Text

Revised Epips, Including TOC, Rev. 11 to IP-1024 & Rev. 6 to IP-1030
	ML022130098
Person / Time
Site:	Indian Point
Issue date:	07/11/2002
From:	Inzirillo F, Walker C, Wilson M; Entergy Nuclear Indian Point 2, Entergy Nuclear Indian Point 3 LLC
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2003-0379, FOIA/PA-2003-0388
	Download: ML022130098 (79)
	v • d • e

TO:

IaOIug "ICHL LontrOlu 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.

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 #

Document Name New Rev.

Old Rev.

Instructions Docmet Dcuen Nme#/

Date

/ Date U2 EP Implementing Procedures TOC Emergency Plan Implementing 6/10/02 7/11/02 Replace entire document Procedures Table of Contents 11 IP-1007 Dose Assessment Cancel 11 Remove entire document 3/26/01 IP-1013 Protective Action Cancel 8

Remove entire document Recommendations 11/1/99 12 IP-1016 Obtaining Meteorological Data Cancel 9/1/99 Remove entire document Obtaining Meteorological, 5

IP-1022 Radiological and Dose Assessment Cancel 9/1/99 Remove entire document Data 11 10 IP-1024 Emergency Classification Replace entire document 7/11/02 6/10/02 6

5 Relceniedcmt IP-1030 Emergency Operations Facility 7/11/02 9/6/01 Replace entire document Modular Emergency assessment &

0 IP-1033 Notification System (MEANS)

Cancel 3/26/0 1 Estimation of Population Dose 6

IP-1036 within the 10 Mile Emergency Cancel 9/1/99 Remove entire document Planning Zone A50,0

Update completed as specified:

Signature of Controlled Copy Holder Date

Page:

1 II-JUL-02 DISTRPIBUTION CONTROL LIST O cument Name:

EMER PLAN DEPT CCNAME NAME 1

2 3

4 9

10 Ii 14 16 19 22 23 24 25 28 29 30 31 32 S

33 34 35 41 319 354 37E 424 51 51:

51:

51 51 51 51 52 52 52 52 52 PLANT MANAGER'S OFFICE EP/TRAINING ADMINISTRATOR RES DEPARTMENT MANAGER REFERENCE LIBRARY JOINT NEWS CENTER SHIFT MGR. (LUB-001-GEN)

CONTROL ROOM & MASTER EOF AEOF/A. GROSJEAN NUC ENGINEERING LIBRARY RESIDENT INSPECTOR MCNAMARA N MCNAMARA N DOCUMENT CONTROL DESK AVRAKOTOS N E-PLAN STAFF E-PLAN STAFF BARANSKI J(VOLUME I ONLY)

MURPHY L -(VOLUME I ONLY)

LONGO N (VOLUME I ONLY)

GREENE D (VOLUME I ONLY)

RAMPOLLA M(VOLUME I ONLY)

SIMULATOR C. STELLATO L.GRANT 3 E-PLAN STAFF I OPS-INSTR (LL'S 1 COPY) 0 L.GRANT 1 L.GRANT 2 C.STELLATO 3 C. STELLATO 7 PLANT MANAGER'S OFFICE 8 DOCUMENT ROOM 9 TSC 0 CONTROL ROOM (UNIT 2) 1 SIMULATOR (UNIT 2) 2 NRC RESIDENT (UNIT2) 3 ROBERT VOGLE (UNIT 2) 4 JOHN MCCANN (UNIT 2)

UNIT 3 /ADMINISTRATION 4

TRAINING RES DEPARTMENT 4

RECORDS(TRNG BLDG)

EMERGENCY PLANNING OPERATIONS OPS(3PT-DO01-DO06 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 LJOCATION 5-3-B

48 L5-4-A f48

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

48

48 EOF

48

48

48

48

48 IP2 UNIT 2 IP2 IP2 48-2-A IP2 OFFSITE IP2

Unit 2 Emergency Plan Implementing Procedures Table of Contents IP-1001 Mobilization of Onsite Emergency Organization IP-1002 Emergency Notification and Communication Planned Discharge of Containment Atmosphere During Accident IP-1003 Conditions

.4-Post Accident Offsite Environmental Surveys, Sampling and Counting Cancelled - Replaced by IP-EP-310 Personnel Radiological Check and Decontamination Radiological Check and Decontamination of Vehicles Central Control Room Joint News Center Onsite Medical Emergency Cancelled - Replaced by IP-EP-410 Radiological Check of Equipment Before It Leaves the Site Radiological Surveys Outside the Protected Area (Title Change)

