1-001, Recognition and Classification of Emergency Conditions 2.14 EP-2-090, Accident Assessment 2.15 EP-2-060, Radiological Field Monitoring 3.0 RESPONSIBILITIES The EOF Director is responsible for ensuring that actions outlined in this procedure are carried out. 2
Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation 4.0 IFITIATInc CONDITIONS This procedure is to be initiated upon any of the following. conditions: 4.1 At the direction of the EOF Director. 4.2 Declaration of any of the following emergency conditions: 4.2.1 Unusual Event (Optional) 4.2.2 Alert (Optional) 4.2.3 Site Emergency 4.2.4 General Emergency 5.0 PROCEDURE 5.1 EOF ACTIVATION 5.1.1 Ascertain the conditions of the site and make a determination as , to the possible hazards to the EOF staff should a near-site EOF activation occur. 5.1.1.1 If it is too hazardous to have personnel report to the site due to natural disaster, toxic chemical or radiation release problems, activate the alternate EOF at the Gretna Green Office. 5.1.1.2 If conditions exist that will permit personnel to respond to the site without jeopardizing their safety, then activate the i primary EOF on site. i f l 3
I l Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation NOTE - EOF staff personnel should be informed as to . which EOF location is being activated when they are notified of the emergency in accordance with the phone tree recall and alerting system discussed in EP-3-050. 5.1.2 Activate and set up necessary work spaces, communications, and emergency equipment in appropriate areas of the EOF as required. (See Attachment 7.1 for a floor plan of the primary EOF location.) 5.1.3 Ensure the Radiological Assessment Coordinator issues pocket dosimeters and/or TLD's to all personnel in the EOF. Record all information corresponding to TLD issuance on Attachment 7.4, EOF Personnel Dosimetry Log. 5.1.4 The EOF Director shall direct that communications be established with the Technical Support Center (TSC) Emergency Coordinator and determine which responsibilities are to be transferred to the EOF. 5.1.5 When the EOF Operations Room, Communications Room and Dose Assessment Area are fully functional, coordinate the transfer of responsibilities from the TSC to the EOF. 5.1.5.1 Ensure the EOF Communications Coordinator coordinates the transfer of selected communications to the EOF per Attachment 7.3 5.1.6 Upon completion of the transfer of responsibilities, inform the Emergency Director. 4
Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation NOTE The responsibilities once transferred from the Emergency Coordinator which may not be dele-gated are: A. Classification and declaration of an emergency B. Request for assistance of off-site agencies C. Protective action recommendations of off-site agencies D. Authorization of radiation exposure in excess of 10CFR20 limits 5.2 EOF OPERATION 5.2.1 The EOF Director shall ensure that the procedural steps from applicable Implementing Instructions are performed as follows: 5.2.1.1 Ensure the proper emergency classification has been designated by reviewing EP-1-001, Recognition and Classification of Emergency Conditions. 5.2.1.2 Ensure that all necessary actions are taken for the designated emergency classification in accordance with EP-1-010, Unusual Event; EP-1-020, Alert; EP-1-030, Site Emergency; or EP-1-040, General Emergency. 5.2.1.3 If extended operation of the EOF is required, provide continuous manning capability. 5.2.2 EOF communicators conduct communications at the direction of the EOF Communications Coordinator and EOF Director per EP-2-010, Notifications and Communications. 1
- 5.2.2.1 The EOF Communications Coordinator shall ensure that the Station l
l Status Checklist and Notification Checklist, Attachments 7.7 and 1 5 l
l Emergency Plan Implementing Procedure EP-2-102 j Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation 7.10 of EP-2-010, are promptly and properly utilized as approved by the EOF Director. 5.2.2.2 Necessary plant data shall be transferred via the sound-powered phone circuit using the Plant Status Checklist, Attachment 7.1 of EP-2-090, as a basis of information. 5.2.3 The EOF Dose Projection Coordinator shall conduct dose assessment calculations under the direction of the EOF Radiological Assessment Coordinator in accordance with EP-2-050, Offsite Dose Assessment (Manual), and EP-2-051, Offsite Dose Assessment (Computerized). 5.2.4 The Radiological Assessment Coordinator shall review the offsite i dose assessment findings and provide recommendations to the EOF Director with respect to warranted protective actions per EP-2-052, Protective Action Guidelines. 5.2.4.1 Field Monitoring Teams shall be directed by the Radiological Assessment Coordinator via the EOF Field Team Communicator ac-cording to EP-2-060, Radiological Field Monitoring. 5.2.5 Engineering Support personnel shall conduct accident assessment and provide technical support to the onsite organization under the direction of the Technical Services Coordinator and Engineering Coordinator. 5.2.5.1 The Engineering Support personnel shall evaluate engineering-related problems of the reactor, essential safety-related systems, and any other significant problem areas identified by the Technical Support Center using, as necessary: A. Piping and Instrumentation Diagrams, including piping system isometrics, general arrangement drawings and electrical schematics l B. Applicable plant operating and/or maintenance procedures C. Parameters as given through the Safety Parameter Display System (SPDS) 6 l- .
Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation D. The W3 SES Final Safety Analysis Report E. Applicable equipment technical manual 5.2.5.2 Instrument and/or systems modifications shall be designed as necessary to support off-normal plant situations in coordination with both the Technical Support Center engineering efforts and those efforts made available through requests to support organizations such as Ebasco, Combustion Engineering and the Institute of Nuclear Power Operations. 5.2.5.3 Engineering Support personnel shall provide engineering recom-mendations for system modifications necessary to ensure the im-mediate safe shutdown of the reactor and any system additions necessary to maintain long-term shutdown capabilities. 5.2.5.4 Engineering Support personnel shall conduct, as requested, supplemental transient or accident analysis, including event tree analyses or computer calculations necessary to determine possible events that could occur and which should be anticipated by the emergency response organizations. 5.2.6 Procedures or guidelines shall be prepared as necessary for the installation, modification or emergency operating methodologies of plant related off-normal systems or conditions, l f ( 7 1
4 Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation NOTE As necessary, a technical review group shall be identified from the EOF and TSC staff to review and approve temporary procedures, procedure modifications and/or provisional guidelines prepared for the immediate and timely installation and/or operation of systems necessary to maintain the safety of reactor operation. When time and conditions permit, these documents shall be sent through the normal station review process (e.g., the Plant Operations Review Committee [PORC], the Quality Assurance Department, and Plant Manager-Nuclear) to review their technical validity, remaining applicability, and/or subsequent incorporation into the Plant Operations Manual. 5.2.7 The EOF Public Relations Coordinator shall prepare draft news releases as necessary. He shall insure that the following occurs: 5.2.7.1 News releases shall be approved by the EOF Director prior to their release. 5.2.7.2 Dissemination of news releases shall be made by the Emergency News Director per the LP&L Public Information Plan. 5.2.8 Technical response to Nuclear Regulatory Commission (NRC) inquiries during the emergency shall be provided by the EOF Licensing Coordinator. 5.2.8.1 Any written response shall be approved by the EOF Director prior to release to the NRC. 8
