ML022120546
| ML022120546 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/16/2002 |
| From: | Entergy Nuclear Indian Point 3 LLC |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022120546 (70) | |
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L1-JUL- 02 DISTRIBUTION CONTROL LIST Icument Name: EMER PLAN DEPT ]LOCATION CC-NAME NAME
------------------------ 45-3-B UNIT 3 /ADMINISTRATION #48 1 PLANT MANAGER'S OFFICE TRAINING 2 EP/TRAINING ADMINISTRATOR 45-4-A RES DEPARTMENT #48 3 RES DEPARTMENT MANAGER RECORDS (TRNG BLDG) 4 REFERENCE LIBRARY EOF EMERGENCY PLANNING IP3 9 JOINT NEWS CENTER OPERATIONS 10 SHIFT MGR. (LUB-001-GEN) IP3 OPS(3PT-D001-D006 ONLY) EOF 11 CONTROL ROOM & MASTER E-PLAN 14 EOF WPO-12D E-PLAN (EOP'S ONLY) WPO/7A 16 AEOF/A.GROSJEAN WPO DOCUMENT CONTROL 19 NUC ENGINEERING LIBRARY 45-2-B US NRC OFFSITE 22 RESIDENT INSPECTOR NRC 23 MCNAMARA N OFFSITE NRC OFFSITE 24 MCNAMARA N NRC OFFSITE 25 DOCUMENT CONTROL DESK J A FITZPATRICK 28 AVRAKOTOS N EOF E-PLAN 29 E-PLAN STAFF EOF E-PLAN OFFSITE 30 E-PLAN STAFF ST. EMERG. MGMT. OFFICE WESTCHESTR 31 BARANSKI J(VOLUME I ONLY) DISASTER & EMERGENCY I ONLY) ROCKLAND 32 MURPHY L -(VOLUME EMERGENCY SERVICES N (VOLUME I ONLY) ORANGE 33 LONGO DISASTER & CIVIL DEFENSE PUTNAM 34 GREENE D (VOLUME I ONLY) OFFICE OF EMERG MANAGE 35 RAMPOLLA M(VOLUME I ONLY) 48-2-A TRAINING #48 41 SIMULATOR NRQ-OPS / TRAINING #48 319 C.STELLATO LRQ-OPS / TRAINING EOF 354 L.GRANT E-PLAN #48 376 E-PLAN STAFF J. CHIUSANO/TRAINING #48 424 OPS-INSTR (LL'S 1 COPY) LRQ-OPS / TRAINING #48 510 L.GRANT LRQ-OPS / TRAINING #48 511 L.GRANT NRQ-OPS / TRAINING #48 512 C.STELLATO NRQ-OPS / TRAINING 513 C.STELLATO IP2 ADMIN/(IPEC ONLY) UNIT 2 517 PLANT MANAGER'S OFFICE TSC (IPEC ONLY) IP2 518 DOCUMENT ROOM UNIT 2 (IPEC ONLY) 519 TSC IP2 OPERATIONS (IPEC ONLY) 48-2-A 520 CONTROL ROOM (UNIT 2) TRAIN/CENTER (IPEC ONLY) IP2 521 SIMULATOR (UNIT 2) US NRC (IPEC ONLY) OFFSITE 522 NRC RESIDENT (UNIT2) TRAINING LIBRARY 523 ROBERT VOGLE (UNIT 2) IP2 NUC SAFETY/LICENSING 524 JOHN MCCANN (UNIT 2)
Entergy Indian Point 3 AP-18.2 Attachment 1 Revision 10 Page lof 1 CONTROLLED DOCUMENT TRANSMITTAL FORM TO: DISTRIBUTION DATE 7/16/2002 TRANSMITTAL NO: 27055 FROM:IP3 DOCUMENT CONTROL GROUP EXTENSION: 2038 The Document(s) identified below are forwarded for use. In accordance with AP-18.2, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s). Sign and return the receipt acknowledgement below within fifteen (15) working days.
AFFECTED DOCUMENT: E PLAN PROCEDURES: u.%%- 3 DOC # REV # TITLE INSTRUCTIONS
- FOLLOW ATTACHED INSTRUCTIONS****************
- PLEASE NOTE EFFECTIVE DATES**
RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S).
XT AWN U (DDtMT* SIGNATI IRE DATE CC#
TO: Emergency Planning Document Controlled Copy #
FROM: Emergency Planning
SUBJECT:
Emergency Planning Document Update Date: 7/11/02 Please update your controlled copy of the documents listed below as specified with the copy(s) attached.
and Please sign this memo indicating that you have completed the update as specified return to:
Entergy Nuclear Indian Point Nuclear Generating Station Records and Documents Department Broadway & Bleakley Aves.
Buchanan, NY 10511 Attn: Document Custodian New Rev. Old Rev.
- 1Date #/ Date Instructions Document # Document Name Volume II U3 Emergency Response Activation Implementing Procedures TOC Table of Contents 7/11/02 7/02 Replace entire document Initiating Conditions & Emergency 9 8 Replace entire document IC/EALs Action Levels 5 Replace entire document IP-2003 CR Watch Chemist 6 Void 10 Remove entire document IP-2301 Emergency Director EOF Technical Advisor & 10 9 Replace entire document IP-2302 Information Liaison Emergency Activation of the Alternate Emergency Operations Void 6 Remove entire document IP-2400 Facility (AEOF)
Emergency Termination & Void 4 Remove entire document IP-2600 Transition to Recovery Remove entire document IP-2601 Recovery Manager Void Development of Recovery Action Remove entire document IP-2602 Void I Plan 0 Replace entire document Recovery Support Group Manager I II"-LOV-)
lr-LoVJ I I I I
New Rev. Old Rev.
/ Date #1Date Instructions Document # Document Name
________ 4 t Volume I1 U3 Emergency Response Activation Implementing Procedures EP-Forms Index 7/11/02 9/01 Replace entire document Section 2/99 Remove entire document EP- Form 46 EOF Staffing Chart Void 7/02 6/02 Replace entire document Appendix A Rosters 1, 11 I
Volume III New Rev. Old Rev.
- /Date #/Date Rm nstvuctions U3 Emergency Plan Implementing Procedures 7/11/02 5/02 TOC Table of Contents Replace entire document IP-1001 Determining the Magnitude of Void 17 Remove entire document IP- 1001Release Void 18 Remove entire document IP-1003 Obtaining Meteorological Data Void 16 Remove entire document IP-1004 MIDAS Computer System Protective Action Remove entire document Recommendations for the Offsite Void 13 IP-1017 Population Update completed as specified: Signature of Controlled Copy Holder Date
VOLUME II APPENDIX 'A' 07/02 copies This page is being substituted for this Appendix in the NRC Volume II controlled distribution to due to the contents being personal and confidential, and not applicable for the public.
Appendix 'A' of the IP-3 Emergency Plan Volume II contains the following:
ROSTER I IP-3 Notification Telephone Numbers for the mandatory emergency notification/call-in. Includes work extension numbers, private home phone numbers, and individuals' beeper numbers.
DIALOGICS The Dialogic Notification System is the automated telephone communication system which IP-3 uses primarily during off-hours to call in selected emergency response personnel (listed on Rosters I and II).
ROSTER II Emergency Response Personnel Telephone List which includes selected IP-3 employees' private home phone numbers who have been trained in specific emergency responsibilities.
ROSTER III Private home phone numbers of all IP-3 employees listed by department.
Note: Rosters I, and II only have been updated this revision.
