ML022120546

Revisions to Vol. II of Emergency Plan Implementing Procedures, Including TOC, Rev. 9 to Iceals, Rev. 6 to IP-2003, Rev. 10 to IP-2302, Rev. 1 to IP-2603, Index to EP-Forms Section, Appendix a Rosters I & II, Vol. III, Including TOC

ML022120546
Person / Time
Site:	Indian Point  (DPR-064)
Issue date:	07/16/2002
From:	Entergy Nuclear Indian Point 3 LLC
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
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L1-JUL- 02 DISTRIBUTION CONTROL LIST Icument Name:

EMER PLAN CC-NAME NAME 1 PLANT MANAGER'S OFFICE 2 EP/TRAINING ADMINISTRATOR 3 RES DEPARTMENT MANAGER 4 REFERENCE LIBRARY 9 JOINT NEWS CENTER 10 SHIFT MGR. (LUB-001-GEN) 11 CONTROL ROOM & MASTER 14 EOF 16 AEOF/A.GROSJEAN 19 NUC ENGINEERING LIBRARY 22 RESIDENT INSPECTOR 23 MCNAMARA N 24 MCNAMARA N 25 DOCUMENT CONTROL DESK 28 AVRAKOTOS N 29 E-PLAN STAFF 30 E-PLAN STAFF 31 BARANSKI J(VOLUME I ONLY) 32 MURPHY L -(VOLUME I ONLY) 33 LONGO N (VOLUME I ONLY) 34 GREENE D (VOLUME I ONLY) 35 RAMPOLLA M(VOLUME I ONLY) 41 SIMULATOR 319 C.STELLATO 354 L.GRANT 376 E-PLAN STAFF 424 OPS-INSTR (LL'S 1 COPY) 510 L.GRANT 511 L.GRANT 512 C.STELLATO 513 C.STELLATO 517 PLANT MANAGER'S OFFICE 518 DOCUMENT ROOM 519 TSC 520 CONTROL ROOM (UNIT 2) 521 SIMULATOR (UNIT 2) 522 NRC RESIDENT (UNIT2) 523 ROBERT VOGLE (UNIT 2) 524 JOHN MCCANN (UNIT 2)

DEPT UNIT 3 /ADMINISTRATION TRAINING RES DEPARTMENT RECORDS (TRNG BLDG)

EMERGENCY PLANNING OPERATIONS OPS(3PT-D001-D006 ONLY)

E-PLAN E-PLAN (EOP'S ONLY)

WPO DOCUMENT CONTROL US NRC NRC NRC NRC J A FITZPATRICK E-PLAN E-PLAN ST.

EMERG.

MGMT.

OFFICE DISASTER & EMERGENCY EMERGENCY SERVICES DISASTER & CIVIL DEFENSE OFFICE OF EMERG MANAGE TRAINING NRQ-OPS / TRAINING LRQ-OPS / TRAINING E-PLAN J.

CHIUSANO/TRAINING LRQ-OPS / TRAINING LRQ-OPS / TRAINING NRQ-OPS / TRAINING NRQ-OPS / TRAINING ADMIN/(IPEC ONLY)

TSC (IPEC ONLY)

UNIT 2 (IPEC ONLY)

OPERATIONS (IPEC ONLY)

TRAIN/CENTER (IPEC ONLY)

US NRC (IPEC ONLY)

TRAINING LIBRARY NUC SAFETY/LICENSING

]LOCATION 45-3-B

1. 48 45-4-A

1. 48 EOF IP3 IP3 EOF WPO-12D WPO/7A 45-2-B OFFSITE OFFSITE OFFSITE OFFSITE EOF EOF OFFSITE WESTCHESTR ROCKLAND ORANGE PUTNAM 48-2-A

1. 48

1. 48 EOF

1. 48

1. 48

1. 48

1. 48

1. 48 IP2 UNIT 2 IP2 IP2 48-2-A IP2 OFFSITE IP2

Entergy Indian Point 3 AP-18.2 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:

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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 (DDt MT*

SIGNATI IRE DATE CC#

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TO:

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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.

Please sign this memo indicating that you have completed the update as specified and return to:

Entergy Nuclear Indian Point Nuclear Generating Station Records and Documents Department Broadway & Bleakley Aves.

Buchanan, NY 10511 Attn: Document Custodian Document Name Volume II Emergency Response Activation Implementing Procedures New Rev.

1. 1 Date Old Rev.