l l Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation 5.2.9 Special provisions for personnel, equipment, transportation, administrative processing, procurement or parts, etc. shall be handled by the EOF Logistics Coordinator. 5.2.10 Access control to the EOF shall be maintained by the Station Security Force as requested by the EOF Director. 5.2.11 If hazards prevent personnel from conducting operations in the EOF, evacuate personnel to the alternate EOF at the Gretna Green Office. 5.2.11.1 Notify the Technical Support Center of the need to evacuate. 5.2.11.2 Transfer EOF responsibilities (such as Protective Action Recom-mendations, communications with offsite agencies, dose assessment, etc.) to the TSC. 5.2.11.3 Make arrangements to obtain the Emergency Coordinator's mobile telephone for use by the EOF Director during transit to the alternate facility. 5.2.11.4 After responsibilities are shifted to the TSC, ensure personnel collect all records and transportable materials. Request the TSC Communicator to notify St. Charles Parish if a police escort is needed from the site to the Alternate EOF. 5.2.11.5 Proceed to private vehicles via the Construction Area gate. Take necessary radiological precautions. 5.2.11.6 Car pool to the Alternate EOF. Maintain communications with l the Emergency Coordinator via mobile telephone. ! 5.2.11.7 Once at the Alternate EOF, break out all equipment and reestablish communications with the TSC. 5.2.11.8 Transfer responsibilities from the TSC to the Alternate EOF, as l necessary. Commence EOF activities. 9
Emergency Plan Implementing Procedure EP-2-102 Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation o NOTE Personnel should evacuate the EOF if a) radiation levels are greater than 24 mrem /hr and there is an indication that radia-tion levels will not significantly decrease during the next four hours, b) wind speed is greater than 30 mph and there is less risk of personnel injury by evacuating the EOF than by remaining at the EOF and c) onsite flooding causes the EOF to be uninhabitable. 5.2.12 Handle all records generated in the operation of the EOF in ac-cordance with EP-2-150, Emergency Records. 5.3 EOF DEACTIVATION 5.3.1 Obtain joint concurrence from the Emergency Director and Emergency Coordinator to deactivate the EOF. i 1 5.3.2 Make preparations with the Emergency Coordinator to transfer any l responsibilities to the Onsite Organization or the Recovery Organization in accordance with EP-2-170, Recovery. 5.3.3 Upon completion of the shift of responsibilities, inform the l Nuclear Operations Supervisor-Shift Supervisor (NOS-SS) that the EOF has been deactivated, i 5.3.4 Deactivate and restore emergency equipment shown on Attachment 7.1 to preactivation conditions. 5.3.5 Complete Attachment 7.2. l l 10 I
Emergency Plan Implementing Procedure EP-2-102 l Emergency Operations Facility (EOF) Activation, Revision 1 Operation and Deactivation 6.0 FINAL CONDITIONS Assess the status of the EOF and ensure the following actions have been completed. 6.1 All records generated during the operation of the EOF have been handled per EP-2-150, Emergency Records. 6.2 All functional equipment / supplies have been restored to preactiva-tion conditions, as appropriate, and Attachment 7.2 has been completed and forwarded to the Emergency Planning Coordinator. 6.3 The entire EOF staff has been relieved of all duties associated with
~
the operation of the EOF. 7.0 ATTACHMENTS 7.1 EOF Floor Plan and Equipment Locations 72 EOF Deficiency Log 7.3 Transferring communications Responsibilities to the EOF 7.4 EOF Personnel Dosimetry Log l 11
EOF FLOOR PLAN AND EQUlPMENT LOCATIONS . I I EnanEEMins suppeRT WORK AREA ADDITIONAL WORK AREA utn's Recu . 5.DG. MECH. ROCM WCMEN'S ROCM
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TRANSFERRING COMMUNICATIONS RESPONSIBILITIES TO THE EOF
- 1. Establish communications with the TSC Lead Communicator and discuss the 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)
- 2. For communication lines which are jointly shared by the TSC and EOF:
- a. EOF Communications Coordinator directs the EOF Communicator to shift communications to the EOF.
- b. The EOF Communicator picks up the line, listens to any transmissions occuring at the time and logs the communication on the Communication Log Sheet (Attachment 7.1 of EP-2-150, Emergency Records).
NOTE Do not respond; allow the TSC Communicator to continue handling communications.
- c. At a point when there is little to no traffic on the line, the EOF l Communicator announces the following: THE WATERFORD 3 EMERGENCY OPERATIONS FACILITY IS NOW RESPONSIBLE FOR COMMUNICATIONS ON THIS LINE.
j d. Stand by for the TSC Communicator to announce that THE WATERFORD 3 l TECHNICAL SUPPORT CENTER RELINQUISHES COMMUNICATION ON THIS LINE. After hearing the announcement, inform the EOF Communications l Coordinator that communications have been transferred. i 3. For communication lines which are not jointly shared by the TSC and EOF: EP-2-102 Revision 1 15 Attachment 7.3 ( ) of,1) l l
TRANSFERRING COMMUNICATIONS RESPONSIBILITIES TO THE EOF NOTE The TSC Lead Communicator and EOF Communications Coordinator coordinate the transfer as follows while in communication with each other.
- a. The EOF Communications Coordinator directs the EOF Communicator to establish communication on the line.
- b. The EOF Communicator establishes contact and makes the following announcement:
THIS IS THE WATERFORD 3 EMERGENCY OPERATIONS FACILITY. THE EMERGENCY OPERATIONS FACILITY IS NOW RESPONSIBLE FOR COMMUNICATIONS ON THIS LINE.
- c. Inform the EOF Communications Coordinator that communications are established.
- d. The EOF Communications Coordinator informs the TSC Lead Com-municator that the transfer has been completed.
NOTE If the EOF is unable to establish communication, the TSC will reestablish communication immediately. The EOF should try establishing communications via an alternate line.
- e. Upon successfully transferring communications responsibilities, inform the EOF Director of the shif t in communications.
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WATERFORD 3 SES
- PLANT OPERATING MANUAL LOUISIANA MICCLE SCUTH UT!UTiES SYSTEM EP-2-120 .
PCM VOLUME IS REVISION 1 PCM SECTION 2 APPROVAL DATE: EFFECTIVE DATE: DIERGENCY PLXi IMPLE'!ENTING PROCEDURE NATURAL EMERGENCIES LP&L W-3 RECORCS CONTROLLE] COPY NO. 0 WI PORC Meeting No. fd -vi d , Reviewed: . P C Chairman Approved: A b Plant Manager-Nuclear 1
WATERFORD 3 SES
'% PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. cY~k -NO
- Title - Y'b'Di O >~;' n '7' < - - - - -
Effective Date (if different from Pd-N approval date) Camniete 1. 9. or C A. Change No. NlA
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C. Deletion M/> DeASON TOR CM1NGE. REVISION. OR DELETION I.0-/ -l) w ?/~ d. b b///< /cs, v/ A ,h - /Mr* A',y pa /Sh.Enl - - -- l,'a - Jl 9 .' h , .),; Y$19, ..,.,l / &./,,,: :44. '
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n SAFETY EVALUATION
, - Does this change, revision, or deletion: YES NO
- 1. Change the f acility as described in the FSAR?
- 2. Change the procedures as described in the FSAR? *
- 3. Conduct tests / experiments not described in the FSAR7 ' 8- -
4 Create a conditicn or conduct an operation which ex-l ceeds, or could result in exceeding, the limits in Technical Specifications? If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safet' Evaluaticn checklist. Safety Evaluation @b & - -- - Date N'-b h - Group /Dep't. Head He iew bv N i$mh' - Date Il-/9 G - 3 Temporary Approval * - - -- - - Da te - - - (NOS) Temporary Approval * - -- -- -
--- Date - -
QC Review - M I - #-- - ---- -- Date - /- 6 4 8 ----- PORC Review k - Date I 'l 9 -Y A- ~ Meetin No. -R t'28-- PlantManagerkNuclearAppkoval- M h b N ~~ Date - 'N - *---
- Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
l l UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
. Emergency Plan Implementing Procedure EP-2-120 Natural Emergencies Revision 1 TABLE OF CONTENTS 1.0 PURPOSE 2.0 REFEREN CES 3.0 RES PONSIBILITIES 4.0 INITIATING CONDITIONS , -5.0 PROCEDURE 5.1 General 5.2 Tornado / Hurricane 5.3 Flooding 5.4 Earthquake 6.0 FINAL CONDITIONS 70 ATTACHMENTS 7.1 List of Structurally Safe Areas to Shelter Onsite Personnel (1 page) (LATER)
LIST OF EFFECTIVE PAGES Title Revision 1 1-5 Revision 1 1 5- - - . --