TABLE OF VOLUME CONTENTSII 07/11/02 ENTERGY NUCLEAR NORTHEAST INDIAN POINT NO. 3 NUCLEAR POWER PLANT EMERGENCY PLAN - VOLUME II EMERGENCY RESPONSE ACTIVATION TABLE OF CONTENTS REV. # / DATE 9 - 07/02 LEVELS IC/EAL'S INITIATING CONDITIONS AND EMERGENCY ACTION CONTROL ROOM 4 - 09/98 IP-2000 Emergency Activation of the Control Room (CR) 15 - 05/02 IP-2001 Emergency Director (ED), Plant Operations Manager (POM), Shift Manager (SM) Procedure 3 - 02/99 IP-2002 CR Health Physics Technician 6 - 07/02 CR Watch Chemist 3 - 09/00 IP-2003 IP-2004 CR Clerk 2 - 06/01 IP-2005 CR Offsite Communicator 4 - 10/99 IP-2006 CR Direct-Line Communicator TECHNICAL SUPPORT CENTER (TSC) 11/00 4 -
IP-2100 Emergency Activation of the Technical Support Center (TSC) 9 - 02/01 Technical Support Center (TSC) Manager 3 - 12/98 IP-2101 TSC Communicator(s) 4 - 08/99 IP-2102 TSC SPDS Computer Operator 2 - 06/01 IP-2103 TSC Video Operator VOID - N/A IP-2104 TSC Accountability Officer 5 - 06/99 IP-2105 IP-2106 TSC Clerk OPERATIONS SUPPORT CENTER (OSC) 6 - 11/00 IP-2200 Emergency Activation of the Operations Support Center (OSC) 82 02/01 12/98 IP-2201 Operations Support Center (OSC) Manager 3 07/02 IP-2202 OSC Direct-Line Communicator 3 06/02 IP-2203 OSC Dispatcher OSC Team Leaders 8 10/99 IP-2204 OSC H.P. Team Leader VOID N/A IP-2205 OSC Accountability Officer 5 06/99 IP-2206 OSC Clerk 4 03/02 IP-2207 4 12/97 IP-2208 OSC Security Team Leader OSC H.P. Technician 3 06/98 IP-2209 OSC Dosimetry Technician 2 03/00 IP-2210 TP-2211 OSC Chemistry Team Leader
TABLE OF VOLUME CONTENTSII 07/11/02 ENTERGY NUCLEAR NORTHEAST INDIAN POINT NO. 3 NUCLEAR POWER PLANT EMERGENCY PLAN - VOLUME II EMERGENCY RESPONSE ACTIVATION TABLE OF CONTENTS REV. # / DATE EMERGENCY OPERATIONS FACILITY (EOF) 5 - 11/00 IP-2300 Emergency Activation of the Emergency Operations Facility (EOF) VOID - N/A IP-2301 Emergency Director Replaced by IP-EP-255 10 07/02 11/00 IP-2302 EOF Technical Advisor and Information Liaison 5 07/02 IP-2303 EOF Radiological Assessment Team Leader (RATL) 5 4 03/00 IP-2304 EOF Dose Assessment Health Physicist EOF MIDAS Operator 7 12/98 IP-2305 5 10/99 IP-2306 EOF Security Officer EOF Clerk 4 03/00 IP-2307 4 09/00 IP-2308 EOF Direct-Line Communicator 3 03/00 IP-2309 EOF Offsite Communicator 4 06/99 IP-2310 EOF Onsite Radiological Communicator VOID N/A IP-2311 EOF Offsite Radiological Communicator VOID N/A IP-2312 EOF Public Relations Liaison N/A IP-2313 EOF Public Relations Technical Advisor VOID IP-2314 EOF Radiological Assessment Monitor ALTERNATE EMERGENCY OPERATIONS FACILITY (AEOF)
VOID - N/A Emergency Activation of the Alternate Emergency IP-2400 Operations Facility (AEOF)
Replaced by IP-EP-251 SECURITY ACTIVATION 11 - 05/02 IP-2500 Security Emergency Activation Responsibilities RECOVERY/TERMINATION VOID - N/A IP-2600 Emergency Termination and Transition to Recovery VOID - N/A Replaced by IP-EP-610 IP-2601 Recovery Manager VOID - N/A Replaced by IP-EP-610 IP-2602 Development of a Recovery Action Plan Replaced by IP-EP-610 1 - 07/02 IP-2603 Recovery Support Group Manager Index 07/02 EP-FORMS SECTION -
ROSTER I 07/02 APPENDIX 'A' ROSTER II 07/02 ROSTER III 06/02
- Emergency Offsite Telephone List 06/02 APPENDIX 'B' List 06/02
'C' - Emergency Response Facility Telephone APPENDIX
ntergy CONTROLLED COPY #:
EMERGENCY PLAN PROCEDURES PROCEDURE NO. IC/EALs REV. 9 TITLE: Initiating Conditions and Emergency Action Levels THIS PROCEDURE IS TSR X THIS PROCEDURE IS NOT TSR WRITTEN BY: O&WA4 (ýA culO, t .Lý SIGNAtURE/DATE REVIEWED BY: (L1A*A'L . ._
GNATURE/ DATE APPROVED BY: / 2 6 SE I I( IEDA EFFECTIVE DATE:
PROCEDURE USE IS REFERENCE
Volume II Initiating conditions and Emergency Action Levels Rev. 9 INITIATING CONDITIONS AND EMERGENCY ACTION LEVELS (EALS)
TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Purpose 1 2.0 Responsibilities 1 3.0 References 1 4.0 Procedure 1 5.0 Attachments 5.1 Initiating conditions and Emergency Action Levels
volume II Initiating conditions and Emergency Action Levels Rev. 9 Initiating conditions and Emergency Action Levels 1.0 PURPOSE This procedure is to be used prior to an emergency classification. This procedure is to be used for declaring an event into one of the four emergency cl assi fi cati on.
2.0 RESPONSIBILITIES The Shift Manager (SM), and/or Emergency Director (ED) shall 2.1 implement this procedure.
2.2 The Control Room Supervisor (CRS) shall implement this procedure if the SM is unavailable to do so.
3.0 REFERENCES
3.1 AP-21, "Conduct of operations" 3.2 IP-2001, "Emergency Director (ED), Plant Operations Manager (POM),
shift Manager (SM) Procedure" 3.3 IP-EP-255, Emergency Operations Facility Management and Liaisons 3.4 Emergency Action Levels Technical Bases 3.5 IP-EP-610, Emergency Termination and Recovery 4.0 PROCEDURE 4.1 initial Declaration:
A. The SM or CRS shall use the Emergency Action Levels Attachment 5.1 to select categories related to plant events or conditions.
B. The SM or CRS shall determine the most appropriate emergency.
Initiating conditions and EALS Page 1 of 3
Volume II Initiating conditions and Emergency Action Levels Rev. 9 NOTE Emergency If the Emergency Action Level is not clear, reference isthelocated in the Action Levels Technical Bases for clarification. It CR with Emergency Plan procedures.
upon determining the emergency classification, the SM or CRS c.
shall declare t e emergency c assification.
NOTE The initial emergency classification should be made within 15 minutes following the identification of an event or combination of events to are taken.
ensure that proper protective and corrective actions SM.
The initial emergency classification will normally be made by the to SM's primary responsibility to act in accordance AP-21 It is the or systems ensure that necessary actions are taken to return equipment shall not to a safe, stable condition. The emergency classification interfere with this primary responsibility.
of time, or an An event that occurs and ends in a very short period has terminated, event occurs and goes unnoticed until after an event State, must still be classified and required notification to the NRC,should be The implementation of the emergency plan and counties made.
used as appropriate in these circumstances.
D. upon declaration of an emergency, the SM shall implement IP 2001 and assume the role as ED.
4.2 Reclassification
the ED A. If reclassification to a higher level is necessary, input shall repeat the classification steps above ensuring from the Control Room (CR) staff.
Initiating conditions and EALS Page 2 of 3
volume II Initiating conditions and Emergency Action Levels Rev. 9 NOTE The Emergency Operations Facility (EOF) ED shall use IP-EP-255. Ký 4.3 Termi nati on/Recovery:
A. An emergency classification will not be declassified but will be terminated or go into Recovery using criteria established in IP-EP-610, Emergency Termination and Recovery. Ký 5.0 ATTACHMENTS 5.1 Initiating Conditions and Emergency Action Levels END OF TEXT Initiating conditions and EALS Page 3 of 3
volume II Initiating conditions Attachment 5.1 and Emergency Action Levels Indian Point 3 Rev. 9 Emergency Action Levels CATEGORY 1.0 CSFST STATUS Alert unusual site Area Ale rt unusual category General Event
_______ _______I.
II 1.1.2 {1,2,3} 1.1.1Failure Any {1,2,3}
of an
-' 1.1.3 {1,2,3} RED path in F-0.1 1.1 subcri ti cal i ty RED path in F-0.1, subcriticality subcri ti cal i ty automatic trip signal AND to reduce power range Actual or imminent entry into < 5%
EITHER:
Manual trip ANDis RED Path in F-0.2, Core Cooling OR successful Red Path in F-0.3, Heat Sink I 1.2.2 {1,2,3,4} 1.2.1 {1,2,3,4}
1.2 ORANGE or RED path in core cooling RED path in F-0.2, F-0.2, Core cooling core cooling AND Functional restoration procedures not effective within 15 minutes.
1.3.1 {1,2,3,4}
in F-0.3, 1.3 Heat RED path Sink HEAT SINK AND Heat regui sink red is 1.4.1 Red Path {1,2,3,4}
on F-0.4, 1.4 Integrity Integrity 1.5 Containment 1.5.1 {1,2,3,4}
Red Path F-0.5, Containment resulting from loss of coolant.
I_____________ _____________ a ______
4 = Hot shutdown Tab7e continued - Next Paqe 1 = Power operation 5 = cold shutdown 2 = Startup 6 = Refueling 3 = Hot standby
volume II Initiating conditions .1 and Emergency Action Levels Indian Point 3 Rev. 9 Emergency Action Levels CATEGORY 2.0 REACTOR FUEL
-I site Area Ale rt Unusual Event General Category 2.1.1 {1,2,3,4}
coolant sample 2.1.3 {1,2,3,4}
2.1 coolant Coolant activity activity:
Activity > 300 jici/cc dose equivalent > 1.0 ici/cc 1-131 AND any of the dose equivalent following: 1-131 OR
- RED path on F-0.4, > 100/(E Bar)
Integrity gci/cc for all
- Primary system leakage noble gases with
> 75 gpm half-lives >10
- > 0.06 pCi/cc on R-11 or R-12 due to RCS leakage 2.2.3 {1,2,3,4} 2.2.2 {1,2,3,4}
I 1.1.1 t+/-,L0,'U
- I 2.2 Containment Containment Radiation > 0.06 g.ci/cc on R Containment Radiation monitor R-25 or R-26 11 or R-12 due to Radiation monitor R > 17 R/HR 25 or R-26 RCS leakage.