1. / Date Instructions Table of Contents 7/11/02 7/02 Replace entire document Initiating Conditions & Emergency Action Levels CR Watch Chemist Emergency Director EOF Technical Advisor &

Information Liaison Emergency Activation of the Alternate Emergency Operations Facility (AEOF)

Emergency Termination &

Transition to Recovery Recovery Manager Development of Recovery Action Plan Recovery Support Group Manager 9

6 Void 10 Void Void 8

5 10 9

6 4

Void Void I

lr-LoVJ I

I I

Replace entire document Replace entire document Remove entire document Replace entire document Remove entire document Remove entire document Remove entire document Remove entire document 0

Replace entire document Document #

U3 TOC IC/EALs IP-2003 IP-2301 IP-2302 IP-2400 IP-2600 IP-2601 IP-2602 I

II"-LOV-)

I

I New Rev.

/ Date Old Rev.

1. 1 Date 4

t Document #

Document Name Volume I1 U3 Emergency Response Activation Implementing Procedures EP-Forms Index Section EP-Form 46 EOF Staffing Chart Appendix A Rosters 1, 11 Volume III U3 Emergency Plan Implementing Procedures TOC Table of Contents IP-1001 Determining the Magnitude of IP-1001Release IP-1003 Obtaining Meteorological Data IP-1004 MIDAS Computer System Protective Action IP-1017 Recommendations for the Offsite Population Void 7/02 9/01 2/99 6/02 New Rev.

1. /Date 7/11/02 Void Void Old Rev.

1. /Date 5/02 17 18 Void 16 Void 13 Instructions Replace entire document Remove entire document Replace entire document Rm nstvuctions Replace entire document Remove entire document Remove entire document Remove entire document Remove entire document Signature of Controlled Copy Holder 7/11/02 Update completed as specified:

Date

VOLUME II APPENDIX

'A' 07/02 This page is being substituted for this Appendix in the NRC Volume II controlled copies due to the contents being personal and confidential, and not applicable for distribution to the public.

Appendix 'A' of the IP-3 Emergency Plan Volume II contains the following:

ROSTER I DIALOGICS ROSTER II IP-3 Notification Telephone Numbers for the mandatory emergency notification/call-in. Includes work extension numbers, private home phone numbers, and individuals' beeper numbers.

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).

Emergency Response Personnel Telephone List which includes selected IP-3 employees' private home phone numbers who have been trained in specific emergency responsibilities.

Private home phone numbers of all IP-3 employees listed by department.

ROSTER III Note: Rosters I, and II only have been updated this revision.

VOLUME II TABLE OF CONTENTS 07/11/02 ENTERGY NUCLEAR NORTHEAST INDIAN POINT NO.

3 NUCLEAR POWER PLANT EMERGENCY PLAN -

VOLUME II EMERGENCY RESPONSE ACTIVATION TABLE OF CONTENTS IC/EAL'S INITIATING CONDITIONS AND EMERGENCY ACTION LEVELS CONTROL ROOM IP-2000 Emergency Activation of the Control Room (CR)

IP-2001 Emergency Director (ED),

Plant Operations Manager (POM),

Shift Manager (SM)

Procedure IP-2002 CR Health Physics Technician IP-2003 CR Watch Chemist IP-2004 CR Clerk IP-2005 CR Offsite Communicator IP-2006 CR Direct-Line Communicator TECHNICAL SUPPORT CENTER (TSC)

IP-2100 Emergency Activation of the Technical Support Center (TSC)

IP-2101 Technical Support Center (TSC)

Manager IP-2102 TSC Communicator(s)

IP-2103 TSC SPDS Computer Operator IP-2104 TSC Video Operator IP-2105 TSC Accountability Officer IP-2106 TSC Clerk OPERATIONS SUPPORT CENTER (OSC)

IP-2200 Emergency Activation of the Operations Support Center (OSC)

IP-2201 Operations Support Center (OSC)

Manager IP-2202 OSC Direct-Line Communicator IP-2203 OSC Dispatcher IP-2204 OSC Team Leaders IP-2205 OSC H.P.

Team Leader IP-2206 OSC Accountability Officer IP-2207 OSC Clerk IP-2208 OSC Security Team Leader IP-2209 OSC H.P. Technician IP-2210 OSC Dosimetry Technician TP-2211 OSC Chemistry Team Leader REV.

/

DATE 9

07/02 4

09/98 15 05/02 3

02/99 6

07/02 3

09/00 2

06/01 4

10/99 4

11/00 9

02/01 3

12/98 4

08/99 2

06/01 VOID -

N/A 5

06/99 6

11/00 8 2 3

3 8

VOID 5

4 4

3 2

02/01 12/98 07/02 06/02 10/99 N/A 06/99 03/02 12/97 06/98 03/00

VOLUME II TABLE OF CONTENTS 07/11/02 ENTERGY NUCLEAR NORTHEAST INDIAN POINT NO.