I Emergency Plan Implementing Procedure EP-2-120 Natural Emergencies Revision 1 1.0 PURPOSE The purpose of this procedure is to provide site specific instructions for an emergency that supplement the Louisiana Power and Light Company Grganization for Major Emergency plan. 2.0 REFERElCES 2.1 Louisiana Power and Light Company Organization'for Major Emergency 2.2 Waterford 3 SES FSAR, Chapter 16 2.3 Waterford 3 SES Emergency' Plan 2.4 EP-2-070, Protected Area Evacuation 2.5 EP-2-071, Site Evacuation 30 RES PON SIBILITIES The Emergency Coordinator is responsible for the implementation of this procedure. 4.0 INITIATING CONDITIOSIS This procedure shall be initiated whenever an Unusual Event, Alert, Site Emergency or General Emergency is declared due to natural events (e.g., hurricane, flooding or tornado). 5.0 PROCEDURE 5.1 GENERAL l 5.1.1 The Emergency Coordinator shall direct that the station alarm be j sounded, at the end of which an announcement shall be made over the public address system which describes the nature of the emergency and gives a brief description of the hazard and any protective measures to be taken (e.g., site evacuation, sheltering, etc.) 5.1.1.1 Refer to Attachment 7 1 for a list of onsite shelter areas. 2
Emergency Plan Implementing' Procedure EP-2-120 Natural Emergencies Revision 1 5.1.1.2 Refer to EP-2-070, Protected Area Evacuation or EP-2-071, Site Evacuation, as appropriate. '5.1.2 The Emergency Coordinator shall direct that the station alarm be sounded at the end of the above announcement. 5.1.3 The Emergency Coordinator shall direct overnight accommodations to be prepared, as necessary. 5.2 TORNAD0/ HURRICANE 5.2.1 The Emergency Coordinator shall direct the Emergency Communicator to maintain regularly scheduled communications with St. Charles Parish Emergency Operations Center (EOC) in order to obtain the latest status of meteorological conditions as applicable. 5.2.2 When sufficient time and manpower are available, the Emergency Coordinator shall direct performance of protective actions for plant equipment and structures in accordance with Administrative Procedure (LATER). 5.2.3 Keep station personnel informed until tornado conditions have abated. 5.3 FLOODING , 5 3.1 If sufficient time exists, the Emergency Coordinator shall direct Security to maintain a flood watch, as required, and: 5.3.1.1 Direct communications to be established between flood watch and Control Room. 5 3 1.2 Direct communications to be established and maintained with U.S. Army Corps of Engineers, in order to obtain periodic status of river levee. 5.3 2 If flooding occurs, the Emergency Coordinator shall direct the following: 5.3.2.1 Verify storm and flood doors, below flood level, in the Nuclear Plant Islant Structure are closed. 3
Emergency Plan Implementing Procedure EP-2-120 Natural Emergencies Revision 1 5.3.2.2 Inspect below grade levels of the Nuclear Plant Islant Structure for leakage. 5.3.2.3 Direct Emergency Communicator to arrange transportation (rail, boat, helicopter) for shift change, as necessary. 5.3.2.4 Coordinate procedure implementation with Emergency Operations Procedures (LATER). 5.4 EARTHQUAKE 5.4.1 The Emergency Coordinator shall direct that the seismic monitoring system be activated to record aftershocks. 5.4.2 The Emergency coordinator shall direct visual inspection of the plant and site with particular attention paid to safety systems, yard tanks, transformers and intake structures. 6.0 FI?lAL CONDITIONS 6.1 Natural event declared over by the Emergency Coordinator 6.2 Recovery organization established 7.0 ATTACHMENTS 7.1 List of Structurally Safe Areas to Shelter Onsite Personnel (LATER) 1 4
LIST OF STRUCTUALLY SAFE AREAS , / TO SHELTER ONSITE ?ERSONNEL i ( , 4
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WATERFORD 3 SES PLANT OPERATING MANDAL 1 N Louisiama POWER & LIGHT mann EP-2-130 POM VOLUME 18 REVISION 1 POM SECTION 2 APPROVAL DATE: EFFECTIVE DATE: EMERGENCY PLAN IMPLDIENTING PROCEDURE EMERGENCY TEAM ASSIGNMENTS ! k?h W-3 RECCRCS l CON TRO:_ _ED COPY l NO. Ab Y l PORC Meeting No. Y3 -04 8 Reviewed: k bk ,, ORC Chairman j Approved: M A.w Plant Manager-Nuclear
WATERFORD 3 SES
*S PLANT OPERATIN'G MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 'N' ' '0' / 5U Titl e cJ -/' u!' b:v *b ' 7 70 ~h' f
Effective Date (if different 'from PM-N approval date) CMelete 1. B. er C A. Change No. N/4 S. Revision No. I C. Deletion n/4 DetSON*COR CM1MGE. REVISION. OR DELETION 0 / / /c ,-/ dlts. % , k///c #n - ) .4-ks- h?4/;,; -A /y,'+ i.i,c-d - - --
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7 i -t ,/ REQUT9ED STGNATURes Originator O ble#4Et - - Date I I-I N1-- --- Technical Review -- d& 4
-- Date 'lI'lb ft-- -- -
SAFETY EVALUATION
,- Does this change, revision,' or deletion: YES NO
*1. Change the facility as described in the FSAR?
~
u Change the procedures as described in the FSAR? 'o 2. Conduct tests / experiments'not described in the FSAR? 3. 4 Create a condition or conduct an operation which ex-ceeds, 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 Safet- Evaluation checklist. Safety Evaluation bb O- -- - Date_.A b - Group /Dep't. HeadRevYew S N Nfsk -- Date N-Ibfr't- -
" t (NOS)
Temporary Approvala -- -- - -- Date
- Temporary Approvala
--- Date - -
QC Revieu d W Or - ' - ----*-- Date - }~/3~/2- --- PORC Review Ilv bbk Da te ' I - I 9 -' $3 - - - - Mee ti n g No . ff G # - -- PlantManageh-NuclearApprbval EN hD-~ Da te - $ / d3 -
- Temporary approval must be followed by Plant Manager-Nuclear approval l
within 14 days. l UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing' Procedure EP-2-130 Emergency Team Assignments Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RES PONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL' CONDITIONS 7.0 ATTACHMENTS 7.1 Emergency Team Selection Sheet (1 page) 7.2 Task Implementation Sheet (5 pages) LIST OF EFFECTIVE PAGES Title Revision 1 1-9 Revision 1 l l i
Emergency Plan Implementing Procedure EP-2-130 Emergency Team Assignments Revision 1 1.0 PURPOSE This procedure provides guidance for the Emergency Coordinator in the formation of the Emergency Teams and their "back-up" provisions.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-081, Search and Rescue 2.3 EP-2-140, Reentry 2.4 EP-2-010, Notifications and Communications 2.5 EP-3-050, E=ergency Response Call List 3.0 RES PONSIBILITIES The Emergency Coordinator is responsible for the implementation of this procedure. 4.0 INITIATING CONDITIONS 4.1 This procedure shall be initiated upon any of the following conditions: 4.1.1 Declaration of Unusual Event, Alert, Site Emergency, or General l Emergency. 4.1.2 As directed by the Emergency Coordinator. 5.0 PROCEDURE 5.1 Upon declaration of an emergency, the Emergency Coordinator shall assess what manpower and resources will be necessary. 5.2 The Emergency Coordinator shall refer to Attachment 7 1 and select the appropriate response team to be utilized.
! 5.2.1 Attachment 7.1, Emergency Team Selection Sheet, lists the availa-ble emergency response teams and references Attachment 7.2, which describes the correct assembly of that team.
2 1
Emergency. Plan Implementing Procedure EP-2-130 Emergency Team Assignments Revision 1 5.3 Upon selecting the appropriate team, refer to the referenced page of the attachment. 5.3.1 The referenced page of the attachment will provide the necessary information for activating the teams. 6.0 FINAL CONDITIONS The necessary teams have been assessed and utilized. 7.0 ATTACMMENTS 7.1 Emergency Team selection Sheet 7.1 Task Implementation Sheet 3
EMERGENCY TEAM SELECTION SHEET TEAM ATTACHMENT 4 Medical Emergency - First Aid Team 7.2, p.5 Maintenance - Emergency Repair / Operations Team 7.2, p.6 Search and Rescue Team 7.2, p.7 Fire Fighting - Fire Team 7.2, p.8 Field Monitoring Team 7.2, p.9 i f I i EP-2-130 Revision 1 4 Attachment 7.1 (1 of 1)
TASK IMPLEMENTATION SHEET MEDICAL EMERGENCY Imolementine Procedures FP-2-200, First Aid and Medical Care EP-2-031, In-Plant Radiological Controls During Emergencies EP-2-032, Monitoring and Decontamination EP-3-010, Emergency Plan Training EP-3-040, Emergency Equipment Inventory Available Hosottals Telechone Ochsner Clinic, Alton Ochsner Medical Foundation 818-an60 West Jefferson General Hospital 1 504 147 9611 St. Charles Hospital 786 6242 Ambuisnee Service St. Charles Ambulance Service LATER West Jefferson Air Care Helicopter 1 800 182-4006 First Aid Team Assembiv During normal working hours, the First Aid Team will consist of various site personnel. Call for the team to be assembled over the public address system. After normal working hours, utilize on-shift Health Physics and/or Radiochemistry technicians; both have received "First Responder" first aid training. Locations of First Aid Kits are found in procedure EP-2-081. EP-2-130 Revision 1 5 Attachment 7.2 (I of6~') i ____ _ _.