> 68 R/HR
_________ I___________ ______________
a 4 = Hot shutdown 1 = Power Operation 5 = cold shutdown 2 = Startup 6 = Refueling Table Continued - Next Page 3 = Hot standby
volume II Initiating conditions .1 Indian Point 3 and Emergency Action Levels Rev. 9 Emergency Action Levels CATEGORY 2.0 REACTOR FUEL site Area Alert Unusual Event Category General 2.3.2 {1,2,3,4,5,6} 2.3.1 2.3 Refueling confirmed sustained {1,2,3,4,5,6}
Acci dents alarm on ANY of the Spent fuel pool or other (reactor cavity following radiation Radiation monitors resulting during refueling) moniators from an uncontrolled water level fuel handling process: cannot be restored and 91R-2 or R-7 vapor maintained above Containment Area the spent fuel Monitors p001o ow water eR-5 Fuel Storage lel alarm Building Area setpoint Monitor oR-12 Containment Gas activity
- R-25 or 26 vapor Containment High Radiation Area Monitors 2.3.3 {1,2,3,4,5,6}
Report of visual observation of irradiated fuel uncovered 1 = Power Operation 4 = Hot Shutdown 2 = startup 5 = cold Shutdown 3 = Hot standby 6 = Refueling Table Continued - Next Page
volume II Initiating conditions .1 and Emergency Action Levels Indian Point 3 Rev. 9 Emergency Action Levels CATEGORY 3.0 REACTOR COOLANT SYSTEM 1*
unusual Event Alert Unusual Event General site Area Category I. 1 1 3.1.1 {1,2,3,4}
3.1.2 unidentified 3.1.1 or 11,2,3,41 3.1 3.1.3 {1,2,3,4,5,6} Primary{1,2,3,4} system leakage ressure boundary RVLIS cannot be maintained exceeding the capacity RCS Leakage > 33% with no RCP's running eakage OR (75 gpm) of a single > 10 gpm
[NOTE: This reactor vessel head charging pump with t he OR includes Primary remove d, it is reported that water Identi fi ed leakage to secondary Ievel in the reactor vessel is > 25 gpm Leakage] droppi ng in an uncontrolled manner and co re uncoverv is likely 3.. {12,,4 I 3.2.1 11,2,3,41 unisolable release 3.2.2 {1,2,3,4}
3.2 Primary to unisolable release of secondary side of secondary side secondary to atmosphere from Leakage to atmosphere from the affected steam generator(s) with primary to the affected steam secondary leakage > 75 gpm generator(s) with
[NOTE: For primary to Primary to 3.2.3 {1,2,3,4} secondary leakage secondary unisolable release of secondary side > 0.3 gpm in any Leakage, Category to atmosphere from the affected steam generator.
3.1 also steam generator(s) with primary to applies.] secondary leakage > 0.3 gpm in any steam generator AND Coolant activity > 300 pCi/cc of dose equivalent 1-131 1 ___________________
3.3.1 {1,2,3,4}< SI 3.3 RCS subcooling RCS subcooling initiation setpoint due to RCS leakage I -j
___ _____ L___
____ ___ ___ __I 4 = Hot shutdown 1 = Power Operation 5 = Cold shutdown 2 = Startup 3 = Hot standby 6 = Refueling Table continued - Next Page
volume II Initiating conditions .1 Indian Point 3 and Emergency Action Levels Rev. 9 Emergency Action Levels CATEGORY 4.0 CONTAINMENT I II.AThrt II IInhicii] Fvent
- * ^ ^I *rt Ilnll*ll::tl Fv*nt Category lGeneral 4 ~ ~~ ~ ~ ~ ~
_______ ~ ~ _____________________
nsa Event 4.1.2 {1,2,3,4} 4.1.1 {1,2,3,4} open 4.1 Containment 4.1.4 {1,2,3,4} Both doors on a vc airlock Rapid, uncontrolled Integrity confirmed Phase "B" isolation decrease in for > 4 hrs.
Status signal following confirmed LOCA containment pressure Oft with less than minimum Inability to clc )se containment following initial purge valves containment cooling safe uards increase due to RCS pressure relief or equipment operating, Table 4.3 which results ir Sa radiological failure the AND OR release pathway to Any indicators of fuel clad environment for loss, Table 4.1 LOSS of primary
> 4 hrs.
coolant inside 4.1.5 {1,2,3,4}
containment with OR containment pressure Any Phase "A" or Phase "B" or EITHER: containment ventilation or sump level response isolation valve(s) not closed not consistent with Rapid, uncontrolled decrease in when required which results in LOCA conditions containment pressure following a radiological release pathway initial increase due to RCS to the environment failure OR LOSS of primary coolant inside containment with containment pressure or sump level response not consistent with LOCA conditions AND Any indicators of fuel clad damage, Table 4.2 I1 1
________ I___
1 = Power Operation 4 = Hot shutdown 2 = startup 5 = cold shutdown 3 = Hot standby 6 = Refueling Tab7e continued - Next Page
volume II Initiating conditions .1 Indian Point 3 and Emergency Action Levels Rev. 9 Emergency Action Levels CATEGORY 4.0 CONTAINMENT r 1 Al rt 1 iiniiii1 Event I zoi t e iAi e a A1 ,*rt IlnlJ*llal Event Category jGeneral 1.A I dart* unHsual Event 4.1.6 {1,2,3,4} 4.1.3 {1,2,3,4}
4.1 Containment Either:
Integrity Either:
Status Any Phase "A" or (Continued) Any Phase "A" or Phase"B" or Phase "B' or CVI CVI valve (s) not closed when valve(s) not closed when required following confirmed requi red following LOCA OR confirmed LOCA OR Inability to isolate any Inability to isolate any primary system discharging rimary system outside containment AMD ischarging outside containment.
Radiological release to the AND environment exists as a result Radiological release to AND the environment exists as Any indicators of fuel clad a result damage, Table 4.2 I I 4.2.1 {1 2,3,4}
4.2 SG Tube 4.2.2 {1,2,3,4} unisolable faulted Rupture w/ unisolable secondary side line (outside vc) ruptured secondary break with SG tube rupture as steam generator Release identified in E-3 "Steam Generator Tube Rupture" AND Any Indicators of fuel clad damage, Table 4.2 4.3 combustible 4.3.1 11,2,3,41 Gas > 4% Hydrogen concentration in concentrations contai nment 1 = Power Operation 4 = Hot shutdown 2 = Startup 5 = cold shutdown 3 = Hot Standby 6 = Refueling Table Continued - Next Page
volume II Initiating conditions .1 and Emergency Action Levels Indian Point 3 Rev. 9 Emergency Action Levels CATEGORY 4.0 CONTAINMENT Table 4.1 Fuel Clad Loss Indicators
- 1. coolant activity > 300 gci/cc dose equivalent of 1-131
- 2. Containment radiation monitor R-25 or R-26 reading > 17 R/hr
- 3. RED path in F-0.2, CORE COOLING Table 4.2 Fuel clad Damage Indicators
- 1. ORANGE or RED path in F-0.2, CORE COOLING
- 2. RED path in F-0.3, HEAT SINK AND Heat sink is required
- 3. Coolant activity > 300 pci/cc dose equivalent 1-131
- 4. Containment radiation monitor R-25 or R-26 reading > 17 R/hr Table 4.3 Minimum Containment Cooling safeguards Equipment Fan cooler units operating Spray Pumps Required Required
<3 2 3 1 5 0 4 = Hot shutdown 1 = Power Operation 5 = cold shutdown 2 = Startup 6 = Refueling 3 = Hot Standby Table Continued - Next Page
volume II Initiating conditions .1 and Emergency Action Levels Indian Point 3 Rev. 9 Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE r I Event Al rt-A1
- rt 1-unusual 4 m unusual Event Category I General 1 *DI I.*CM* *aC Aler2t1,,45}
I 5.1.2{1,2,3,4,5,6} I Genera I 5.1.4 t1,2,3,4,5,61 5.1.3 {1,2,3,4,5,6} A valid reading on A valid reading on EMfluent 5.1 monitors A valid reading on any any monitors Table A valid reading on any any monitors Table monitors Table 5.1 monitors Table 5.1 5.1 column "NUE" for column "SAE" for > 15 5.1 column "Alert column "GE" for > 15 for > 60 minutes unless minutes unless dose minutes unless dose sample analysis can assessment can confirm > 15 minutes unless assessment can confirm dose assessment can confirm release releases are below Table releases are below rates Table 5.2 column "SAE" confirm releases 5.2 column "GE" within are below Table 5.2 < 2 x improved this time period.
within this time technical period. column "Alert" within this time specifications period. within this time period.
I
____________ I 4. 5.2.1 rmed
{1,2,3,4,5,bl sample 5.2.5 11,2,3,4,5,61 I 5.2.4 {1,2,3,4,5,61 5.2.2 1,2,3,4,5,61 confirmed sample I confi 5.2 Dose Dose projections or analysis for gaseous Proiections/ Dose projections or analysis for field surveys resulting field surveys or liquid release Environmental resulting from actual gaseous or liquid from actual or imminent release rates rates Measurements/ or imminent release > 2 x improved Release Rates release which indicate > 200 x improved doses / dose rates > which indicate doses /2 technical dose rates > Table 5. technical Table 5.2 column "GE" at specifications speci-fications the site boundary or column "SAE" at the limits for site boundary or limits for beyond. > 15 minutes > 60 minutes.
beyond.
5.2.3 {1,2,3,4,5,6}
Dose projections or field surveys resulting from actual or imminent release which indicate doses/
dose rate > Table 5.2 column "Alert" at the site boundarv or beyond f
______________ t 1
_ _ __ _ _ _ _ I _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ __I_
1 = Power Operation 4 = Hot shutdown 5 = cold Shutdown 2 = Startup 3 = Hot standby 6 = Refueling Table continued - Next Page
volume II .1 Initiating conditions Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CfiTF(ARY O RADIOACTIVITY RELEASE rATPnORY 5 0
'I I I C-t-a Ar2 A1 P rt unusual Event
(:ate gory igenerl i-- , * . ........