Cancelled - Replaced by IP-EP-510 Coordination of Corporate Response Airborne Activity Determination Manual Update, Readout and Printout of Proteus Plant Parameter Data Cancelled - Replaced by IP-EP-510 ODerations Support Center (OSC)

IP-1 024 Emergency Classification IP-1025 Cancelled IP-1 026 Emergency Data Acquisition Personnel Accountability and Evacuation IP-i1030 Emergency Operations Facility (EOF)

IP-1033

[Cancelled - Replaced byIPE-2 As of 7/11/02 IP-1004 IP-1007 IP-1008 IP-1009 IP-1010 IP-1011 IP-1012 IP-1013 IP-1014 IP-1015 IP-1016 IP-1019 IP-1020 IP-1021 IP-1022 IP-1 023 IP-1 027 Page 1 of 2 13 5/25/01 26 5/30/02 7

4/16/01 5

9/1/99 7

4/29/02 7

9/1/99 5

5/30/02 7

6/402 10 5/25/01 6

9/1/99 9

3/26/01 10 9/6/01 8

01/12/01 6

4/29/02 18 4/11/02 11 7/11/02 0

01/12/01 16 4/11/02 6

7/11/02 Cancelled-Replaced by IP-EP-310 Personnel Radiological Check and Decontamination

Unit 2 Emergency Plan Implementing Procedures Table of Contents Technical Support Center (TSC) 16 2/20/01 IP-1036 Cancelled - Replaced by IP-EP-620 IP-1037 Cancelled - Replaced by IP-EP-510 IP-1039 Offsite Contamination Checks 9

01/12/01 IP-1045 Cancelled - Replaced by IP-EP-251 IP-1047 Cancelled - Replaced by IP-EP-510 IP-1048 Cancelled - Replaced by IP-EP-610 IP-1050 Security 3

4/11/02 As of 7/11/02 IP-1035 Page 2 of 2

I P-1 024 Rev. 11 ENTERGY INDIAN POINT STATION EMERGENCY PLANNING EMERGENCY CLASSIFICATION Prepared by:

Technical Reviewer:

Reviewer:

SNSC Review:

Approval:

C. Kelly Walker Print Name SPnt V1Name Print Name Print Name Print Name Meeting Number Frank Inzirillo Print Name Signature ignature Signature Signature Signature

"-7f(/0 I-..

Date Date Date Date Date at Uate Effective Date:

') /

O//-.z Biennial Review Reviewer/Date Reviewer/Date IP-1024 (Class) R11.doc Page 1 of 24

Emergency Classification IP-1 024 Rev. 11 EMERGENCY CLASSIFICATION 1.0 PURPOSE To describe the method for classification of emergencies as a Notification of Unusual Event (NUE), Alert, Site Area Emergency (SAE) or General Emergency (GE).

2.0 DISCUSSION 2.1 The symptom, event or barrier base classification may be made for NUE, Alert, Site Area or General Emergency, using Attachment 2.

2.2 IF a symptom, event or barrier base classification has been declared in a category followed by the same classification in another category THEN the classification continues to apply but an update should be made to offsite authorities in accordance with Reference 6.2.

2.3 IF a symptom, event or barrier based classification has been declared in a category followed by an increased classification THEN the higher classification shall be declared AND offsite authorities shall be notified in accordance with Reference 6.2.

2.4 Many of the classifications derived from the Reference 6.3 methodology are fission product barrier based. That is, a condition based upon loss or potential loss of one or more of the three fission product barriers. (Fuel cladding, RCS and Containment).

Refer to Attachment 1.

2.5 The following criteria serves as bases for event classification related to fission product barrier loss:

2.5.1 Unusual Event - any loss OR potential loss of containment.

2.5.2 Alert - Any loss OR potential loss of fuel clad or RCS.

2.5.3 Site Area Emergency - Any loss of both fuel clad AND RCS OR any potential loss of EITHER fuel clad OR RCS with a loss of any addition barrier.

2.5.4 General Emergency - Loss of any two barriers with loss OR potential loss of a third.

2.6 Event based classifications refer to occurrences with potential safety significance such as failure of Safety Injection pumps, safety valve failures, or electric power failures.

2.7 The symptom based classifications refer to those indicators that are measurable over a continuous spectrum, such as, core temperature, coolant levels and containment pressure.