J TASK IMPLEMENTATION SHEET EMERGENCY MAINTENANCE OF PLANT FACILITIES Imolementing Procedures EP-2-031, In-Plant Radiological Controls During Emergencies EP-2-140, Reentry Recair Ocerations Team Assembiv Direct Operational Support Center (OSC) Supervisor to establish an Emergency Repair / Operations Team in accordance with EP-2-140, Reentry. The OSC Supervisor will draw from station Maintenance personnel that have mustered in the OSC in response to the emergency. 7 Mechanical 6 I&C 4 Electrical 6 Computer 12 H.P. (6-30 min.) Additional Engineering staff may be available in the Technical Suport Center (TSC). If necessary, direct additional call-outs to be made. If a protected area evacuation has occurred (Site Emergency), personnel will be available at assembly areas (contact via Security). i i l l l l l l l t EP-2-130 Revision 1 6 Attachment 7.2 (d of 5l
TASK IMPLEMENTATION SHEET SEARCH AND RESCUE ONSITE Imolementine Procedures EP-2-031, In-Plant Radiological Controls During Emergencies EP-2-081, Search and Rescue Team Assembly Direct the OSC Supervisor to establish an emergancy Search and Rescue Team in accordance with EP-2-081. Search and Rescue Teams should consist of volunteers from Operations, Maintenance, Radiological Controls, and/or Security. Select members from personnel who have assembled in the OSC in response to the emergency. 7 Mechanical 6 I&C 4 Electrical 6 Computer 12' Health Physics (6, 30 min.) Additional personnel available: Direct the TSC Supervisor to perform further call-outs. If a protected area evacuation has occurred, personnel will be available in assembly areas. Contact the Shift Security Supervisor to request personnel from Security. EP-2-130 Revision 1 7 Attachment 7 2 (j of f')
TASK IMPLEMENTATION SHEET FIRE FIGHTING Imolementine Procedures FP-1-010, Fire Emergency Procedure EP-2-110, Man-Caused Emergencies PS-11-103, Vehicle Access Fire Deoartments Telechone Offsite Fire Company - (St. Charles Emergency Operations Center or 789-6266 Industrial Hotline) Fire Team Assembiv Prior to the activation of the OSC, the NOS-SS will direct the Fire Team to assemble and perform fire-fighting tasks. After the activation of the OSC, the OSC Supervisor will direct Fire Team activities. The Fire Team consists of various on-shift personnel. Back-up to the Fire Team is offsite assistance. ENSURE SECURITY IS NOTIFIED IF THE FIRE DEPARTMENT IS CALLED TO ENSURE EXPEDITIOUS ENTRY OF VEHICLES AND PERSONNEL. Requests for the offsite fire company will be generated only through the St. Charles Industrial Hotline. EP-2-130 Revision 1 8 Attachment 7.2 ( Y of 5')
TASK IMPLEMENTATION SHEET FIELD MONITORING Imolementine Procedures EP-2-060, Radiological Field Monitoring Emergency Field Monitoring Team Assembiv The Emergency Coordinator or the Health Physics Coordinator may direct that EP-2-060 be implemented. The assignment of personnel to Radiation Field Monitoring Teams shall be made by the Radiological Controls Coordinator (located in the OSC). He shall select at least two individuals, one of whom shall be qualified in the operation of the field monitoring equipment. If a vehicle is used, one of the individuals must be qualified to operate the vehicle. Personnel Available 7 Mechanical 12 Health Physics (6, 30 min.) 4 Electrical 6 I&C 6 Computer Additional personnel: Direct the TSC Supervisor to perform further call-outs. If a Site Emergency has been declared, personnel will also be available from assembly areas. (Protected area evacuation is in process or has occurred.) EP-2-130 Revision 1 9 Attachment 7 2 (5'off )
A !
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WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA MtCOLE SOUTH UTiUT;ES SYSTEM EP-2-140 POM VOLUME 18 REVISION 1 PCM SECTION 2 APPROVAL DATE: EFFECTIVE DATE:
'DIERGENCY PLAN I!!PLE!!ENTI::G PROCEDURE REENTRY LP&L W-3 RECORDS i CONTRO!_'_ED COPY NO. AY PORC Meeting No, f3 G d i f
Reviewed: k hv_ {fRCChairman Approved: \ b u. Plant Manager-Nuclear
WATERFORD 3 SES
N PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST 1
Procedure No. O-/ Title - O ' tn'/ - " - - - - - - - - - - - - Effective Date (if different'from PM-N approval date) Camniete 1. B. or C A. Change No. Hl.4
- 3. Revision No. /
C. Deletion n/> MEASON' TOR CM1NGE. REVISION. OR DELETION Y / b su. (Asn4j ////h se d kh- ,Shr/'sb 2fr'b:3ik - -- Nt /il b "u. - tltn l6l h , ~ ;-h y ll U //c -- Q - ~ ' h - A A- -- -- -~
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Technical Review -o M -
~ ~~ Date ll-19' @ - -
n SAFETY EVALUATION f Does this change, revision, or deletion: YES NO
*1. Change the facility as described in the FSAR? Ls
- 2. Change the procedures as described in the FSAR?
3.
~~
Conduct tests / experiments not described in the FSAR7 4 Create a condition or conduct an operation which ex- " ceeds, 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 d - -- - Date O M ' - Group /Dep't. HeadReviNw Mh v s Date II'l7- N -- Temporary Approva18 -- ~~ ~ ~~ Date - (NOS) Temporary Approval * - - - Date - - QC Revieu A W * - ' -
----~~Date- I~/'J~ M ~~~-
PORC Review b b N Date I - M - f 3' - - Meeting No. fd" W - ~ PlantManage-NuclearApprbal b Odd --'- Da te ?L I SV
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' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
30 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 1 1-6 Revision 1 I i i 1 I
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 1.0 PURPOSE This procedure provides both specific steps to be followed, and guidance to be considered, prior to and during the reentry of an evacuated area for the purposes of emergency repair to systems and equipment or investigative assessment of abnormal plant conditions. NOTE The scope of this procedure does not include reentry into affected areas offsite. State and local agencies will coordinate any offsite recovery effort required following a Site or General Emer-gency in which evacuation was implemented as a protective action.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-030, Emergency Radiation Exposure Guidelines and Controls 23 EP-2-031, In-Plant Radiological Controls During Emergencies 2.4 EP-2-032, Monitoring and Decontamination 2.5 EP-2-033, Administration of Iodine Blocking Agents 2.6 EP-2-070, Protected Area Evacuation l 2.7 EP-2-071, Site Evacuation 2.8 EP-2-101, Operational Support Center (OSC) Activation, Operation, , and Deactivation l 2.9 EP-2-130, Emergency Team Assignments 2.10 EP-2-170, Recovery l I l 2
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 30 RES PON SIBILITIES The Operational Support Center (OSC) Supervisor is responsible for implementing this procedure. 4.0 INITIATING CONDITIONS 4.1 This procedure is to be initiated upon any of the following conditions: 4.1.1 Conditions that require entry into an area classified as
" evacuated" according to EP-2-070, Protected Area Evacuation, or EP-2-071, Site Evacuation.
4.1.2 As directed by the Emergency Coordinator. 5.0 PR0cEDURE 5.1 Assess the need for reentry.and whether the benefits to be gained offset the potential hazards to the reentry personnel. 5.1.1 Utilize all available data including area and process monitor readings, survey data, and personnel observations to determine: 5.1.1.1 Which plant area (s) is (are) affected. 5.1.1.2 The conditions in the area, such as personnel hazards, temperature, toxic environment, and equipment condition. i l 5 1.1.3 Whether or not there are personnel in the area (s) who need i assistance. l 5.1.1.4 The time schedule, based on necessity, for reentry to commence. l i 5.1.2 Isolate and post areas determined to be unsafe or unnecessary to be reentered with appropriate warning signs and rope barriers (e.g., contaminated or high radiation areas). I l l l l 3 t
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 5.2 Pre-plan reentry activities, including:
- 5.2.1 Protective clothing and survey equipment requirements.