5.3.2 {1,2,3,4,5,6} 5.3.1 {1,2,3,4,5,6}
5.3 Area Sustained area Any sustained direct Radi ati on Radiation levels > ARM reading > 100 x Level s 15 Mr/hr in alarm or offscale EITHER: high resulting from control Room an uncontrolled OR process CAS and SAS 5.3.3 {1,2,3,4,5,6}
sustained abnormal area radiation levels > 8 R/hr within any areas, Table 5.3
_____________ i _______________ I.__________ .1 1 = Power Operation 4 = Hot shutdown 2 = Startup 5 = cold shutdown 3 = Hot standby 6 = Refueling Table continued - Next Page
volume II Initiating conditions .1 and Emergency Action Levels Indian Point 3 Rev. 9 Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Table Areas Plant 5.3 Thresholds classification SAE A1lert NUE
- Auxiliary Feedpump monitor GE monitor Building 5.1 Effluent 7.24E4gCi/sec Table R-27 360 ci/sec 36.0 Ci/sec 3.6 ci/sec
- P.A.B.
R-14 N/A N/A N/A 2.72E- 3pci/cc *Fuel storage Building R-19 N/A N/A 475 ýici/cc 9.50_Fci/cc *Control Building oService Water Pumps oRefueling water Tank
- Diesel Fuel Tank
- vital Area Access to Contai nment Tabl e 5.2 Dose Projection/Env. Measurement classification Thresholds *Appendix R Diesel Generator GE SAE Alert oBackup Service Water 1000 mRem 100 mRem 10 mRem TEDE 5000 mRem 500 mRem N/A CDE Thyroid 1000 mRem/hr 100 mRem/hr 10 mRem/hr External Exposure Rate 5000 mRem/hr 500 mRem/hr N/A Thyroid exposure rate (for 1 hr. of inhalation) I II 4 = Hot shutdown 1 = Power Operation 5 = cold shutdown 2 = Startup 3 = Hot standby 6 = Refueling Table Continued - Next Page
volume II Initiating conditions AttachmenL 5.1 Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 6.0 ELECTRICAL FAILURES site Area Alert unusual Event Category General 6.1.4 {1,2,3,4} 6.1.2 {5,6 or Defueled} 6.1.1 {1,2,3,4,5,6}
6.1 LOSS of 6.1.5 {1,2,3,4} safeguards buses not AC Power Loss of all Loss of all safeguard bus Loss of all safeguard bus AC AC power power > 15 minutes. capable of being Sources safeguard bus AC powered from at least power > 15 minutes.
AND EITHER: 6.1.3 {1,2,3,4} one of the following 480V safeguard bus power sources for > 15 Power restoration minutes:
to any emergency supplies REDUCED TO ONLY ONE bus is not likely of the following for > 15 in < 4 hrs. minutes: *Unit Auxiliary OR e 480V EDG 31 transformer Actual or imminent
- 480V EDG 32 *station Auxiliary entry into ORANGE e 480V EDG 33 transformer or RED path on e Appendix R Diesel 13W92 feeder F-O.2, Core *13W93 feeder cooli ng" unit Auxiliary transformer a Station Auxiliary transformer
- 13W92 feeder a 13W93 feeder 6.2.2 {1,2,3,4} 6.2.1 {5,6}
6.2 Loss of < 105 vdc bus DC < 105 vdc bus voltage indications for voltage indications Power for > 15 minutes Sources > 15 minutes on the switchable voltmeter for on the switchable all of the following voltmeter for all panels: of the following panels:
'31 '31
' 32
- 32
' 33 a 33 e 34 ' 34 1 = Power Operation 4 = Hot Shutdown 2 = Startup 5 = cold shutdown 3 = Hot Standby 6 = Refueling Table Continued - Next Page
volume II Attachmer,_ 3.1 Initiating conditions Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 7.0 EQUIPMENT FAILURES General site Area Alert Unusual Event Category 7.1 Technical 7.1.1 {1,2,3,4}
Specifications/ Plant is not brought Requirements to required operating mode within Improved Technical specifications LCO Action Statement Time.
7.2.5 {1,2,3} 7.2.2 {1,2,3} 7.2.1 {1,2,3}
7.2 System Failures or control Room Turbine failure Report of main control Room Evacuation generated missiles turbine failure Evacuation AND which causes or requiring turbine Plant control cannot potentially causes trip resulting in:
be established per any required safety ONOP-FP-1A, "Safe related system or Damage to turbine shutdown From outside structure to become generator seals the Control Room" in inoperable. OR
< 30 minutes casing penetration 7.2.3{1,2,3}
Entry into ONOP-FP 1A, 'Safe Shutdown From outside the control Room" 7.2.4 {5,6}
Reactor coolant temperature cannot be maintained
< 200 OF 1 = Power Operation 4 = Hot shutdown 2 = Startup 5 = cold shutdown 3 = Hot Standby 6 = Refueling Table continued - Next Page
Attachmer. j.1 volume II Indian Point 3 Initiating conditions Emergency Action Levels and Emergency Action Levels Rev. 9 CATEGORY 7.0 EQUPMENT FAILURES Category General Site Area Alert Unusual Event 7.3 LOSS of 7.3.4 {1,2,3,4} 7.3.3 {1,2,3,4} 7.3.1 {1,2,3,4}
Indications/ Loss of most safety unplanned loss of most unplanned loss of most Alarms/ system annunciators safety system annunciators safety system annunciators Communication or indications on or indications on control or indications on control capability control Room Panels, Room Panels, Table 7.3 for Room Panels, Table 7.3 for Table 7.3 > 15 minutes > 15 minutes AND AND AND LOSS of CFMS, QSPDS Increased surveillance is Increased surveillance is and other control required for safe plant required for safe plant room indicators operation operati on needed to monitor AND EITHER:
critical safety A significant plant 7.3.2 {1,2,3,4,5,6}
function status transient in progress LOSS of all communications AND OR capability affecting the A significant plant CFMS and QSPDS are ability to EITHER:
transient in progress unavailable Perform routine onsite operations (phones, sound powered phone systems, page party system, and radi os/wal ki e tal ki es)
OR Notify offsite agencies or personnel (ENS, Bell lines, FAX transmissions, and dedicated phone systems) 1 = Power Operation 4 = Hot shutdown 2 = Startup 5 = cold shutdown 3 = Hot Standby 6 = Refueling Table Continued - Next Page
volume II Attachmer,. 5.1 Initiating conditions Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 7.0 EQUIPMENT FAILURES Table 7.3 vital Control ROOM Panels SAF SBF-1 SBF-2 SCF SDF SEF SFF SGF SHF SJF SKF SLF SMF SNF SOF FAF FBF FCF FDF 1 = Power Operation 4 = Hot Shutdown 2 = Startup 5 = cold Shutdown 3 = Hot standby 6 = Refueling Table Continued - Next Page
Attachmer,- '.1 volume II Initiating conditions Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS Category General site Area Alert Unusual Event 8.1 Security 8.1.4 {1,2,3,4,5,6} 8.1.3 {1,2,3,4,5,6} 8.1.2{1,2,3,4,5,6} 8.1.1 {1,2,3,4,5,6}
Threats Security Event which Intrusion into a plant Intrusion into Bomb Device or other results in: security vital area by plant Protected indication of attempted an adversary Area by an sabotage discovered Loss of plant control OR adversary within plant Protected from the Control Room Any security event OR Area OR which represents Any security event OR Loss of remote shutdown actual or likely which represents an Notification of any capability failures of plant actual substantial credible site specific systems needed to degradation of the security threat by the protect the public level of safety of Security shift supervisor the plant or outside agency (NRC, military or law enforcement) 8.2 Fire or 8.2.3{1,2,3,4,5,6} 8.2.1 {1,2,3,4,5,6}
Explosion Fire or explosion confirmed fire in or in any plant area, contiguous to any plant Table 8.1, which area, Table 8.1 not causes or extinguished in potentially causes # 15 minutes of Control any required safety Room notification related system or structure to become 8.2.2 {1,2,3,4,5,6}
inoperable Report by plant personnel of an explosion within Protected Area boundary resulting in visible damage to non-vital permanent structures or equipment
______________ ________________ I _______________ J _____________ ________________
1 = Power Operation 4 = Hot Shutdown 2 = Startup 5 = cold Shutdown 3 = Hot Standby 6 = Refueling Table continued - Next Page
volume II Attachmet. j.1 Initiating conditions Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS Category General site Area Alert Unusual Event 8.3 Man-Made 8.3.3 {1,2,3,4,5,6} 8.3.1 {1,2,3,4,5,6}
Events vehicle crash or projectile vehicle crash into or impact which causes or projectile which impacts potentially causes any plant structures or systems required safety related within Protected Area system or structure to boundary become inoperable, Table 8.1 8.3.2 {1,2,3,4,5,6}
Report or detection of 8.3.4 {1,2,3,4,5,6} toxic or flammable gases Report or detection of that could enter or have toxic or flammable gases entered within the within a plant area, Table Protected Area boundary in 8.1, in concentrations that amounts that could affect will be life threatening to the health of plant plant personnel or preclude personnel or safe plant access to equipment (even operation when using personal OR protective equipment) Report by local, county or needed for safe plant state officials, or unit 2 operation for potential evacuation of site personnel based on offsite event 1 = Power Operation 4 = Hot shutdown 2 = Startup 5 = cold shutdown 3 = Hot Standby 6 = Refueling Table continued - Next Page
Attachmer .1 folume II Initiating -onditions Indian Po,,.c 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS Category General Site Area Alert Unusual Event 8.4 Natural 8.4.4 {1,2,3,4,5,6} 8.4.1 {1,2,3,4,5,6}
Events Earthquake felt in plant Earthquake felt in plant based upon consensus of based upon a consensus of control Room operators on control Room Operators on duty duty AND AND EITHER Kinemetrics Strong Motion Kinemetrics Strong Motion Accelographs in the Vc Accelographs in the VC produce an alarm in the produce an alarm in the control Room Control Room AND OR Amber and red Peak Shock At least one amber Peak Annunciators indicate shock Annunciator is lit seismic activity 8.4.2 {1,2,3,4,5,6}
Report 8.4.5 {1,2,3,4,5,6} by plant personnel of Sustained winds tornado within plant
> 90 mph Protected Area boundary OR Tornado strikes a plant 8.4.3 {1,2,3,4,5,6} River vital area, Table 8.1 level
_ 14.5' (0 MSL)
OR Intake structure level
< -4.5' (0 MSL) 1 = Power operation 4 = Hot Shutdown 2 = startup 5 = cold shutdown 3 = Hot Standby 6 = Refueling Table continued - Next Page
volume II AttachmenL J.1 Initiating conditions Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS Category General site Area Alert Unusual Event 8.4 Natural 8.4.6 {1,2,3,4,5,6}
Events Assessment by the Control Room personnel that a natural event has occurred which causes or potentially causes any required safety related system or structure to become inoperable, Table 8.1 8.4.7 {1,2,3,4,5,6}
River level
>_ 15' (0 MSL)
OR LOW intake structure level resulting in loss of service water flow 1 = Power Operation 4 = Hot shutdown 2 = Startup 5 = cold shutdown 6 = Refueling Table continued - Next Page 3 = Hot Standby
jol ume II Initiating Conditions Attachment a.1 Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS Table 8.1 Plant Areas
- Auxiliary Feedpump Building
- P.A.B.