3 NUCLEAR POWER PLANT EMERGENCY PLAN -

VOLUME II EMERGENCY RESPONSE ACTIVATION TABLE OF CONTENTS EMERGENCY OPERATIONS FACILITY (EOF)

IP-2300 Emergency Activation of the Emergency Operations Facility (EOF)

IP-2301 Emergency Director Replaced by IP-EP-255 IP-2302 EOF Technical Advisor and Information Liaison IP-2303 EOF Radiological Assessment Team Leader (RATL)

IP-2304 EOF Dose Assessment Health Physicist IP-2305 EOF MIDAS Operator IP-2306 EOF Security Officer IP-2307 EOF Clerk IP-2308 EOF Direct-Line Communicator IP-2309 EOF Offsite Communicator IP-2310 EOF Onsite Radiological Communicator IP-2311 EOF Offsite Radiological Communicator IP-2312 EOF Public Relations Liaison IP-2313 EOF Public Relations Technical Advisor IP-2314 EOF Radiological Assessment Monitor ALTERNATE EMERGENCY OPERATIONS FACILITY (AEOF)

IP-2400 Emergency Activation of the Alternate Emergency Operations Facility (AEOF)

Replaced by IP-EP-251 SECURITY ACTIVATION IP-2500 Security Emergency Activation Responsibilities RECOVERY/TERMINATION IP-2600 Emergency Termination and Transition to Recovery Replaced by IP-EP-610 IP-2601 Recovery Manager Replaced by IP-EP-610 IP-2602 Development of a Recovery Action Plan Replaced by IP-EP-610 IP-2603 Recovery Support Group Manager REV.

/

DATE 5

11/00 VOID -

N/A 10 5

5 4

7 5

4 4

3 4

VOID VOID VOID 07/02 11/00 07/02 03/00 12/98 10/99 03/00 09/00 03/00 06/99 N/A N/A N/A VOID -

N/A 11 05/02 VOID -

N/A VOID -

N/A VOID N/A 1

07/02 EP-FORMS SECTION -

Index 07/02 APPENDIX

'A' APPENDIX

'B' APPENDIX

'C' ROSTER I ROSTER II ROSTER III Emergency Offsite Telephone List Emergency Response Facility Telephone List 07/02 07/02 06/02 06/02 06/02

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 2.1 The Shift Manager (SM),

and/or Emergency Director (ED) shall 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.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 If the Emergency Action Level is not clear, reference the Emergency Action Levels Technical Bases for clarification.

It is located in the CR with Emergency Plan procedures.

c.

upon determining the emergency classification, the SM or CRS 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 ensure that proper protective and corrective actions are taken.

The initial emergency classification will normally be made by the SM.

It is the SM's primary responsibility to act in accordance AP-21 to ensure that necessary actions are taken to return equipment or systems to a safe, stable condition.

The emergency classification shall not interfere with this primary responsibility.

An event that occurs and ends in a very short period of time, or an event occurs and goes unnoticed until after an event has terminated, must still be classified and required notification to the NRC,

State, and counties made.

The implementation of the emergency plan should be 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

A.

If reclassification to a higher level is necessary, the ED shall repeat the classification steps above ensuring input 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.

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.

5.0 ATTACHMENTS 5.1 Initiating Conditions and Emergency Action Levels END OF TEXT Initiating conditions and EALS Ký Ký Page 3 of 3

.1 Indian Point 3 Emergency Action Levels CATEGORY 1.0 CSFST STATUS volume II Initiating conditions and Emergency Action Levels Rev. 9 category General II -'1.1 subcri ti cal i ty 1.2 core cooling 1.3 Heat Sink 1.4 Integrity 1.5 Containment 1.1.3 {1,2,3}

RED path in F-0.1, subcriticality AND Actual or imminent entry into EITHER:

RED Path in F-0.2, Core Cooling OR Red Path in F-0.3, Heat Sink 1.2.2 {1,2,3,4}

RED path in F-0.2, core cooling AND Functional restoration procedures not effective within 15 minutes.