2.8 The Technical Bases Document provides an explanation and rational for each of the Emergency Action Levels (EALs). This document is also used by individuals who are responsible for the implementation of this procedure as a technical reference and aid in EAL interpretation.

2.9 The EALs are grouped into nine categories to simplify their presentation and promote a Page 2 of 24

Emergency Classification IP-1024 Rev. 11 rapid understanding by their users. These categories are:

Category 1 CSFST Status Category 2 Reactor Fuel Category 3 Reactor Coolant System Category 4 Containment Category 5 Radioactivity Release/Area Radiation Category 6 Electrical Failures Category 7 Equipment Failures Category 8 Hazards Category 9 Other 2.10 Categories one through five are primarily symptom based.

The symptoms are indicative of actual or potential degradation of either fission product barriers or personnel safety.

2.11 Categories six, seven and eight are event based. Electrical Failures are those events associated with losses of either AC or vital DC electrical power. Equipment Failures are abnormal and emergency events associated with vital plant system failures, while hazards are those non-plant system related events which have affected or may affect plant safety.

2.12 Category nine provides the Emergency Director (Shift Manager) the latitude to classify and declare emergencies based on plant symptoms or events which in his judgment warrant classification. This judgment includes evaluation of loss or potential loss of one or more fission product barriers warranting emergency classification consistent with the barrier loss criteria as specified in section 2.5.

2.13 Categories are further divided into one or more subcategories depending on the types and number of plant conditions that dictate emergency classifications. For example, the Electrical Failures category has two subcategories whose values can be indicative of losses of electrical power sources. Loss of AC power sources and loss of DC power sources. An EAL may or may not exist for each subcategory at all four classification levels.

Similarly, more than one EAL may exist for a subcategory in a given emergency classification when appropriate (i.e. no EAL at the General Emergency level but three EALs at the Unusual Event Level).

2.14 The operating modes of operation are defined as follows:

2.14.1 Power Operations -When the reactor is critical and the neutron flux power range instrumentation indicates greater than2% of rated power.

2.14.2 Hot Shutdown -When the reactor is sub-critical by an amount greater than or equal to the margin as specified in Technical Specification 3.10 and Tayg is greater than 200°F and less than or equal to 5550F.

Page 3 of 24

Emergency Classification IP-1024 Rev. 11 2.14.3 Cold Shutdown -When the reactor is sub-critical by at least 1 % Ak/k and Tavg is less than or equal to 2000F.

2.14.4 Refuel -Any operation involving movement of core components when vessel head is completely unbolted.

2.15.5 Defueled - Reactor vessel contains no irradiated fuel.

2.15 Plant Emergency Operating Procedures (EOPs) are designed to maintain or restore a set of critical safety functions that are prioritized for restoration efforts during accident conditions. By monitoring the critical safety functions status, the impact of multiple events can be inherently addressed.

2.16 The critical safety functions are monitored through the use of Critical Safety Function Status Trees (CSFSTs). When certain plant parameters exceed threshold values specified by the CSFST, the plant operator is directed to one or more functional restoration procedure in an attempt to restore those parameters to within acceptable limits. The following CSFSTs are utilized to be indicative of failures or potential failures of one or more fission product barriers:

2.16.1 Subcriticality - Orange or Red paths in this CSFST indicate losses of reactivity control which may pose a threat to fuel clad and RCS integrity.

2.16.2 Core Cooling - Orange OR Red paths in this CSFST indicate losses of core subcooling AND thus pose a direct threat to the integrity of the reactor fuel clad.

2.16.3 Heat Sink - The Red path of this CSFST is indicative of a loss of ability to remove decay heat from the core and thus poses a direct threat to fuel clad integrity.

2.16.4 Integrity - The Red path of this CSFST is indicative of a direct threat to RCS barrier integrity.

2.16.5 Containment - Red path of this CSFST is indicative to a loss of RCS barrier AND direct threat to the containment barrier integrity.

3.0 PRECAUTIONS AND LIMITATIONS NONE 4.0 EQUIPMENT AND MATERIALS NONE Page 4 of 24

Emergency Classification IP-1024 Rev. 11 5.0 INSTRUCTIONS 5.1 The Operator is alerted by initial event recognition or Control Room alarms.

5.2 The Operator shall notify the Shift Manager AND Watch Engineer.

5.3 The Operator may enter the Emergency Operating Procedures (EOPs) or Abnormal Operating Instructions (AOls) while the Watch Engineer monitors the Critical Safety Function Status Trees (CSFST), if appropriate.