- CAS/SAS
- Fuel storage Building
- control Building
- Control Room
- Service Water Pumps
- Refueling Water Tank
- EDG Rooms
- Diesel Fuel Tanks
- vital Area Access to Containment
- Appendix R Diesel Generator
- Backup Service Water 1 = Power operation 4 = Hot shutdown 2 = Startup 5 = cold shutdown 3 = Hot standby 6 = Refueling Table continued - Next Page
volume II Attachmer. ,.1 Initiating conditions Indian Point 3 and Emergency Action Levels Emergency Action Levels Rev. 9 CATEGORY 9.0 OTHER site Area (Alert Unusual Event Category General 9.1.7 {1,2,3,4,5,6} 9.1.5 {1,2,3,4,5,6} 9.1.3 9.1.1 9.1 other As determined by the shift As determined by the shift {1,2,3,4,5,6} {1,2,3,4,5,6}
Manager or Emergency Manager or Emergency Director, Any event, as Any event, as Director, events are in events are in progress which determined by the determined by the progress which indicate indicate actual or likely shift Manager or shift Manager or actual, or imminent core failures of plant systems needed Emergency Director, Emergency Director, damage and the potential for to protect the public. Any that could cause or that could lead to a large release of releases are not expected to has caused actual or has led to a radioactive material in result in exposures which exceed substantial potential excess of EPA PAGS outside EPA PAGs. degradation of the degradation of the the site boundary. level of safety of level of safety of 9.1.6 {1,2,3,4} the plant. the plant.
9.1.8 {1,2,3,4} Any event, as determined by the shift Manager or Emergency 9.1.4 {1,2,3,4} 9.1.2 {1,2,3,4}
Any event, as determined by Any event, as the Shift Manager or Director, that could lead or has Any event, as led to determined by the determined by the Emergency Director, that Shift Manager or could lead or has led to a EITHER: shift Manager or LOSS or potential loss of both Emergency Director, Emergency Director, loss of any two fission that could lead to product barriers and loss or fuel clad and RCS barrier that could lead or OR has led to a loss a loss or potential potential loss of the third loss of containment Loss or potential loss of either or potential loss fuel clad or RCS barrier in of either fuel clad conjunction with a loss of or RCS barrier containment 1 = Power Operation 4 = Hot Shutdown 2 = Startup 5 = cold shutdown 3 = Hot Standby 6 = Refueling
En tePRO EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-2003 REV. 6 TITLE: CR WATCH CHEMIST THIS PROCEDURE IS TSR X THIS PROCEDURE IS NOT TSR WPTmT1 u SIGNATURE/DATE REVIEWED BY:
NAUiA APPROVED BY:
EFFECTIVE DATE.
7Z "9/1/02-E I If PROCEDURE USE IS REFERENCE
Volume II IP-2003 Rev. 6 CR WATCH CHEMIST TABLE OF CONTENTS Section Title Page 1 .0 P UR P O S E ................................................................................................ .. 3 2.0 RESPONSIBILITIES ................................................................................... 3 3 .0 R E F E R E NC E S ........................................................................................... . 3 4 .0 P R O C E D UR E ............................................................................................ . . 3
Volume II IP-2003 Rev. 6 CR WATCH CHEMIST 1.0 PURPOSE 1.1 This procedure provides instruction to the Watch Chemistry in the Control Room or Simulator for performing Dose Assessment calculations.
2.0 RESPONSIBILITIES 2.1 Watch Chemists are responsible for Dose Assessment calculations, while the EOF is being staffed and/or while the EOF is being transferred to the AEOF.
2.2 The Watch Chemist position is a normal on-duty staff position, See E-Plan Volume II, Appendix A for current staffing.
3.0 REFERENCES
3.1 E-Plan, Volume I, Section 5.0, "Organizational Control of Emergencies" 3.2 EP Form, #4, "Control Room Emergency Staffing Chart" 3.3 EP Form, Part I, "NYS Radiological Emergency Data Form" 3.4 EP Form, Part II, "NYS Radiological Emergency Data Form" 3.5 IP-1001, "Determining the Magnitude of Release" 3.6 IP-1003, "Obtaining Meteorological Data" 3.7 IP-1 004, "Midas Computer System - Dose Assessment Model" 3.8 IP-1017, "Protective Action Recommendations for the Offsite Population" 3.9 IP-EP-310, "Dose Assessment" 3.10 IP-EP-410, "Protective Action Recommendations" 3.11 IP-2000, "Emergency Activation of the Control Room" 4.0 PROCEDURE NOTE Initial the blank lines upon completion of the designated step 4.1 Card in if appropriate for accountability.
4.2 Obtain the Watch Chemist E-Plan position book.
Page 3 of 7
Volume II IP-2003 Rev. 6 4.3 Get a turnover on the event from the Control Room crew to determine if a release is in progress and if so determine the release point (document on Event Log Sheets located in the position book).
4.4 Synchronize your time with the CR flight panel clock or remove watch.
4.5 Using the Dell PC, sign on as yourself and open the E-Plan Folder.
4.6 Obtain Met tower data using one of the following methods:
- Control Room meteorological display panel.
- IP-2 Control Room meteorological display panel (phone 9-734-5294).
Login as CCREOF and hit enter (Time will be displayed in Eastern Standard Time and wind speed will be in mph [mph x .447 = meter/sec].
For any other back-up method refer to IP-1 003, "Obtaining Meteorological Data".
4.7 Determine the magnitude of the release and whether or not the release is greater then Effluent Technical Specifications (as defined by the conservative AP-1 1 limits) by one of the following methods.
IP-2003, Computer program (From the desktop E-Plan folder and double click on the E-Plan IP-2003 icon) or access IP-2003 via the 3 1/2 Floppy disk in the Watch Chemist E-Plan position book.
- IP-1001 Procedure.
- IF an unmonitored release path exists, THEN estimate the release rate and in BLOCK 6 of EP-Form Part I, circle "D" Page 4 of 7
Volume II IP-2003 Rev. 6 NOTE "Tech Spec" (AP-11) limit is 38,100 pCi/sec Noble Gas or 12 ipCi/sec Iodine.
4.8 IF there is no release due to the event AND A General Emergency has not been declared, THEN record the following on EP-Form Part I, "NYS Radiological Emergency Data Form" within 15 minutes of the initial E-Plan classification or classification change(s) and every 30 minutes thereafter.
- In BLOCK 6, circle "A" and record "A" in the box.
- In BLOCK 7, circle "A" and record "A" in the box.
- In BLOCK 11, enter wind speed and elevation (10 meters) from Step 4.9.
- In BLOCK 12, enter wind direction & elevation (10 meters) from Step 4.9.
- In BLOCK 13, circle stability class and record letter in box per Step 4.9.
4.9 IF there is a release due to the event that is below Tech Spec
(< 38,100 [tCi/sec NG and < 12 uCi/sec Iodine) AND the site boundary doses are below Protective Action Recommendations (< 1 Rem whole body {TEDE}
and < 5 Rem thyroid {TODE}) AND A General Emergency has not been declared, THEN record the following on EP-Form Part I, "NYS Radiological Emergency Data Form" within 15 minutes of the initial E-Plan classification or E Plan classification change(s) and every 30 minutes thereafter.
- In BLOCK 6, circle "B" and determine if the release is to the atmosphere or water and check the appropriate box record "B" in the box.
- In BLOCK 7, circle "A" and record "A" in the box.
- In BLOCK 11, enter wind speed and elevation (10 meters) from Step 4.9.
- In BLOCK 12, enter wind direction from and elevation (10 meters) from Step 4.9.
In BLOCK 13, circle the stability class and record the letter in the box from Step 4.9.