1.5.1 {1,2,3,4}

Red Path F-0.5, Containment resulting from loss of coolant.

site Area Alert unusual

_______I.

1.1.2 {1,2,3}

RED path in F-0.1 subcri ti cal i ty 1.2.1 {1,2,3,4}

ORANGE or RED path in F-0.2, Core cooling 1.3.1 {1,2,3,4}

RED path in F-0.3, HEAT SINK AND Heat sink is regui red 1.1.1 {1,2,3}

Any Failure of an automatic trip signal to reduce power range

< 5%

AND Manual trip is successful 1.4.1 {1,2,3,4}

Red Path on F-0.4, Integrity I

a ______

= Power operation

= Startup

= Hot standby 4 = Hot shutdown Tab7e continued -

Next Paqe 5 = cold shutdown 6 = Refueling unusual Event 1

2 3

I Ale rt

.1 Indian Point 3 Emergency Action Levels CATEGORY 2.0 REACTOR FUEL volume II Initiating conditions and Emergency Action Levels Rev.

9 Category 2.1 coolant Activity 2.2 Containment Radiation General 2.2.3 {1,2,3,4}

Containment Radiation monitor R 25 or R-26

> 68 R/HR

-I site Area 2.1.3 {1,2,3,4}

Coolant activity

> 300 jici/cc dose equivalent 1-131 AND any of the following:

• RED path on F-0.4, Integrity

• Primary system leakage

> 75 gpm

• RCS subcooling < SI initiation setpoint

• > 0.06 pCi/cc on R-11 or R-12 due to RCS leakage 2.2.2 {1,2,3,4}

Containment Radiation monitor R-25 or R-26

> 17 R/HR I

-

I 1.1.1 t+/-,L0,'U

> 0.06 g.ci/cc on R 11 or R-12 due to 2.1.1 {1,2,3,4}

coolant sample activity:

> 1.0 ici/cc dose equivalent 1-131 OR

> 100/(E Bar) gci/cc for all noble gases with half-lives >10 minutes I

a 1 = Power Operation 2 = Startup 3 = Hot standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table Continued - Next Page Unusual Event Ale rt RCS leakage.

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 2.0 REACTOR FUEL Category General site Area Alert Unusual Event 2.3 Refueling 2.3.2 {1,2,3,4,5,6}

2.3.1 Acci dents confirmed sustained

{1,2,3,4,5,6}

or other alarm on ANY of the Spent fuel pool Radiation following radiation (reactor cavity moniators monitors resulting during refueling) 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 2 = startup 3 = Hot standby 4 = Hot Shutdown 5 = cold Shutdown 6 = Refueling Table Continued - Next Page

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 3.0 REACTOR COOLANT SYSTEM 1*

unusual Event Category 3.1 RCS Leakage

[NOTE: This includes Primary to secondary Leakage]

3.2 Primary to secondary Leakage

[NOTE: For Primary to secondary Leakage, Category 3.1 also applies.]

3.3 RCS subcooling General site Area Alert

I.

1 1 3.1.1 {1,2,3,4}

3.1.3 RVLIS

> 33%

with t remove Ievel droppi and co

{1,2,3,4,5,6}

cannot be maintained with no RCP's running OR he reactor vessel head d, it is reported that water in the reactor vessel is ng in an uncontrolled manner re uncoverv is likely 3.2.2 {1,2,3,4}

unisolable release of secondary side to atmosphere from the affected steam generator(s) with primary to secondary leakage > 75 gpm 3.2.3 {1,2,3,4}

unisolable release of secondary side to atmosphere from the affected steam generator(s) with primary to secondary leakage > 0.3 gpm in any steam generator AND Coolant activity > 300 pCi/cc of dose equivalent 1-131 L___ ___

__I 3.1.2 {1,2,3,4}

Primary system leakage exceeding the capacity (75 gpm) of a single charging pump

1 ___________________

3.3.1 {1,2,3,4}

RCS subcooling < SI initiation setpoint due to RCS leakage

-j 3.1.1 11,2,3,41 unidentified or ressure boundary eakage

> 10 gpm OR Identi fi ed leakage

> 25 gpm 3..

{12,,4 3.2.1 11,2,3,41 unisolable release of secondary side to atmosphere from the affected steam generator(s) with primary to secondary leakage

> 0.3 gpm in any steam generator.

1 = Power Operation 2 = Startup 3 = Hot standby 4 = Hot shutdown 5 = Cold shutdown 6 = Refueling Table continued - Next Page I

I Unusual Event

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 4.0 CONTAINMENT I

I.