5.2.2 shielding and access control requirements. 5.2 3 Anticipated hazard protection and communications requirements. 5.3 Establish reentry teams from personnel available in the Operational Support Center, Control Room, or other assembly areas. 5.3.1 The OSC supervisor should assign a team leader and communicator (as required). 5.3.2 The team members should be briefed on the plan of action and if radiological hazards are present, the Radiological Controls Coordinator shall conduct a briefing in accordance with EP-2-031, In-Plant Radiological Controls During Emergencies. Attachment 73 of EP-2-101 should be used to document the briefing. 5 3.3 The team members should complete an emergency exposure authoriza-tion form in accordance with EP-2-030, Emergency Radiation Ex-posure Guidelines and Controls, if high radiation levels are expected. 5.4 Ensure that personnel making the reentry are qualified for first aid, plant operations, health physics, and/or maintenance evaluations and corrective actions as necessary for the specific j reentry evolution taking place. 5.5 For safety purposes, ensure that each reentry team is composed of at ! least two individuals. l l l 4
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 5.6 For radiologically affected areas, the guidelines of EP-2-031, In-Plant Radiological Controls During Emergencies, should be followed with specific emphasis on control of expo'sure, including: 5.6.1 Assigning an individual as a control point to time personnel entry and to maintain a record of all entries into the affected area using Attachment 7.3 of EP-2-101. 5.6.2 -Ensuring that reentry personnel frequently check direct-reading dosimeters and withdraw to a safe area if assigned exposure limits are approached. 5.6.3 Directing reentry personnel to monitor radiation levels and take periodic air samples along the reentry route and subsequently post radiation and/or contaminated area signs. 5.6.4 Administering thyroid prophylaxis according to EP-2-033, Administration of Iodine Blocking Agents, if high levels of radioactive iodine are encountered. 5.7 For environmentally or structurally affected areas (i.e., steam leak, smoke, flooding, earthquake damage, toxic atmosphere, etc.), ensure that appropriate measures are taken for personnel safety, including: 5.7.1 Reducing potential hazards to reentry personnel, if possible, by actions such as ventilation purge or the securing of systems. 5.7.2 Outfitting personnel with appropriate emergency equipment, such as self-contained breathing apparatus, steam suits, flashlights, tow lines, special tools and communications devices as required. 5.7.3 Testing the equipment for operability prior to reentry. l 574 Directing reentry personnel to withdraw to a predetermined " safe area" if severe unanticipated or unplanned conditions are encountered, pending further evaluation of the reentry effort. 5 i L
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 5.8 Ensure that the OSC maintains a current status board on reentry team operations and that reentry personnel log out of the OSC prior to departing on assigned reentry activities. 5.9 Ensure that the reentry team leader maintains continuous com-munications with the OSC Supervisor, if possible, or otherwise at predetermined intervals to report progress of the reentry and observed conditions. 5.10 Coordinate the return of the reentry team to the control point. 5.10.1 Implement EP-2-032, Monitoring and Decontamination, if required. 5.10.2 Debrief team members at the OSC using Attachment 7.2 of EP-2-101. If radiological hazards were present, the Radiological Controls Coordinator should also conduct a debriefing in ac-cordance with Attachment 7.3 of EP-2-101. 5.10.3 Report the results and findings of the reentry to the Emergency Coordinator. 5 11 Determine the need for additional reentries and, if required, for the initiation of recovery operations in accordance with EP-2-170, j Recovery. l 6.0 FINAL CONDITIONS 6.1 Reentry operations have been completed and all reentry team members have been accounted for. l 6.2 Debriefing of reentry team members has been completed and documented. 7.0 ATTACHMENTS NONE l 6 l
WATERFORD 3 SES PLANT OPERATING MANUAL SM
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$$hkbsvSNM EP-2-130 POM VOLUME 18 REVISION 1 POM SECTICN 2 APPROVAL DATE: _
EFFECTIVE DATE: EMERGENCY PLAN DIPLEMENTING PROCEDURE DIERGENCY RECORDS LPSL W-3 RECORDS CONTROLLED COPY
. si PORC Meeting No. 13 - O !
Reviewed: kk 1 Pi{RCChairman , App roved : %d M Plant Manager-Nuclear
WATERFORD 3 SES & PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. t - W- Title -bo 'h W'-
't 7'f "? f-~---~-
Effective Date (if different from PM-N approval date) Camolete 1. B. o r- C A. Change No. Nh B. Revision No. I C. Deletion n/>
*4r A SON: FO R CMANCE. WEVISION. OR DELETION ht A/f wm / e/n %_, ,$//h ,ki: n/-b 7b~- sh>c8$, 4-/4>h,-r - --
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Date b bh-- ---- Technical Review -- b a@ vb@ - - s
- Date'- M-l@ f'L - --
SAFETY EVALUATION , Does this change, revision, or deletion: YES NO f -s
- 1. Change the facility as described in the FSAR?
h v
- 2. Change the procedures as described in the FSAR?
Conduct tests / experiments not described in the FSAR? 3. u
- 4. Create a condition or conduct an operation which ex-ceeds, 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 b Y bM - -- - Date I N 9'3 ' - Group /Dep't. HeadReYiew bb4 ' Date ll 'I T'C' - t Temporary Approval *
~~ -
- -- Date -
(N]S) D a t e _.- Temporary Approval
- QC Revieu A W N a N P - - -------
Date - -l--/3-1 3 ----- PORC Review M b-<- bb Date f 'I 'I -I S' - - ~ Me e ti n g No . -fM's 8 - - Plant ManagerfNuclear Apprgval T4 WM --~ - Date 1ON U ----
- Temporary approval must be follcwed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5.1 Communications Logs 5.2 Emergency Response Facility Logs 5.3 Supporting Records 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Communications Log (1 page) 7.2 Facility Log Sheet (1 page) LIST OF EFFECTIVE PAGES i Title Revision 1 1-7 Revision 1 l 1
Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 1.0 PURPOSE This procedure outlines the logs / records to be maintained during an emergency and provides guidance on their final disposition. 2'.0 REFERENCES 2.1 Waterford 3 SES Emergency Plan 2.2 UNT-4-006, Control of Plant Documents and Records 2.3 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.4 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation 2.5 EP-2-102, Emergency Operations Facility (EOF) Activation, Operation, and Deactivation 3.0 RESPONSIBILITIES 3.1 The Emergency Coordinator and EOF Director are responsible for ensuring that the maintenance and updating of the facility logs and forms outlined in this procedure are carried out. 4.0 INITIATING CONDITIONS 4.1 This procedure is to be initiated upon any of the following ( conditions: 4.1.1 At the direction of the Emergency Coordinator and/or EOF Director. 4.1.2 Declaration of any of the following emergency conditions: 4.1.2.1 Unusual Event 4.1.2.2 Alert 4.1.2.3 Site Emergency l 2
Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 4.1.2.4 General Emergency 5.0 PROCEDURE 5.1 COMMUNICATIONS LOGS 5.1.1 Log all information transmitted or received on the Communications Log sheets (Attachment 7.1) as indica ted. 5.2 EMERGENCY RESPONSE FACILITY LOGS NOTE Each emergency response facility activated in response to an emergency must maintain an accounting of actions undertaken within the facility during its operation. 5.2.1 Initiate a log for the facility at the time of facility activation. The log shall consist of Facility Log Sheets (see At-tachment 7 2). 5.2.2 Record information on Facility Log Sheets as it becomes available. Information shall include, as a minimum: 5.2.2.1 Time and date, shift, check block of facility, enter page numbers, person manning the position (Supervisor), Log Keeper (sign name). . i 5.2.2.2 Names of personnel assuming staff positions in the emergency response facility. 5.2.2.3 Plant status at the time of emergency declaration. 5.2.2.4 Major steps taken under the direction of the facility staff, j including time and date these actions were initiated and the individual who directed the actions be taken. l 3
Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 5.2.2.5 Important data received (e.g., change in plant status, results of radiological surveys). 5.2.2.6 Summation of any formal meetings conducted in relation to the emergency. 5.2.2.7 Recommendations given to or received from non-LP&L personnel providing support to the emergency facility. 5.2.2.8 Final emergency resolutions and summation of emergency facility actions in relation to the emergency facility's deactivation, including time and date of deactivation. 5.3 SUPPORTING RECORDS 5.3.1 For documents that are generated during the operation of the emergency facilities (e.g., Field Survey Results, Administration of Potassium Iodine Log), include the following information as a minimum: 5 3.1.1 Time, date and author.
'5.3.1.2 Location in which document was generated (e.g., dose assessment area, technical assessment area).