Page 5 of 7
Volume II IP-2003 Rev. 6 4.10 IF there is a release due to the event that is above Tech Spec (>38,100 uCi/sec NG or 12 uCi/sec Iodine) AND Site Boundary Doses are below Protective Action Recommendations (< 1 Rem whole body {TEDE} and < 5 Rem thyroid {TODE}) AND a General Emergency has not been declared, THEN record the following on EP-Form Part I and Part II, "NYS Radiological Emergency Data Forms" within 15 minutes of the initial E-plan classification or E plan classification change(s) and every 30 minutes thereafter. Fill out EP-Form Part I as follows:
In BLOCK 6, circle "C" and determine if the release is to the atmosphere or water and check the appropriate box record "C" in the box.
- In BLOCK 7, circle "A" and record "A" in the box.
- In BLOCK 11, enter wind speed and elevation (10 meters) from Step 4.9 In BLOCK 12, enter wind direction from and elevation (10 meters) from Step 4.9.
In BLOCK 13, circle the stability class and record the letter in the box from Step 4.9.
4.10.1 Fill out EP-Form Part II as follows:
- In BLOCKS 16, 17, 18, and 19 fill out the known data in the appropriate spaces per the Dose Assessment program. Fill in N/A for the results/data that are unknown.
4.10.2 Provide EP-Form Part I and Part II to the ED for review.
4.10.3 After the ED has reviewed the EP-Form Part I and Part II, provide the form to the clerk for faxing.
4.10.4 IF A General Emergency is declared OR Site Boundary Doses are above Protective Action Recommendations (> 1 Rem whole body
{TEDE} or > 5 Rem thyroid {TODE}), THEN record the following on EP Form Part I and Part II, "NYS Radiological Emergency Data Forms" within 15 minutes of the initial E-plan classification or E-plan classification change(s) and every 30 minutes thereafter.
Page 6 of 7
Volume II IP-2003 Rev. 6 4.10.5 Fill out EP-Form Part I as follows:
"* In BLOCK 6, circle the appropriate letter, which corresponds to the type of release in progress and record that letter in the box.
"* In BLOCK 7, circle "B and C" and record "B" and "C" in the box. In section "B" circle the appropriate ERPA's per the IP-2003 computer program or applicable EPlan procedures.
"* In BLOCK 11, enter wind speed and elevation (10 meters) from Step 4.9
"* In BLOCK 12, enter wind direction from and elevation (10 meters) from Step 4.9.
"* In BLOCK 13, circle the stability class and record the letter in the box from Step 4.9.
4.10.6 Fill out EP-Form Part II as follows:
In BLOCKS 16, 17, 18, and 19 fill out the known data in the appropriate spaces per the Dose Assessment program. Fill in N/A for the results/data that are unknown.
4.10.7 Provide EP-Form Part I and Part II to the ED for review.
4.10.8 After the ED has reviewed the EP-Form Part I and Part II, provide the forms to the clerk for faxing.
4.11 Ensure you are signed in on EP-Form #4, "Control Room Emergency Staff Chart".
4.12 Display the plume direction on the 10-mile map using the plume overlay.
4.13 Recalculate the Dose Assessment as necessary based on changes in release rate or Met data and re-evaluate the PARs as necessary.
4.14 Update the ED of any changes that could affect the release rate, dose assessment calculation or PARs.
END OF TEXT Page 7 of 7
Entergy EMERGENCY PLAN PROCEDURES IP-2302 REV. 10 PROCEDURE NO.
TITLE:EOF TECHNICAL ADVISORS AND INFORMATION LIAISONS THIS PROCEDURE IS TSR X THIS PROCEDURE IS NOT TSR WRITTEN BY: * *.*,
- IGNATURE/DATE REVIEWED BY * . !GN**A.T D "-*
/,I GNAT UREDATE APPROVED BY: A SIGNAT_ ATE EFFECTIVE DATE: _ _ _ _
_ ___/_____
PROCEDURE USE IS REFERENCE
VOLUME II IP-2302 Rev. 10 EOF TECHNICAL ADVISORS AND INFORMATION LIAISONS TABLE OF CONTENTS TITLE PAGE SECTION Purpose 1 1.0 Responsibilities 1 2.0 References 1 3.0 Procedure 2 4.0 5.0 Attachments 5.1 Emergency Director Technical Advisor 5.2 EOF Information Liaison 5.3 Accessing and Using SPDS 5.4 JNC Essential Information Checklist 5.5 Turnover Checklist
VOLUME II IP-2302 Rev. 10 EOF TECHNICAL ADVISORS AND INFORMATION LIAISONS 1.0 PURPOSE 1.1 The purpose of this procedure is to provide guidance to the TECHNICAL ADVISORS and INFORMATION LIAISONS in the Emergency Operations Facility (EOF).
The TECHNICAL ADVISOR and INFORMATION LIAISON positions are filled in accordance with Roster II staffing.
See E-Plan Volume II, Appendix A for current staffing.
2.0 RESPONSIBILITIES 2.1 The Emergency Director Technical Advisor (ED TA)is responsible for providing technical advice to the Emergency Director (ED).
2.2 The EOF INFORMATION LIAISON (EOF IL)is responsible for obtaining and interpreting technical data pertaining to the emergency at IP3, and relaying this information to the Joint News Center Technical Advisor.
3.0 REFERENCES
3.1 EP-Form #8, "EOF to AEOF Relocation Information" 3.2 EP-Form #31a, "Plant Status Log, (measurement)"
3.3 EP-Form #31b, "Plant Status Log, (rad. monitors)"
3.4 EP-Form #31c, "Equipment Status Log (equipment status)"
IP-2302 Page 1 of 2
VOLUME II IP-2302 Rev. 10 4.0 PROCEDURE NOTE:
The steps in this procedure are not required to be performed in sequence.
Initial the blank lines upon completion of the designated steps.
4.1 SIGN IN on EP-Form #7, "EOF Staffing Chart".
4.2 SYNCHRONIZE your time with the EOF clock.
4.3 Upon assuming duties, OBTAIN a briefing from the Control Room (CR) or ED.
4.4 IF filling the ED TA position, THEN go to Attachment 5.1, "Emergency Director Technical Advisor".
IF filling the EOF IL position, THEN go to Attachment 5.2, "EOF Information Liaison".
4.5 Use Attachment 5.7, "Turnover Checklist" when conducting turnover.
5.0 ATTACHMENTS 5.1 Emergency Director Technical Advisor 5.2 EOF Information Liaison 5.3 Accessing and Using SPDS 5.4 JNC Essential Information Checklist 5.5 Turnover Checklist 1D END OF TEXT IP-2302 Page 2 ol 2
VOLUME II IP-2302 Rev. 10 Page 1 of 1 ATTACHMENT 5.1 EMERGENCY DIRECTOR TECHNICAL ADVISOR
- 1. OBTAIN plant data.
A. IF Safety Parameter Display System (SPDS) is operational, THEN ACTIVATE SPDS using Attachment 5.3, "Accessing and Using SPDS", as necessary.
B. IF SPDS is NOT operational, THEN obtain the following forms from the TSC approximately every 15 min.:
- EP-Form #31a, "Plant Status Log (measurements)"
- EP-Form #31b, "Plant Status Log (rad. monitors)"
- EP-Form #31c, "Equipment Status Log (equipment)"
- 2. REVIEW data on EP-Forms #31a, b and c.
- 3. From the information obtained above:
A. IF paper forms are used, THEN IDENTIFY trends that challenge plant safety and fission product barriers on the forms (ie, happy/frowning faces, up/down arrows, etc.),
B. Once reviewed, INITIAL the paper forms and forward to the clerks for processing.
- 4. For use as reference of emergency events, LOG important data and status of emergency on flip charts and fission product barrier board.
- 5. RECEIVE EP-Forms Part I and Part II, "NYS Radiological Emergency Data Forms" from Offsite Communicator for review, as necessary.
- 6. DISCUSS plant conditions and prognosis with the ED.
"*REVIEW E-Plan Volume II, IC/EAL's "Initiating Conditions and Emergency Action Levels" for a potential change in classification.
"*ADVISE the ED of any changes that would affect the current classification.
VOLUME II IP-2302 Rev. 10 Page 1 of 2 ATTACHMENT 5.2 EOF INFORMATION LIAISON 1.0 Establish communications with EOF staff, the IP Communications Representative and JNC Technical Advisor, if activated.
2.0 Turn on designated computer and locate EOF liaison folder for EOF to JNC Essential Form template. Establish email capability to the IP Communications Representative (their current location email address should be established when making contact) and JNC Technical Advisor (address = JNC Tech Advisor), once activated.
Create a folder named for the event date, and put all completed EOF to JNC Essential Information Forms and any other electronic documents to this folder.
3.0 Obtain up-to-date information and begin to document available information on the EOF to JNC Essential Information Checklist (Attachment 5.4). Fax all completed forms to the JNC Fax/Copy Room.
4.0 Coordinate the review and approval of news release(s) with the IP Communications Representative, ensuring prompt approval by the Emergency Director.
5.0 Coordinate with the IP Communications Representative to distribute the news release. Distribution includes the JNC and EOF, media and other Entergy location. If requested, print and send via fax the news release on the machine located at the EOF Information Liaison work area. Numbers are pre-programmed and/or available on the Fax Distribution form located by the fax machine.
7.0 When informed of JNC activity, establish hot line contact with JNC Technical Advisor.
8.0 Provide current EOF time to the JNC for clock synchronization.
9.0 Update JNC Technical Advisor with information relating to plant events both verbally and using the EOF to JNC Essential Information Checklist (Attachment 5.4), at approximately 30 minute intervals or as events warrant.
"* DISCUSS site radiological information with the Radiological Assessment Team Leader (RATL);
"* DISCUSS plant status information with the ED TA;
"* DISCUSS accountability/evacuation status with the Onsite Radiological Communicator;
"* DISCUSS Offsite Monitoring Team status with the Offsite Radiological Communicator;
"* DISCUSS meteorological and dose assessment information with the Dose Assessment H.P. (DAHP).