I I AThrt I IInhicii] Fvent Category lGeneral 4.1 Containment Integrity Status 4.1.4 {1,2,3,4}

confirmed Phase "B" isolation signal following confirmed LOCA with less than minimum containment cooling safe uards equipment operating, Table 4.3 AND Any indicators of fuel clad loss, Table 4.1 4.1.5 {1,2,3,4}

EITHER:

Rapid, uncontrolled decrease in containment pressure following initial increase due to RCS 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 4 ~ ~

~

~

~

~

~

~ ~

nsa Event 4.1.2 {1,2,3,4}

Rapid, uncontrolled decrease in containment pressure following initial increase due to RCS failure OR LOSS of primary coolant inside containment with containment pressure or sump level response not consistent with LOCA conditions I1 1

I___

4.1.1 {1,2,3,4}

Both doors open for > 4 hrs.

Of Inability to clc pressure relief which results ir release pathway environment for

> 4 hrs.

on a vc airlock t )se containment or purge valves Sa radiological to the OR Any Phase "A" or Phase "B" or containment ventilation isolation valve(s) not closed when required which results in a radiological release pathway to the environment 1 = Power Operation 2 = startup 3 = Hot standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Tab7e continued - Next Page Ilnll*ll::tl Fv*nt

^I *rt

^

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 4.0 CONTAINMENT r

1 1

Al rt iiniiii1 Event Category jGeneral 4.1 Containment Integrity Status (Continued) 4.2 SG Tube Rupture w/

secondary Release 4.1.6 {1,2,3,4}

Either:

Any Phase "A" or Phase"B" or CVI valve (s) not closed when required following confirmed LOCA OR Inability to isolate any primary system discharging outside containment AMD Radiological release to the environment exists as a result AND Any indicators of fuel clad damage, Table 4.2 4.2.2 {1,2,3,4}

unisolable secondary side line break with SG tube rupture as identified in E-3 "Steam Generator Tube Rupture" AND Any Indicators of fuel clad damage, Table 4.2 4.1.3 {1,2,3,4}

Either:

Any Phase "A" or Phase "B' or CVI valve(s) not closed when requi red following confirmed LOCA OR Inability to isolate any rimary system ischarging outside containment.

AND Radiological release to the environment exists as a result 4.2.1 {1 2,3,4}

unisolable faulted (outside vc) ruptured steam generator I

I 4.3 combustible 4.3.1 11,2,3,41 Gas

> 4% Hydrogen concentration in concentrations contai nment 1 = Power Operation 2 = Startup 3 = Hot Standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table Continued - Next Page A I dart*

unHsual Event I zo i t e iA i e a 1.

IlnlJ*llal Event A1,*rt

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 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

1 = Power Operation 2 = Startup 3 = Hot Standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table Continued - Next Page

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 5.0 RADIOACTIVITY RELEASE Category 5.1 EMfluent monitors 5.2 Dose Proiections/

Environmental Measurements/

Release Rates r

I Al rt-1-unusual Event I General 1 D CM C

5.1.4 t1,2,3,4,5,61 A valid reading on any monitors Table 5.1 column "GE" for > 15 minutes unless dose assessment can confirm releases are below Table 5.2 column "GE" within this time period.

5.1.3 {1,2,3,4,5,6}

A valid reading on any monitors Table 5.1 column "SAE" for > 15 minutes unless dose assessment can confirm releases are below Table 5.2 column "SAE" within this time period.

I 4.

5.2.5 11,2,3,4,5,61 Dose projections or field surveys resulting from actual or imminent release which indicate doses / dose rates >

Table 5.2 column "GE" at the site boundary or beyond.

5.2.4 {1,2,3,4,5,61 Dose projections or field surveys resulting from actual or imminent release which indicate doses dose rates > Table 5.

column "SAE" at the site boundary or beyond.

/ 2 Aler2t1,,45}

5.1.2{1,2,3,4,5,6}

A valid reading on any monitors Table 5.1 column "Alert for

> 15 minutes unless dose assessment can confirm releases are below Table 5.2 column "Alert" within this time period.

5.2.2 1,2,3,4,5,61 confirmed sample analysis for gaseous or liquid release rates

> 200 x improved technical specifications limits for

> 15 minutes 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 t

1 unusual Event A valid reading on any monitors Table 5.1 column "NUE" for

> 60 minutes unless sample analysis can confirm release rates

< 2 x improved technical specifications within this time period.

5.2.1 {1,2,3,4,5,bl confi rmed sample analysis for gaseous or liquid release rates

> 2 x improved technical speci-fications limits for

> 60 minutes.