6.0 FINAL CONDITIONS l l 6.1 DISPOSITION OF LOGS AND RECORDS l-L 6.1.1 Collect all records and logs generated in the operation of the l emergency facility after each drill, exercise, or emergency situation, etc. I 6.1.2 Make copies of the collected records and forward the copies to the Emergency Planning Coordinator for review. 6.1.3 Handle all records and logs in accordance with UNT-4-006. 4
Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 7.0 ATTACHMENTS 7.1 Communications Log 7.2 Facility Log Sheet 5
e AaE NR. COMMUNICATIONS LOG l I TIME SENT TIME RECEIVED DATE
- 00'JuuNaCATION ct~CUIT USED MESSAGE TO MESSAGE FROM MESSAar l
l -. TMANSMITT ED/ AUTMCRIZED SY I A ECElvt SY DATE & TIME f RECEIVED l .Y/ACTICN TAKEN l
* * ' ' THIS COPY FOR COMMUNICATCR/ACTICN
~.
EP-2-150 Revision 1 6 Attachment 7.1 (1 of 1) wa . . em
FACILITY LOG SHEET DATE: ECC D EOF 0 Page of TIME: TSC C Supervisor: SHIFT: OSC Log Keeper: Time Event Description I i I I I ! I I I I I I I I 1 I
~
I l l l -. _ I I I b L l l l i E?-2-150 Revision 1 7 Attachment 7.2 (1 of 1-)
WATERFORD 3 SES __.
-- am-PLANT OPERATING MANUAL ! '.a -)
b mug s i l O POWERl DUISIANA mamamme m & LIGHT - MICOt.E SCUTH UT'UT'E3 SYSTEM EP-2-170 PCM VOLL?.E 19 REVISION 9 FCM SEC* ION 2 APPROVAL DATE: Mav 2, 19 83 EFFECTIVE DATE: Fuel Loaa DIERGENCY PLAN IMPLEMENTING PRCCEDURE RECOVERY OPERATION LpSL W- 3 RECC" i _, u ., i - CON,ihw l COPY g, f I PORC Meeting No. 73 -s N Reviewed: /, 24a .
~
P0KC Chai~an l Approved: '
? fv 'M' l Plant Manager-Nuclear i
l
o . WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST OM Procedure No. G/'-2-#7o Title Effective Date P J L M (if different frca approval date) th elsta 1. B. er C A. Change No. JA B. Revision No. A C. Deletion ~/A WF1 MON FOR cMAMar_ METTRTON. OR DELETTOM T lm 0 kmul A G m2 s a ee, ~ac p . ..o MEOUTRED STOVATUWFR Originator Ie W Date 4 '/ Technical Review O N ntauv Date e g . 3AFETT EVALUATION , Does this change, revision, or deletion: TES NO
- 1. Change the facility as described in the FSAR? /
- 2. Change the procedures as described in the FSAR7-
- 3. Conduct tests / experiments not d,escribed 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-tach a 10 CFR 50.59 Safe y Evaluation checklist. Safety Evaluation k Date N-I Y'O Group /Dep't. Head Review Ck O b t h Date U ' /4'O S Temporary Approval
- Date (NO3)
Temporary Approvale Date l QC Review / #A OfYW Date d-28-9% l PORC Review I I A >e Y e Date ' 4MG Meeting No. FF'74 PlantNana{erlhuolearApproval
- Nl2 9 Date sh wM eTemporary 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
. _ _ _ _ . - , . - _ _ - _ _r_,_- - ,- - - - -
Emergency Plan Implementing Procedure EP-2-170 Recovery Operation Revision 2 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RES PONSIBILITIES .
' i 4.0 INITIATING CONDITIONS l
(~ ^~ 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS LIST OF EFFECTIVE'PAGES .f~ Title Revision 2 , 1-8 Revision 2 I O i 1
Emergency Plan Implementing Procedure EP-2-170
~-
Recovery Operation Revision 2 1.0 PURPOSE This procedure provides criteria and guidance for terminating a declared emergency condition and restoring the station as close as possible to its preemergency status. The termination of an emergency and recovery efforts will depend on the nature of the emergency and the status of plant systems following corrective measures. Although the general provisions within this procedure are expected to be applicable to all emergencies, it may be necessary to supplement this guidance with provisions specific to the emergency at hand. In particular, actual recovery procedures shall be formulated and approved by the Plant Operation Review Committee (PORC) prior to implementation of recovery efforts. ;
2.0 REFERENCES
l . 2.1 W3 SES Emergency Preparedness Plan and Implementing Procecures 2.2 Title 10, CFR Parts 20 and 50 j 2.3 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plan and Preparedness in Support of Nuclear Power Plants 3.0 RES PONSIBILITIES 3.1 The Emergency Coordinator, in conjunction with the Emergency Operational Facility (EOF) Recovery Director for Site Area o,r j General Emergencies, will make the determination of when an emergency condition is resolved in accordance with the above criteria and may declare the termination of the emergency. . 3.2 For any emergency condition involving plant systems and/or a plant shutdown, the Emergency Coordinator will make a determination as to when it is safe to return the plant to a normal operating mode. 3.3 Nuclear Project Support Group (NPSG) Licensing will resolve any license or technical specification concerns related to the emergency. 2
Emergency Plan Implementing Procedure EP-2-170 Recovery Operation Revision 2 t 3.4 Recovery Organization 3.4.1 Although the planning for recovery and the extent of the recovery efforts will vary according to the nature of the specific emergency situation, a long-term recovery organization is defined in section 9 of the W3 SES Emergency Preparedness Plan. 3.5 Recovery Operation , i 3.5.1 Recovery activities not covered by existing approved procedures shall be preplanned and approved by PORC prior to their implementation. 3.5.2 Station recovery activities shall be in accordance with the sts- . tion technical specifications and other license conditions. ~ Specifically during recovery operations, the radiation exposure ! limits of 10CFR20 shall apply. Compliance with these limits shall , be the responsibility of the Emergency Coordinator via the Health Physics Coordinator. 3.5.3 Recovery actions that plan for or may result in radioactive releases will be evaluated by the Emergency Coordinator / EOF Recovery Director snd their staffs as far in advance of the event - as possible. Such events and data pertaining to the releases will be reported to the appropriate offsite emergency response organizations and agencies, even if the release is within normal technical specifications, for as long as the recovery oper,ation continues. 3.5.4 The recovery operation will continue until the station is returned to its preemergency status, or as determined by the Vice - President-Nuclear Operations (EOF Recovery Director). 3
. Emergency Plan Implementing Procedure EP-2-170
~~
Recovery Operation Revision 2 4.0 INITIATING CONDITIONS An emergency condition has been declared at Waterford 3 SES. Cor-rective and protective actions have been implemented and control has i been regained over plant systems and/or inadvertent radioactive releases. i 4.1 Progression from Emergency to Termination / Recovery !_ 4.1.1 Actions taken during an emergency situation can be categorized into two general phases: response and recovery. Response actions are the corrective and protective measures taken to mitigate the consequences of the event and to place the emergency under control. Recovery actions are actions of a longer duration taken - to restore the station as nearly as possible to-its preemergency condition. . 4.1.2 The extent and nature of the corrective and protective measures j and the extent of recovery operations will depend on the emergency conditions at hand and the status of station areas and equipment. , i In many emergency situations, the emergency condition may be - resolved without significant plant damage and, thus, the station , can be restored to a normal operational mode without a definitive recovery phase and without extensive outside assistance. In the event of more extensive damage, a long-term recovery may be necessary, and the manpower and resource demand of such a long- , I , term recovery will require the establishment of a recovery-organization. 4.1.3 At the onset of an emergency condition, response actions to . mitigate the consequences of the accident take precedence over recovery actions. The EC or EOF Recovery Director may initiate 4 some limited recovery operations during the response phase. Gradually, as the response effort begins to abate, recovery ef-forts gain more importance. Finally, a point is reached where the emergency situation has decreased to the extent that it can be considered, for all practical purposes, to be resolved. At this 4
Emergency Plen Implementing Proccduro EP-2-170
~~
Recovery Operation Revision 2 point, the emergency can be declared to be terminated, and a recovery organization is implemented if necessary. 4.1.4 If, following its termination, the emergency situation recurs, the Emergency Coordinator and EOF Recovery Director will reactivate the onsite emergency organizations and, if necessary, the offsite i emergency organizations. Recovery efforts will be suspended until
~