VOLUME II IP-2302 Rev. 10 Page 2 of 2 ATTACHMENT 5.2, Continued EOF INFORMATION LIAISON 10.0 Respond promptly to requests from JNC for information.
11.0 Ensure prompt review and concurrence of JNC news releases by the Emergency Director.
12.0 Receive and post final news releases from JNC on bulletin board in EOF Information Liaison work area. Provide final news releases to the administrative staff for distribution within the facility.
- Ensure prompt distribution of final news releases by EOF Administrative Staff, as appropriate within the EOF to select managers and the State and County representatives.
13.0 Update the PAR Status Board as necessary.
14.0 If relocation to the AEOF is required, THEN ensure that information is transferred from the PAR Status Board to EP-Form
- 8, "EOF to AEOF Relocation Information". Also, coordinate with the JNC and the EOF Information Liaison going to the AEOF until a complete transfer has been made.
VOLUME II IP-2302 Rev. 10 Page 1 of 3 ATTACHMENT 5.3 ACCESSING AND USING SPDS
- 1. POWERING UP SPDS:
A. ENSURE the main power switch is ON (no main switch at the EOF, middle left of the desk at the AEOF).
B. ENSURE that the RAMTEK display generator power switch is ON (back center wall at the EOF, lower left of the desk at the AEOF).
C. ENSURE that the GENICOM printer power switch is ON and that the ON LINE light is on (front right side light).
D. ENSURE that the VGR 4000 video printer (if equipped) power is ON by pulling out the power switch on the right side of the case. Pull out the paper tray (on the left side of the case). The green copy light should come on and not be flashing.
E. ENSURE that the SPDS monitor power is on and that the time in the upper left corner is updating.
- IF the screen is blank, THEN try adjusting the brightness control using the buttons found on the lower left side of the monitor.
F. IF the screen is blank or blinking, OR if the time is not updating, THEN do the following:
- 1. Reset the SPDS as follows:
- b. Wait 10 seconds.
- c. Turn the power switch ON. The screen should start blinking.
Within two minutes, the screen should stop blinking and "INITIALIZING DISPLAYS" should be displayed. Approximately 4 1/2 minutes later, the SECURITY/PRINTER screen (Page 101) should appear and the time should be updating.
- 2. LOGGING ON SPDS:
A. Log-on as follows:
NOTE Due to sticky keys, 2 or 3 attempts may be necessary.
- EOF - Type EOF4, press RETURN
VOLUME II IP-2302 Rev. 10 Page 2 of 3 ATTACHMENT 5.3, Continued ACCESSING AND USING SPDS B. VERIFY that a primary or secondary printer light is blue (listed under the facility name in the right middle portion of the Terminal screen).
- 1. GO to the SECURITY/PRINTER screen (page 101)
- a. PRESS the PAGE key
- b. TYPE 101
- c. PRESS the EXEC key
- 2. IF the printer light is magenta in color, THEN do the following:
- b. PRESS the ADDR key.
- d. PRESS the EXEC key.
- 3. IF the printer is not available for output, THEN call contact the TSC (X 8710).
- 3. ACCESSING EP-FORMS #31A/#31B/#31C:
A. OSC, TSC OR EOF: OBTAIN EP-Form #31a, "Plant Status Log (measurements)",
EP-Form #31b, "Plant Status Log (rad. monitors)" and EP-Form #31c, "Plant Status Log (equipment)", as follows:
- 1. PRESS the DIALOGUE key.
- 2. TYPE the Emergency Status function number, and press RETURN.
(This entry selects Emergency Plant Status.)
- 3. (Skip this step for a 1-time demand report.)
TYPE a desired time interval (1-60 minutes, 15 minutes is suggested)for a automatic report, then PRESS the VALUE ONE key.
- 4. Optionally, TYPE a different station number (on whose printer the report will print), then PRESS the VALUE TWO key.
- 5. PRESS the EXEC key. EP-Forms #31a/b/c will print in a few seconds.
- 6. Stop an automatic report by typing the station number on whose printer the report is printing, then PRESS the VALUE TWO key, then PRESS the STOP key.
- 4. LOGGING OFF SPDS:
A. PRESS the PAGE key.
B. TYPE 101.
C. PRESS the EXEC key.
D. WHEN the SECURITY/PRINTERS screen is displayed, PRESS the STOP key.
VOLUME II IP-2302 Rev. 10 Page 3 of 3 ATTACHMENT 5.3, Continued ACCESSING AND USING SPDS
- 5. RESTORING THE FACILITY:
A. ENSURE the SECURITY/PRINTERS screen is in the sign-off mode.
B. Turn the power switch on the SPDS monitor OFF to avoid the SECURITY/PRINTERS screen image being "burned" into the SPDS monitor.
VOLUME II IP-2302 Rev.10 Page 1 of 1 ATTACHMENT 5.4 JNC ESSENTIAL INFORMATION CHECKLIST Emergency Classification: Reactor: U At Power Ul Tripped Time: EAL #:Trpe RCS Temp:____ °F Pressure: PSIG I Unusual Event RVLIS / Pressurizer Level:
L] Al
[] Alert Subcooling method:
[ Site Area Emergency Weather Forecast:
[] General Emergency Method of Core Cooling: Ul S/G [L Safety Injection L) RHR Electrical Power Supplies Available: [l 138 KV YJ 13.8 KV # Diesel Generators Event
Description:
Major Equipment Problems/Priorities:
[ No Radiological Release [] Release of radioactive materials due to event Radiological Release below / above federally approved operating limits Radiological Release to: U Atmosphere U Water [L Unmonitored release requiring evaluation
- of Onsite Teams # of Offsite Teams Fission Product Barrier Status Accountability Completed At: Barrier Intact Challenged Lost
- Not accounted for: Fuel Clad [] [] []
Actions being taken for search & rescue:
__ __ _ __ __ __ _RCS 1J l L]
ERO Staffing: [] YES [l NO J] In progress Containment [U [] [
Release of Non-essential Personnel I]YES [] NO Injuries: IQ__ Employee UJContractor Status of other IP Unit:
Typeof njuries:___Status___ofother__IP__Unit:
Type of Injuries: Release of Non-essential Personnel DJYES Ll NO U Hospital Released / Admitted Q Contaminated This Checklist was Completed: pate I ]I By: _ _ _ __Name
-me nnt Name
VOLUME II IP-2302 Rev.10 Page 1 of 1 ATTACHMENT 5.5 TURNOVER CHECKLIST When the Technical Advisor or Information Liaison is relieved by another Technical Advisor or Information Liaison, the following checklist should be used to effectively turnover responsibilities.
Current Position:
Relieving Position:
Date: Time:
The following items should be discussed as applicable:
- 1. Emergency Classification
- 2. Initiating Event (Date Time and Cause)
- 3. Plant Conditions
- 4. Equipment out of service
- 5. Proposed/In -Progress/Completed Actions
- 6. Site Accountability/Site Evacuation
- 7. Any other items that should be communicated.
EMRteNCY EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-2603 REV. 1 TITLE: Recovery Support Group Manager THIS PROCEDURE IS TSR THIS PROCEDURE IS NOT TSR WRITTEN BY: ý&~~~~ kir 1DL SIGNATURE/DATE I L8JoZ REVIEWED BY: ,I IGNATURE/DATE APPROVED BY:
a S I6 ?RE/DATE EFFECTIVE DATE:
PROCEDURE USE IS REFERENCE
VOLUME II IP-2603 Rev. 1 RECOVERY SUPPORT GROUP MANAGER TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Purpose 1 2.0 Responsibilities 1 3.0 References 1 4.0 Procedure 1 5.0 Attachments 3 5.1 Recovery Support Group Manager Initial Actions
VOLUME II IP-2603 Rev. 1 IP-2603 RECOVERY SUPPORT GROUP MANAGER 1.0 PURPOSE 1.1 The purpose of this procedure is to provide instruction to the Recovery Support Group Manager. The Recovery Support Group Manager coordinates requests for personnel, equipment and materials, and support services.
This procedure is implemented by the Recovery Support Group Manager in the event of an emergency at the plant which requires notification of the Corporate Recovery Manager and coordination of 1 Corporate resources during the Emergency Phase and/or activation of the Recovery Organization during the Recovery Phase. The Corporate Recovery Manager may designate other personnel to act as Recovery Support Group Manager.
2.0 RESPONSIBILITIES 2.1 The Recovery Support Group Manager is responsible for:
A. Notifying the Corporate Recovery Manager of emergencies and 1 keeping him informed of the emergency status.
B. Coordinating requests for corporate support.
C. Coordinating requests for other personnel, equipment and materials, and support services.
D. Notifying and coordinating requests for assistance with offsite support organizations as directed by the Corporate Recovery
- Manager.
3.0 REFERENCES
3.1 IP-EP-610, Emergency Termination and Recovery ip 3.2 EP-Form Part I, "New York State Radiological Emergency Data Form, Part I General Information" 3.3 Volume I, Emergency Plan 3.4 Volume II, Appendix B 3.5 Volume II, Appendix C IP-2603 Page 1 of 3
VOLUME II IP-2603 Rev. 1 PROCEDURE NOTE The steps in this procedure are not required to be performed in sequence.
Initial the blank lines upon completion of the designated steps.