_ I _

I _

I

__I_

1 = Power Operation 2 = Startup 3 = Hot standby 4 = Hot shutdown 5 = cold Shutdown 6 = Refueling Table continued - Next Page A1

• rt 4

m I

I Genera I

• I I.* *

• a I

I I

f

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CfiTF(ARY

O RADIOACTIVITY RELEASE

'I I

I

(

C-t-a Ar2 A1 P rt

ate gory igenerl i

5.3 Area Radi ati on Level s 5.3.2 {1,2,3,4,5,6}

Sustained area Radiation levels >

15 Mr/hr in EITHER:

control Room OR 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 2 = Startup 3 = Hot standby 5.3.1 {1,2,3,4,5,6}

Any sustained direct ARM reading > 100 x alarm or offscale high resulting from an uncontrolled process 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table continued - Next Page rATPnORY 5 0 unusual Event

.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 5.0 RADIOACTIVITY RELEASE Table 5.1 Effluent monitor classification Thresholds monitor GE SAE A1lert NUE R-27 360 ci/sec 36.0 Ci/sec 3.6 ci/sec 7.24E4gCi/sec R-14 N/A N/A N/A 2.72E-3pci/cc R-19 N/A N/A 475 ýici/cc 9.50_ Fci/cc 1 = Power Operation 2 = Startup 3 = Hot standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table Continued - Next Page Table 5.3 Plant Areas

• Auxiliary Feedpump Building

• P.A.B.

• Fuel storage Building

• Control Building oService Water Pumps oRefueling water Tank

• Diesel Fuel Tank

• vital Area Access to Contai nment

• Appendix R Diesel Generator oBackup Service Water Tabl e 5.2 Dose Projection/Env. Measurement classification Thresholds GE SAE Alert TEDE 1000 mRem 100 mRem 10 mRem CDE Thyroid 5000 mRem 500 mRem N/A External Exposure Rate 1000 mRem/hr 100 mRem/hr 10 mRem/hr Thyroid exposure rate (for 1 5000 mRem/hr 500 mRem/hr N/A hr. of inhalation)

I II

AttachmenL 5.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev.

9 CATEGORY 6.0 ELECTRICAL FAILURES Category General site Area Alert unusual Event 6.1 LOSS of 6.1.5 {1,2,3,4}

6.1.4 {1,2,3,4}

6.1.2 {5,6 or Defueled}

6.1.1 {1,2,3,4,5,6}

AC Power Loss of all Loss of all safeguard bus Loss of all safeguard bus AC safeguards buses not Sources safeguard bus AC AC power power > 15 minutes.

capable of being power

> 15 minutes.

powered from at least AND EITHER:

6.1.3 {1,2,3,4}

one of the following Power restoration 480V safeguard bus power sources for > 15 to any emergency supplies REDUCED TO ONLY ONE minutes:

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 13W92 feeder F-O.2, Core e Appendix R Diesel cooli ng" unit Auxiliary

• 13W93 feeder transformer a Station Auxiliary transformer

• 13W92 feeder a 13W93 feeder 6.2 Loss of 6.2.2 {1,2,3,4}

6.2.1 {5,6}

DC

< 105 vdc bus voltage

< 105 vdc bus Power indications for voltage indications Sources

> 15 minutes on the for > 15 minutes 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 2 = Startup 3 = Hot Standby 4 = Hot Shutdown 5 = cold shutdown 6 = Refueling Table Continued - Next Page

Attachmer,_

3.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 7.0 EQUIPMENT FAILURES 1 = Power Operation 2 = Startup 3 = Hot Standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table continued - Next Page Category General site Area Alert Unusual Event 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 System 7.2.5 {1,2,3}

7.2.2 {1,2,3}

7.2.1 {1,2,3}

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

Attachmer.

j.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev.

9 CATEGORY 7.0 EQUPMENT FAILURES 1 = Power Operation 2 = Startup 3 = Hot Standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table Continued - Next Page 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)

Attachmer,.

5.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 7.0 EQUIPMENT FAILURES 1 = Power Operation 2 = Startup 3 = Hot standby 4 = Hot Shutdown 5 = cold Shutdown 6 = Refueling Table Continued - Next Page 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

Attachmer,-

'.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS I _______________

J _____________

1 = Power Operation 2 = Startup 3 = Hot Standby 4

5 6

= Hot Shutdown

= cold Shutdown

= Refueling Table continued - Next Page 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

1. 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

Attachmet.

j.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS 1 = Power Operation 2 = Startup 3 = Hot Standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table continued - Next Page 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

Attachmer

.1 Indian Po,,.c 3 Emergency Action Levels folume II Initiating -onditions and 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 2 = startup 3 = Hot Standby 4 = Hot Shutdown 5 = cold shutdown 6 = Refueling Table continued - Next Page

AttachmenL J.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and 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 2 = Startup 3 = Hot Standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table continued - Next Page

Attachment a.1 Indian Point 3 Emergency Action Levels jol ume II Initiating Conditions and Emergency Action Levels Rev. 9 CATEGORY 8.0 HAZARDS 1 = Power operation 2 = Startup 3 = Hot standby 4 = Hot shutdown 5 = cold shutdown 6 = Refueling Table continued - Next Page 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

Attachmer.