5.4 The Shift Manager shall evaluate Attachment 2 to determine IF a GE, SAE, ALERT or NUE classification applies THEN determine the highest classification and declare it, if applicable.

5.5 The Shift Manager shall assume the role of Emergency Director and initiate County, State AND NRC notifications in accordance with Reference 6.2.

5.6 The Emergency Director (Shift Manager) continues to evaluate future events and potential challenges from information supported by the Operator and Watch Engineer.

As conditions warrant, the Emergency Director (Shift Manager) shall re-enter Section 5.4.

5.7 If necessary the Emergency Director (Shift Manager) shall upgrade the emergency classification.

5.8 If no classification applies, the Shift Manager evaluates whether Technical Specifications Limits on LCO reportable under Reference 6.1 applies and performs the applicable notification as per Reference 6.1.

6.0 REFERENCES

6.1 SAO-124, Oral Reporting of Non-Emergency Items and Items of Interest and Significant Occurrence Reporting 6.2 IP-1002, Emergency Notification and Communication 6.3 NUMARC/NESP-007, Revision 2, Methodology for Development of Emergency Action Levels 7.0 ATTACHMENTS 7.1 - Fission Product Barrier Loss & Potential Loss Indicators 7.2 - Emergency Action Levels 8.0 ADDENDUM None Page 5 of 24

IP-1024 Rev. 11 ATTACHMENT 1 Sheet 1 of 2 Fission Product Barrier Loss/Potential Loss Matrix (Those thresholds for which loss or potential loss is determined to be imminent, classify as though the threshold(s) has been exceeded)

Fuel Cladding RCS RED path in F-0.2, CORE COOLING Coolant activity >300 g.Ci/cc 1-131 equivalent

"* Core Exit Thermocouple Readings >1200°F

"* Containment radiation monitor R-25 or R-26 >17R/hr Emergency Director Judgment Loss RCS subcooling < SI initiation setpoint due to RCS leakage Unisolated faulted (outside VC) ruptured steam generator

>0.171iCi/cc on R-42 OR >66 iCi/cc on R-41 due to RCS leakage Emergency Director Judgment Page 6 of 24 Emergency Classification Potential Loss ORANGE path in F-0.2, CORE COOLING RED path in F-0.3, HEAT SINK Core Exit Thermocouple Readings >700'F RVLIS <-41% w/no RCPs running Emergency Director Judgment Loss Potential Loss RED path on F-0.4, INTEGRITY RED path on F-0.3, HEAT SINK Primary system leakage exceeding capacity (>75GPM) of single charging pump Emergency Director Judgment

Emergency Classification IP-1024 Rev. 11 ATTACHMENT 1 Sheet 2 of 2 Fission Product Barrier Loss/Potential Loss Matrix (Those thresholds for which loss or potential loss is determined to be imminent, classify as though the threshold(s) has been exceeded)

Containment Potential Loss RED path F-0.5, CONTAINMENT Either:

Core exit thermocouples >1200*F OR Core exit thermocouples >700'F with RVLIS < 41% w/no RCPs AND Restoration procedures not effective within 15 minutes Confirmed phase "B" isolation signal following confirmed LOCA with less than minimum containment cooling safeguards equipment operating Fan Cooler Units Oper.

Spray Pumps Req'd

<3 2

3 5

1 0

Containment Pressure 47 psig and increasing

->4%

hyrdogen concentration in containment Containment radiation monitor R-25/26 reading >68 R/hr Emergency Director Judgment Loss Rapid uncontrolled decrease in containment pressure following initial increase due to RCS failure Either:

Any Phase "A" or Phase "B" or containment ventilation isolation valve(s) not closed when required following confirmed LOCA OR Inability to isolate any primary system discharging outside containment AND Radiological release to the environment exists as a result Both doors open on a VC airlock for >4 hrs.

OR Inability to close containment pressure relief or purge valves which results in a radiological release pathway to the environment for >4 hrs.