4.1 Notification A. RECEIVE notification of an emergency from the Plant.
B. CONFIRM the notification with Site Security and obtain a Plant status.
C. NOTIFY the Corporate Recovery Manager or alternate of the emergency.
4.2 Activation A. ESTABLISH and MAINTAIN communications with the Corporate Recovery Manager during the EMERGENCY PHASE.
B. As requested by the Corporate Recovery Manager, COORDINATE corporate resources through normal channels to support the plant during the EMERGENCY PHASE.
C. As requested by the Corporate Recovery Manager, NOTIFY offsite support organizations to support the plant during the' EMERGENCY PHASE. Organizations, which may be called upon to provide assistance, are listed in Volume I, Emergency Plan.
D. IF RECOVERY OPERATIONS ARE REQUIRED, THEN REPORT to the designated Recovery Center (EOF or other location).
4.3 Recovery Operations A. ASSIST the Corporate Recovery Manager to determine if, corporate capabilities required for Recovery Support Group (see Volume I, Emergency Plan).
B. COORDINATE corporate resources to support Recovery operations. A Recovery Support Group call list is located in Volume II Appendix C.
IP-2603 Page 2 of 3
VOLUME II IP-2603 Rev. 1 C. COORDINATE requests for other personnel, equipment and materials, and support services through the Recovery Support Group organization.
D. COORDINATE support from offsite support organizations. Organizations, which may be called upon to provide assistance, are listed in Volume II, Appendix B.
E. DEVELOP a shift-rotation schedule for the Recovery Support Group as needed.
F. COORDINATE the implementation of tasks appropriate to the Recovery Support Group in IP-EP-610, Emergency Termination and Recovery.
G. CONTINUE to update the Corporate Recovery Manager on the status of Recovery Support Group operations.
H. MONITOR progress of Recovery Support Group and Recovery Support Group tasks in the Recovery Action Plan and provide assistance/coordination where appropriate.
I. Consider the following while ASSISTING the Corporate Recovery Manager in determining resource requirements for Recovery functions:
"* Need for additional personnel required for long-term recovery efforts,
"* Need for offsite technical assistance,
"* Need for supplies, equipment, parts, and other material.
4.4 TERMINATE Recovery Operations A. ENSURE the completion or dispositioning of Recovery Support Group tasks outlined in the Recovery Action Plan.
B. ENSURE that appropriate offsite agencies/
organizations have been notified of the termination of Recovery.
C. ENSURE that all Recovery Support Group actions have been documented.
5.0 ATTACHMENTS 5.1 Recovery Support Group Manager Initial Actions END OF TEXT IP-2603 Page 3 of 3
VOLUME II IP-2603 Rev. 1 Page 1 of 1 ATTACHMENT 5.1 RECOVERY SUPPORT GROUP MANAGER INITIAL ACTIONS via When the Recovery Support Group Manager receives an emergency notification respond by telephoning the number on the pager and the IP-3 beeper from IP, Security to determine the nature of the emergency. (Refer to Volume II, (CAS) telephone number).
Appendix C for IP-3 Security Command Post
- 1. Contact IP-3 Security CAS at (914) 736-8067 or 8068.
- 2. USE the appropriate EP-Form, Part I "New York State Radiological Emergency Data Form, Part I - General Information" to note pertinent information.
- 3. For further instructions, CONTACT the Corporate Recovery Manager or alternate. Refer to Recovery Support Group Call list (Volume II, Appendix C) for Corporate Recovery Manager notification information.
- 4. If requested by the Corporate Recovery Manager, CONTACT Corporate departments for support. Refer to the Recovery Support Group Call list (Volume II, Appendix C) for Corporate department notification information.
- 5. If requested by the Corporate Recovery Manager, CONTACT offsite support organizations for support. Refer to Volume II, Appendix B for offsite support organization notification information.
- 6. If requested by the Corporate Recovery Manager, report to the designated Recovery Center (EOF or other locations) and implement IP-2603, "Recovery Support Group Manager".
VOLUME II EP-FORMS 07/11/02 EMERGENCY PLAN - VOLUME II EMERGENCY RESPONSE ACTIVATION EP-FORMS INDEX CORRESPONDING EP-FORM # EP-FORM TITLE PROCEDURE DATE 4 Control Room Emergency Staffing Chart N/A 10/00 5 Environmental TLD and Air Sample Readout N/A 02/98 6 Emergency Exposure Summary Sheet N/A 03/93 7 Authorization for Personnel to Receive N/A 12/95 Emergency Exposure Above 10CFR20 Limits 8 EOF to AEOF Relocation Information N/A 07/96 9 TSC Staffing Chart N/A 06/99 10 OSC Staffing Chart N/A 3/00 12 Ambulance and Attendant Survey Form IP-1021 10/94 13 Fire Fighter Exposure Record IP-1055 05/96 14 Personnel Contamination Check IP-1060 02/98 15 Skin Decontamination Record IP-1060 02/96 16 Vehicle Contamination Check N/A 10/95 17 Equipment Contamination Check N/A 10/95 18 OSC Emergency Briefing Form IP-1025 10/94 19 NYPA Communications Message Form N/A 08/93 20 OSC/TSC Survey Map N/A 04/95 21 Air Sample Counting Instrument Data Sheet N/A 01/95 i
VOLUME II EP-FORMS 07/11/02 EMERGENCY PLAN - VOLUME II EMERGENCY RESPONSE ACTIVATION EP-FORMS INDEX (CONT'D)
CORRESPONDING PROCEDURE DATE EP-FORM # EP-FORM TITLE N/A 04/96 22 Determination of Radioactive Airborne Concentrations N/A 02/98 23 Team Status Form N/A 02/98 27 Offsite Survey Team Data IP-1038 09/01 Part I New York State Radiological Emergency Data Form, Part I - General Information IP-1038 09/01 Part II New York State Radiological Emergency Data Form, Part II - Radiological Assessment Data N/A 02/97 31a Plant Status Log (measurements)
N/A 09/99 31b Plant Status Log (rad. monitors)
N/A 02/97 31c Plant Status Log (equipment status)
N/A 12/93 40 Manual Dose Projection Worksheet N/A 11/94 42 EOF Radiological Survey Form N/A 02/98 45 EOF Personnel Dosimetry Record N/A 11/94 47 Visitors Log N/A 02/98 48 RADCOM Worksheet IP-1038 03/90 361 (NRC Form) Event Notification Worksheet ii
VOLUME III TABLE OF CONTENTS 07/11/02 ENTERGY NUCLEAR NORTHEAST PLANT INDIAN POINT NO. 3 NUCLEAR POWER EMERGENCY PLAN - VOLUME III IMPLEMENTING PROCEDURES TABLE OF CONTENTS REV. DATE PROCEDURE TITLE PROCEDURE #
Dose Assessment VOID N/A IP-1001 Determining the Magnitude of Release Replaced by IP-EP-310 4 02/99 IP-1002 Post-Accident Monitoring of Noble Gas Concentration in Plant Vent IP-1003 Obtaining Meteorological Data Replaced by IP-EP-510 System Midas Computer IP-1004 Replaced by IP-EP-510 Environmental Monitoring Surveys 24 05/99 IP-1011 Offsite Monitoring/Site Perimeter 4 02/99 Emergency Airborne Activity Determination IP-1012 and 7 12/98 IP-1015 Post-Accident Environmental Sampling Counting Protective Actions for VOID N/A IP-1017 Protective Action Recommendations the Offsite Population Replaced by IP-EP-410 9 11/97 (KI)
IP-1019 Emergency Use of Potassiun Iodide Personnel Injury 25 06/98 IP-1021 Radiological Medical Emergency VOID N/A Decon IP-1023 Use and Set Up of the IP3 Personnel Suite Damage Assessment Teams 12 12/98 IP-1025 Repair and Corrective Action 12 12/97 IP-1027 Emergency Personnel Exposure 9 06/98 IP-1028 Core Damage Assessment Notification and Communication 26 09/01 IP-1038 Offsite Emergency Notifications 4 02/01 (ERDS)
IP-1039 Emergency Response Data System Activation and Testing i
VOLUME III TABLE OF CONTENTS 07/11/02 ENTERGY NUCLEAR NORTHEAST INDIAN POINT NO. 3 NUCLEAR POWER PLANT EMERGENCY PLAN - VOLUME III IMPLEMENTING PROCEDURES TABLE OF CONTENTS PROCEDURE TITLE REV. DATE PROCEDURE #
Emergency Response Facilities Habitability of the Emergency Response 16 11/97 IP-1040 Facilities and Assembly Areas Personnel Monitoring for EOF, TSC, OSC VOID N/A IP-1041 and Control Room Personnel Accountability and Evacuation 27 04/02 IP-1050 Accountability Evacuation of Site 13 03/02 IP-1053 12/97 Search and Rescue Teams 10 IP-1054 Non-Radiological Emergencies 8 07/02 IP-1052 Hazardous Waste Emergency is 04/02 IP-1055 Fire Emergency Response in VOID N/A IP-1056 Directing Fire Fighting Personnel Controlled Area 8 10/01 IP-1057 Natural Phenomena Emergency Earthquake Emergency VOID N/A IP-1058 Air Raid Alert 7 05/01 IP-1059 H.P. Release Surveys and Decontamination 11 02/98 IP-1060 Personnel Radiological Check and Decontamination Vehicle/Equipment Radiological Check 11 11/97 IP-1063 and Decontamination Emergency Equipment and Maintenance Periodic Inventory of Emergency Plan 31 02/01 IP-1070 Equipment Roster Notification Methods 26 05/02 IP-1076 Conduct of Emergency Exercises and Drills VOID N/A IP-1080 N/A Maintenance of Emergency Preparedness VOID IP-1085 at IP-3 ii
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