,.1 Indian Point 3 Emergency Action Levels volume II Initiating conditions and Emergency Action Levels Rev. 9 CATEGORY 9.0 OTHER Category General site Area (Alert Unusual Event 9.1 other 9.1.7 {1,2,3,4,5,6}

9.1.5 {1,2,3,4,5,6}

9.1.3 9.1.1 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 Any event, as determined by shift Manager or Emergency 9.1.4 {1,2,3,4}

9.1.2 {1,2,3,4}

the Shift Manager or Director, that could lead or has Any event, as Any event, as Emergency Director, that led to determined by the determined by the could lead or has led to a EITHER:

shift Manager or Shift Manager or loss of any two fission LOSS or potential loss of both Emergency Director, Emergency Director, product barriers and loss or fuel clad and RCS barrier that could lead or that could lead to potential loss of the third OR has led to a loss a loss or potential Loss or potential loss of either or potential loss loss of containment fuel clad or RCS barrier in of either fuel clad conjunction with a loss of or RCS barrier containment 1 = Power Operation 2 = Startup 3 = Hot Standby 4 = Hot Shutdown 5 = cold shutdown 6 = Refueling

En tePRO EMERGENCY PLAN PROCEDURES PROCEDURE NO.

IP-2003 CR WATCH CHEMIST WPTmT1 THIS PROCEDURE IS TSR X

THIS PROCEDURE IS NOT TSR REVIEWED BY:

APPROVED BY:

EFFECTIVE DATE.7Z SIGNATURE/DATE NAUiA "9/1/02-E TITLE:

REV.

6 PROCEDURE USE IS REFERENCE u

I If

Volume II IP-2003 Rev. 6 CR WATCH CHEMIST TABLE OF CONTENTS Section Title Page 1.0 P U R P O S E................................................................................................

3 2.0 RESPONSIBILITIES...................................................................................

3 3.0 R E F E R E N C E S...........................................................................................

. 3 4.0 P R O C E D U R 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 I P-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).

From the desktop E-Plan folder, double click on Connect to Met Tower.

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.

Provide EP-Form Part I to the ED for review.

After the ED has reviewed the EP-Form Part I, provide the form to the clerk for faxing.

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.

Provide EP-Form Part I to the ED for review.

After the ED has reviewed the EP-Form Part I, provide the form to the clerk for faxing.

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

En tergy EMERGENCY PLAN PROCEDURES PROCEDURE NO.

IP-2302 REV.

10 TITLE:EOF TECHNICAL ADVISORS AND INFORMATION LIAISONS THIS PROCEDURE IS TSR X

THIS PROCEDURE IS NOT TSR WRITTEN BY:

- IGNATURE/DATE REVIEWED BY *

!G N**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 SECTION TITLE PAGE 1.0 Purpose 1

2.0 Responsibilities 1

3.0 References 1

4.0 Procedure 2

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)"

Page 1 of 2 IP-2302

Page 2 ol 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

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.

7.

IF relocation to the Alternate EOF (AEOF),

THEN support as necessary.

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

1. 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:

a.

Turn OFF the RAMTEK power (EOF) or the main power (AEOF).

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.

IF the above step fails, THEN contact the TSC (X 8710) and inform the CCR.

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

• AEOF For Level 4 logon, Type AYEOF, press RETURN OR For Level 5 login, Type AEOF, 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:

a.

TYPE CPR7 (EOF) or CPR8 (AEOF).

b.

PRESS the ADDR key.

c.

TYPE 7 (EOF) or 8 (AEOF),

and PRESS the VALUE ONE 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 I

Unusual Event RCS Temp:____

°F Pressure:

PSIG L]

Al RVLIS / Pressurizer Level:

[] 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

1. of Onsite Teams

1. of Offsite Teams Fission Product Barrier Status Accountability Completed At:

Barrier Intact Challenged Lost

1. 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:

Q__

I Employee UJ Contractor Status of other IP Unit:

Type of 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:

I I

By:

__Name pate

]

-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 Recovery Support Group Manager THIS PROCEDURE IS TSR THIS PROCEDURE IS NOT TSR WRITTEN BY:

REVIEWED BY:

APPROVED BY:

EFFECTIVE DATE:

SIGNATURE/DATE IGNATURE/DATE a

S I6 ?RE/

DATE TITLE:

ý&~~~~

kir 1DL I L8JoZ PROCEDURE USE IS REFERENCE

,I

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 Page 1 of 3 IP-2603

Page 2 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

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 Page 3 of 3 IP-2603

VOLUME II IP-2603 Rev.