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 Unisolable release of secondary side to atmosphere from the affected steam generator(s) with primary to secondary leakage >Technical Specification limit in any steam generator Loss of primary coolant inside containment with containment pressure or sump level response not consistent with LOCA conditions Emergency Director Judgment Page 7 of 24 IL--JL-

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 1.0 CSFST STATUS Category General Site Area Alert Unusual Event 1.1

[SG2]

[SS2,SS4]

[SA2]

Subcriticality 1.1.3 {1,2) 1.1.2 {1,21 1.1.1 {1,2}

RED path in F-0.1, Subcriticality RED path in F-0.1 Subcriticality Any Failure of an automatic AND AND trip signal to reduce power Actual or imminent entry into either:

Emergency boration is required range < 5%

RED Path in F-0.2, Core Cooling AND OR Manual trip is successful Red Path in F-O.3, Heat Sink 1.2

[fl,ri,cpl] [FC1,PC6,PC6]

[fpVfl,ri] [SS4,FC3,FC4]

Core Cooling 1.2.2 {1,2}

1.2.1 {1,2}

RED path in F-0.2,Core Cooling ORANGE or RED path in F-0.2, AND Core Cooling Functional restoration actions taken and procedures not effective within 15 minutes.

1.3

[fpl,rpl] [SS4,RCS1,FC1]

Heat Sink 1.3.1 {1,2}

RED path in F-0.3, HEAT SINK AND Heat sink is required 1.4

[rpl] [RCS1]

Integrity 1.4.1 {1,2}

RED Path on F-0.4, Integrity 1.5

[fl,rl,cpl] [PC1]

Containment 1.5.1 {1,2}

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

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 8 of 24

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels P.ATF:(';ORY 2 f REACTOR FUEL category General Site rea Alert Un usual Event

[fl.rpl/rl]

[f I] [FC2]

[SU4]

2.1

[FC2,RCS1,RCS2,RCS4]

2.1.2 (1,2) 2.1.1 (1,2,3,4,51 Coolant Activity 2.1.3 11,2)

Coolant Activity > 300 giCVcc 1-131 Coolant sample Coolant activity > 300 JLCi/cc 1-131 equivalent activity:

equivalent and any of the following:

> 60/(E bar) pCi/cc

RED path on F-0.4, Integrity

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

RCS subcooling < SI initiation setpoint due to RCS leakage

Rise in R-41 offscale or R-42

>0.17 gCi/cc due to RCS leakage 2.2

[fl,rl,cpl] [PC5]

[fl,rli] [FC5]

[rl] [RCS4]

Containment 2.2.3 {1,2) 2.2.2 {1,2) 2.2.1 {1,2)

Radiation Containment Radiation Containment Radiation monitor R-25 Rise in R-41 offscale or R-42 monitor R-25 or R-26 or R-26 > 17 R/HR

> 0.17pCi/cc due to RCS leakage

> 68 R/HR

[AA2]

[AU2]

2.3 2.3.2 (1,2,3,4,5) 2.3.1 (1,2,3,4,5)

Refueling Confirmed sustained alarm on ANY of Spent fuel pool Accidents or the following radiation monitors resulting (reactor cavity during Other Radiation from fuel damage caused by an refueling ) water level Monitors uncontrolled fuel handling process:

cannot be restored

"* R-2/R-7 Vapor Containment Area and maintained above Monitors Technical

"* R-5 Fuel Storage Building Area Specification Monitor minimum water level

"* R-25 or 26 Vapor Containment High Radiation Area Monitors

[AA2]

2.3.3 (1,2,3,4,5)

Report of visual observation of irradiated fuel uncovered

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 9 of 24

Emergency Classification I P-1 024 Rev. 11 - Emergency Action Levels CATEGORY 3.0 REACTOR COOLANT SYSTEM Category General Ste Area Alert.

Unuhsual Event

[fpl,rl][SS5, SS4,FC4]

[rpl] [RCS2]

[SU5]

3.1 3.1.3 11,2,3,4) 3.1.2 (1,2) 3.1.1 (1,2)

RCS Leakage RVLIS cannot be maintained Primary system leakage Unidentified or pressure

> 41% with no RCP's running exceeding capacity (> 75 boundary leakage OR gpm) of single charging

> 10 gpm With the reactor vessel head removed, pump OR it is reported that water level in the Identified leakage reactor vessel is dropping in an

> 25 gpm uncontrolled manner and core uncovery is likely 3.2

[rpl,cl] [PC4,RCS2]

[cl] [PC4]

3.2.2 {1,2) 3.2.1 (1,2) Unisolable Primary to Secondary Leakage Unisolable release of secondary side to release of secondary side atmosphere from the affected steam to atmosphere from the generator(s) with primary to secondary affected steam leakage exceeding capacity (> 75 gpm) generator(s) with primary of a single charging pump to secondary leakage >