the EC and EOF / Recovery Director allow them to resume. 4.2 Termination Criteria An emergency condition can be considered resolved,'and a recovery organization established (if necessary), when the following guidelines have been met: 4.2.1 In-plant radiation levels are stable or are cecreasing below ac-ceptable levels with time. l 4.2.2 The release of radioactive material to the environment is under control or has ceased, and the potential for additional ! uncontrolled releases has decreased to an acceptable level. 4.2.3 Any fire, flooding, earthquake or similar initiating events are , under control or have ceased. 4.2.4 The plant is in a stable configuration. 4.2.5 For contaminated / injured personnel, when the victim (s) has (have) , been transferred to a hospital, or has (have) received appropriate I medical treatment 4.2.6 For emergency conditions classified as Unusual Events, when the specified corrective action has been taken, or when the plant has been placed in the appropriate operating mode (related EAL's), and when notifications are complete 5
Emergoney Plan Impicmsnting Procsduro EP-2-170
~~ . Recovery Operation Revision 2 5.0 PROCEDURE -
When it has been determined that the emergency condition has been resolved, the following shall be performed as applicable, and as directed by the EC and EOF Recovery Director: , 5.1 The offsite organizations shall be notified that the emergency condition at the station has been resolved and that onsite emergency I, operations will be terminated. If a recovery organization is being established, this should be included in the notification. NOTE For Unusual Events in which the emergency is - resolved prior to the initial notification, an - appropriate phrase should be added to the ,, notification to the effect that the emergency condition has been resolved. 5.2 LP&L Information Director should be notified to make a press release on the termination of the emergency (and the start of recovery , efforts). 5.3 Any emergency radiation exposure limits shall be terminated and normal radiation control measures reestablished. 5.4 Any procedural waivers instituted during the emergency should be terminated or formally documented by procedure changes. l 5.5 Emergency organization personnel should be directed to assemble all - ? l documents generated during the emergency and to submit them to the Emergency Planning Coordinator. 5.6 Any equipment used during the emergency shall be serviced, as l necessary, and returned to designated storage locations. Any l damaged or def ective equipment shall be brought to the attention of irdividuals responsible for its maintenance. Consumable materials 6
Emergency Plan Implementing Procedure EP-2-170 Recovery Operation Revision 2 (i.e., procedure forms, bags, etc.) shall be restocked as soon as possible. 5.7 If a long-term recovery operation is indicated, a recovery organization will be established in accordance with the LP&L Emergency Preparedness Plan (EPP). l 5.8 If applicable, the EPP should be evaluated to ensure that an ! adequate emergency preparedness status can be maintained in light of the degraded plant conditions (i.e., inaccessibility of evacuation assembly areas, inoperative emergency instrumentation and equipment as it relates to the EPP) and appropriate corrective measures . . implemented. 5.9 For an Alert and higher emergency conditions, the Emergency - Coordinator, with the assistance of the TSC staff, will prepare a , report of the emergency and submit this report to PORC. For Unusual ' Events, the Licensee Event Report (LER) satisfies this requirement. l 5.10 The PORC will review the Emergency Coordinator's report and will e evaluate and assign responsibilities.for corrective actions. This report will be submitted to PORC for review and submission to the , NRC as per section 6, Administrative Section, of the W3 SES Technical Specifications. 5.11 The PORC shall review / approve procedures for station recovery that include as applicable: , i 5.11.1 Procedures for decontamination l l 5.11.2 Procedures for repair 5.11.3 Recommendations for special inspections and tests that must be ( performed to assure the integrity of the plant and adequacy of ! the repairs 5.11.4 Radioactive waste processing and handling procedures 7 l l i
Emergency Plan Impicncnting Procsdure EP-2-170 Recovery Operation Revision 2 5.11.5 An estimate of the radiation exposure that will be accumulated by personnel in executing these procedures -7 5.11.6 Exposure reduction methods (ALARA) to minimize the projected ex-posure of personnel i 5.12 The Emergency Planning Coordinator should review the various reports on the emergency to identify deficiencies in the Emergency Preparedness Plan and the implementing procedures, if any, and should initiate appropriate corrective action, if necessary, as soon as possible. . 6.0 FINAL CONDITIONS j. 6.1 All systems have been restored to a normal condition. , 7.0 ATTACHMENTS t NONE l D f 8 L
WATERFORD 3 SES _ PLANT OPERATING MANUAL
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" Louisiama POWER & LIGHT '
N N SYS EP 190 PCM VOLL7.E ia , ggyIstog , POM SECTION , APPROVAL DATE: May 2, 1983 EFTECTIVE DATE: Fuel Load EMEROCICY PLA'i DIPLDIENTING PROCEDL"RE PERSONNEL ACCOL'NTN5ILITY LP&L W-3 F ' C O ql,73F*. .t"i;
- [ i
II 1:,/ r La, - COP'/
- h. NO. j.
? ORC Meettng No., $'3 -I ')/2 Reviewed: fe %g .
/ FORC Ch irman App roved : h_ %
Plant Manager-l Nuclear
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WATERFORD 3 SES __ PLANT OPERATING MANUAL REVIEW COVER SHEET PROCEDURE NO. 8/2-2 -11 0 TYPE E41fNuw @umu k(Medkm TITLE OM b=#dM q PROCEDURE EFFECTIVE DATE bel Lotto (If different from approval date) AUTHOR b b "*C-TECHNICALRENEW &# U ikw 3- 2J 43 . Signature, Telchnical Reviewer Date PORC REVIEW REQUIRED YES [ NO
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SAFETY EVALUATION Does this procedure:
- 1. Change the facility as described in the FSAR? YES N 0_.'
- 2. Change the procedures as described in the FSAR? YES N0_'_.
- 3. Conduct tests / experiments not described in the YES Nog --
FSAR? 4 Create a condition or conduct an operation YES Nog which exceeds, or could result in exceeding, the limits in Technical Specifications? [ If any question 1 through 4 has been answered YES, complete and at-tach a 10 CFR 50.59 SAFETY EVALUATION. SAFETY EVALUATION Cy[h4 ~3 2.f- % 3 V Sign \ ature Technical Reviewer Date GROUP / DEPARTMENT HEAD REVIEW CN-f cA 3 33 V I Signature Date QC REVIEW A'A dr/b , A - 4 y # J' Da '
< Sign ture, QC Engineer
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# G PORC REVIEW -
' Signature, PORC Chairman ! Date PORC MEETING NO. [ [f5-'M l _ Applicable Conditions (Temporary Procedures Only):
l l . UNT-1-003 Revision 6 Attachment 6.5 (1 of 1) II
Emergency Plan ImplGmenting Procodure EP-2-190 Personnel Accountability Revision 0 TABLE OF CONTENTS 1.0 PURPOSE _,
2.0 REFERENCES
13 . 0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS
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5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Emergency Response Facility Site Accountability Roster (1 page) 72 Emergency Response Facility Continuous Accountability Roster (1 page) 7.3 Missing Person Roster (1 page) . LIST OF EFFECTIVE PAGES Title Revision 0 1-10 Revision 0 O e 1
Emergency Plan Implementing Procedure EP-2-190 Personnel Accountability ' Revision 0 1.0 PURPOSE This procedure provides a method by which station personnel are ac- . counted for if a Protected Area Evacuation or a Site Area Evacuation
- becomes necessary. Is also provides a procedure to account for all personnel, as they are assigned field duties, on a continuous basis.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-070, Protected Area Evacuation 2.3 EP-2-071, Site Evacuation 2.4 EP-1-030, Site Area Emergency 2.5 EP-1-040, General Emergency - 2.6 EP-2-081, Search and Rescue l 2.7 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.8 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation , 2.9 EP-2-102, Emergency Operations Facility (EOF) Activation, Operation, and Deactivation 2.10 EP-2-130, Emergency Team Assignments I 2.11 NUREG 0654, FEMA, REP-1, Rev. 1 2.12 PS-16-103, Accountability of Personnel During Emergencies 3.0 R ES PONSIB IL ITIE S 31 The Emergency Coordinator is responsible for implementing this procedure. . l 3.2 The TSC Supervisor, OSC Supervisor, EOF Director and the On-Shift I NOS-SS are responsible for providing roster reports to the Security Shift Supervisor. 2
Emergency Plan Impicsonting Procsdure EP-2-190
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Personnel Accountability - Revision 0 3.3 The Security Shift' Supervisor is responsible for assembling all
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personnel accountability information and forwarding the names of
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unaccounted personnel to the Emergency Coordinator. ; 3.4 The OSC Supervisor is responsible for the accountability of all personnel assigned field duties from the OSC on a continuous basis.