1 Page 1 of 1 ATTACHMENT 5.1 RECOVERY SUPPORT GROUP MANAGER INITIAL ACTIONS When the Recovery Support Group Manager receives an emergency notification via beeper from IP, respond by telephoning the number on the pager and the IP-3 Security to determine the nature of the emergency.

(Refer to Volume II, Appendix C for IP-3 Security Command Post (CAS) telephone number).

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)

EP-FORM #

EP-FORM TITLE 22 Determination of Radioactive Airborne Concentrations 23 Team Status Form 27 Offsite Survey Team Data Part I New York State Radiological Emergency Data Form, Part I - General Information Part II New York State Radiological Emergency Data Form, Part II

- Radiological Assessment Data 31a Plant Status Log (measurements) 31b Plant Status Log (rad. monitors) 31c Plant Status Log (equipment status) 40 Manual Dose Projection Worksheet 42 EOF Radiological Survey Form 45 EOF Personnel Dosimetry Record 47 Visitors Log 48 RADCOM Worksheet 361 (NRC Form)

Event Notification Worksheet CORRESPONDING PROCEDURE N/A N/A N/A IP-1038 IP-1038 N/A N/A N/A N/A N/A N/A N/A N/A IP-1038 ii DATE 04/96 02/98 02/98 09/01 09/01 02/97 09/99 02/97 12/93 11/94 02/98 11/94 02/98 03/90

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 #

PROCEDURE TITLE REV.

DATE Dose Assessment IP-1001 Determining the Magnitude of Release VOID N/A Replaced by IP-EP-310 IP-1002 Post-Accident Monitoring of Noble Gas 4

02/99 Concentration in Plant Vent IP-1003 Obtaining Meteorological Data Replaced by IP-EP-510 IP-1004 Midas Computer System Replaced by IP-EP-510 Environmental Monitoring IP-1011 Offsite Monitoring/Site Perimeter Surveys 24 05/99 IP-1012 Emergency Airborne Activity Determination 4

02/99 IP-1015 Post-Accident Environmental Sampling and 7

12/98 Counting Protective Actions IP-1017 Protective Action Recommendations for VOID N/A the Offsite Population Replaced by IP-EP-410 IP-1019 Emergency Use of Potassiun Iodide (KI) 9 11/97 Personnel Injury IP-1021 Radiological Medical Emergency 25 06/98 IP-1023 Use and Set Up of the IP3 Personnel Decon VOID N/A Suite Damage Assessment IP-1025 Repair and Corrective Action Teams 12 12/98 IP-1027 Emergency Personnel Exposure 12 12/97 IP-1028 Core Damage Assessment 9

06/98 Notification and Communication IP-1038 Offsite Emergency Notifications 26 09/01 IP-1039 Emergency Response Data System (ERDS) 4 02/01 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 #

PROCEDURE TITLE REV.

DATE Emergency Response Facilities IP-1040 Habitability of the Emergency Response 16 11/97 Facilities and Assembly Areas IP-1041 Personnel Monitoring for EOF,

TSC, OSC VOID N/A and Control Room Personnel Accountability and Evacuation IP-1050 Accountability 27 04/02 IP-1053 Evacuation of Site 13 03/02 IP-1054 Search and Rescue Teams 10 12/97 Non-Radiological Emergencies IP-1052 Hazardous Waste Emergency 8

07/02 IP-1055 Fire Emergency Response is 04/02 IP-1056 Directing Fire Fighting Personnel in VOID N/A Controlled Area IP-1057 Natural Phenomena Emergency 8

10/01 IP-1058 Earthquake Emergency VOID N/A IP-1059 Air Raid Alert 7

05/01 H.P. Release Surveys and Decontamination IP-1060 Personnel Radiological Check and 11 02/98 Decontamination IP-1063 Vehicle/Equipment Radiological Check 11 11/97 and Decontamination Emergency Equipment and Maintenance IP-1070 Periodic Inventory of Emergency Plan 31 02/01 Equipment IP-1076 Roster Notification Methods 26 05/02 IP-1080 Conduct of Emergency Exercises and Drills VOID N/A IP-1085 Maintenance of Emergency Preparedness VOID N/A at IP-3 ii

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