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3.5 The NOS-SS is responsible for all On-Shift Operators, Health Physics Technicians, and Chemistry Technicians who are assigned field duties ,, on a continuous basis. 3.6 The TSC Supervisor:is responsible for the accountability of all personnel assigned field duties from the TSC on a continuous basis. 3.7 The EOF Director i.s responsible for the accountability of all , personnel assigned field duties,from 'het EOF on a continuous basis. , 4.0 IMITIATING CONDITIONS , 4.1 Declaration of a Site Area Emergency 4.2 Declaration of a General Emergency 4.3 As directed by the Emergency Coordinator 5.0 PROCEDURE 5.1 INITIAL PERSONNEL ACCOUNTABILITY i 5.1.1 The On-Shif t NOS-SS shall account for all On-Shif t Operators, Health Physics Technicians and Chemistry Technicians by co,mpleting Attachment 7.1, Emergency Response Facility Site Accountability Roster. The NOS-SS shall forward Attachment 7.1 to the Security Shif t Supervisor within 15 minutes of the activation of a Site . Area Emergency or General Emergency. i l i 3 I
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Emergency Plan Impicmsnting Procedure EP-2-190 ._.
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Personnel Accountability Revision 0 r-NOTE If a Site Area Emergency or General Emergency is declared after normal working hours, Attachment 7.2, Emergency Response Facility Continuous Accountability Roster, shall be used to verify that personnel responding to the emergency reach their respective work areas when they enter the ., station. 5.1.2 The TSC Supervisor shall account for all TSC personnel by completing Attachment 7.1, Emergency Response Facility Site Ac-countability Roster. The TSC Supervisor shall forward Attachment 71 to the Security Shift Supervisor within 15 minutes of the activation of a Site Area Emergency or General Emergency. . NOTE If a Site Area Emergency or General Emergency is declared after normal working hours, Attachment 7.2, Emergency Response Facility Continuous , Accountability Roster, shall be used to verify that personnel responding to the emergency reach their respective work areas when they enter the station. 5.1.3 The OSC Supervisor shall account for all OSC personnel by I completing Attachment 7.1, Emergency Response Facility Site Ac-countability Roster. The OSC Supervisor shall forward Attachment 7 .1 to the Security Shif t Supervisor within 15 minutes of a site i Area Emergency or General Emergency. 4
i 4 Emergency Plan ImpicmGnting Proccdure EP-2-190 Personnel Accountability - Revision 0
'n-NOTE
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If a Site Area Emergency or General Emergency is ' declared after normal working hours, Attachment 7.2, Emergency Response Facility Continuous Accountability Roster, shall be used to verify that personnel responding to the emergency reach their respective work areas when they enter the , station. 5.1.4 The EOF Director shall account for all EOF personnel by completing Attachment 7.1, Emergency Response Facility Site Accountability Roster. The EOF Director shall forward Attachment 7 1 to the Security Shift Supervisor within 15 minutes of a Site Area - Emergency or General Emergency. , NOTE If a Site Area Emergency or General Emergency is declared after normal working hours, Attachment 7.2, Emergency Response Facility Continuous , Accountability Roster, shall be used to verify that personnel responding to the emergency reach their respective work areas when they enter the station. l 5.1.5 The Security Shif t Supervisor shall tabulate the rosters from his assembly area, the TSC, OSC, EOF and Control Room and compare it with the personnel on station. Any personnel unaccounted for shall be reported by name and badge number to the Emergency Coordinator no later than 30 minutes after the Site Area Emergency or General Emergency was declared by completing Attachment 7.3, Missing Person Roster. 5
Emergency Plan Impismsnting Proccdure EP-2-190 -_ Personnel Accountability Revision 0 5.1.6 The Emergency Coordinator shall instruct the OSC to send a Search and Rescue team to search for all unaccounted personnel. The 'r Emergency Coordinat'or shall forward the results of all the ac-countability rosters to the EOF Director and the Security Coordinator. 5.1.7 The EOF Director shall forward the results of all the ac-countability rosters to the Emergency Director in the CCC. 5.2 CONTINUOUS PERSONNEL ACCOUNTABILITY 5 . 2 .1 The OSC Supervisor shall account for all personnel sent from the OSC for field assignments with Attachment 7.2, Emergency Response Facility Continuous Accountability Roster. If the listed person-nel do not return or call in at the.specified time, the OSC Supervisor shall notify the Emergency Coordinator (EC), who will direct the OSC Supervisor to dispatch a Search and Rescue team if , deemed necessary. 5.2.2 The NOS-SS shall account for all HP Technicians, Chemistry Technicians and Operators with Attachment 7.2, Emergency Response Facility Continuous Accountability Roster. If the listed person-nel do not return or call in at the specified time, the NOS-SS , shall notify the Emergency Coordinator. The EC will direct the OSC Supervisor to dispatch a Search and Rescue team if deemed necessary. 5.2.3 Security personnel shall account for all Security personne1 end, personnel reporting to the station by completing Attachment 7.2, Emergency Response Facility Continuous Accountability Roster. All incoming personnel will log in with Security and call Security when they reach their destination. If any personnel do not call in by the specified time, Security personnel shall notify the Emergency Coordinator. The EC shall direct the OSC Supervisor to dispatch a Search and Rescue Team if deemed necessary. When reporting personnel arrive at their destination (TSC, OSC, or EOF), continuous accountability responsibilities for that 6
Emergency Plan Implementing Proc dure EP-2-190
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Personnel Accountability Revision 0 individual are transferred frem the Security Department to the cognizant facility. The TSC Supervisor shall account for all personnel in the TSC in
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5.2.4 accordance with Attachment 7.2, Emergency Response Facility Continuous Accountability Roster. If the listed personnel do not return or call in at the specified time, the TSC Supervisor shall notify the EC. The EC will direct the OSC Supervisor to dispatch
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a Search and Rescue team if deemed necessary. 5.2.5 The EOF Director shall account for all personnel in the EOF in ac-cordance with Attachment 7.2, Emergency Response Facility Continuous Accountability Roster. If the listed personnel do not .. return or call in at the specified time, the EOF Director shall notify the EC. The EC will direct the OSC Supervisor to dis, patch a Search and Rescue team if deemed necessary. 6.0 FINAL CONDITIONS This procedure shall be complete when: 6.1 Site Area Emergency accountability is ccmplete. 6.2 General Emergency accountability is complete. , 6.3 The emergency has been declassified to an Alert or less and continuous accountability is complete. 7.0 ATTACHMENTS 7.1 Emergency Response Facility Site Accountability Roster 72 Emergency Response Facility Continuous Accountability Roster 7.3 Missing Person Roster 7
EMERGENCY RESPONSE FACILITY SITE ACCOUNTABILITY ROSTER _ EMERGENCY RESPONSE CENTER DATE: TIME: CONTACT: TELEPHONE
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NAME (Print) BADGE NO. NA>E (Print) BADGE NO. f l
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( l I EP-2-190 Revision 0 8 ATTACHMENT 7.1 (1 of 1) l l --- - - . - - . _ _
EMERGENCY RESPONSE FACILITY CONTINUOUS ACCOUNTABILITY ROSTER _ EMERGENCY RESPONSE CENTER: DATE: TLE: .
-r TUiE CALL TIME EXPECTED IN TLE NAME (Print) BADGE # ASSIGNMENT LOCATION OUT TO RETURN INTERVAL IN ir J
EP-2-190 Revision 0 9 ATTACBMENT 7.2 (1 of 1)
._ _. ___ ,, . _ _ = _ _ _ _ _ - . _ - , _ _ _ - - - __ _ .._ _ _ __ _
l i. I Area:
,. .."* MISSING PERSON ROSTER .
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,.- C Protected Area M Q Administration' Area DAU:
C Construction Area BADGE NO. NAME (Print) BADCE NO. _.. NAME (Prist) l l l
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l l y. \ h oecurity Office (Access Centrol) SECURITT SHIPT SUPERVISOR 10 ATIACHMENT 7.3 (1 of 1) EP-2-190 Revision 0
- . . . ._- WATERFORE:.LSES2 sc=. ... : - PLANT OPERATING MANUAL W LOUISIANA POWER & LIGHT NSNSys$ EP-3-020 PCM VOLUME 14}}