[fl,cl] [PC4,FC2]

Technical Specification 3.2.3 {1,2) limit in any Steam Unisolable release of secondary side to Generator atmosphere from the affected steam generator(s) with primary to secondary leakage > Technical Specification limit in any steam generator AND Coolant activity> 300 gCi/cc of 1-131 equivalent 3.3

[rl] [RCS2]

RCS Subcooling 3.3.1 {1,2)

RCS subcooling <SI initiation setpoint due to RCS leakage

[11= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [51= Defuel Page 10 of 24

- Emergency Action Levels 4.1 Containment Integrity Status 4.1.4 {1,2}

Confirmed Phase "B" isolation signal following confirmed LOCA with less than minimum containment cooling safeguards equipment operating, Table 4.3 AND Any indicators of fuel clad loss, Table 4.1

[fpl/fl,rl,cl] [PC2,FC1,FC2,FC3,FC4,FC5]

4.1.5 {1,2)

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 indications of fuel clad damage, Table 4.2

[fpl/fl,rl,cl] [PC3,FC1,FC2,FC3,FC4,FC5]

4.1.6 {1,21 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 AND Radiological release to the environment exists as a result AND Any indicators of fuel clad damage, Table 4.2 4.1.1 {1,2}

Both doors open on a VC airlock for > 4 hrs.

OR Inability to close containment pressure relief or purge valves which results in a radiological release pathway to the environment for > 4 hrs.

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 j _____________________________

J ___________________

J __________________________

[1]= Power Operations [2]= Hot Shutdown [31= Cold Shutdown [4]= Refuel [5]= Defuel Page 11 of 24 Emergency Classification 4.1.2 11,2)

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

[rl,cl] [PC3]

4.1.3 {1,2)

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 AND Radiological release to the environment exists as a result I P-1 024 Rev. 11 1

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 12 of 24 Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Category General Site Area Alert Ujnusual Event

[fpVfl,rl,cl] [RCS3,FC1,FC2,FC3,FC4,FC5]

[rl,cl] [RCS3]

4.2 4.2.2 {1,2}

4.2.1 {1,2}

Unisolable faulted (outside VC) ruptured steam Unisolable faulted (outside VC)

SG Tube Rupture generator ruptured steam generator w/Secondary AND Release Any indicators of fuel clad damage, Table 4.2

[fl,rl,cpl] [PC2]

4.3 4.3.1 {1,2}

Cobu l G 4% Hydrogen concentration in containment Combustible Gas Concentrations

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Table 4.1 Fuel Clad Loss Indicators

1. Coolant activity > 300 gCVcc of 1-131 equivalent

2.

Containment radiation monitor R-25/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 g*Cl/cc of 1-131 equivalent

4. Containment radiation monitor R-25/R-26 reading > 17 R/hr Table 4.3 Minimum Containment Cooling Safeguards Equipment Fan Cooler Units Operating Spray Pumps Required

<3 2

3 1

5 0

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 13 of 24

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE category General Site.Area Alert Unusual.Event

[AG1]

[AS1]

[AA1]

[AU1]

5.1 Effluent Monitors 5.1.4 {1,2,3,4,5}

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

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

5.1.1{1,2,3,4,S)

A valid reading on any A valid reading on any A valid reading on any A valid reading on any monitors Table 5.1 column monitors Table 5.1 column monitors Table 5.1 monitors Table 5.1 column "GE" for > 15 minutes "SAE" for > 15 minutes column "Alert for "NUE" for unless dose assessment can unless dose assessment can

> 15 minutes unless

> 60 minutes unless confirm releases are below confirm releases are below dose assessment can sample analysis can Table 5.2 column "GE" within Table 5.2 column "SAE" within confirm releases are confirm release rates this time period, this time period, below Table 5.2 column

< 2 x technical "Alert" within this time specifications within this

period, time period.

[AG1]

[AS1]

[AA1]

[AU1]

5.2 Dose Projections/

5.2.5 {1,2,3,4,5}

5.2.4 {1,2,3,4,5}

5.2.2{1,2,3,4,5}

5.2.1{1,2,3,4,5)

Environmental Measurements/

Dose projections or field Dose projections or field Confirmed sample Confirmed sample analysis Release Rates surveys resulting from an surveys resulting from an analysis for gaseous or for gaseous or liquid actual imminent release actual imminent release which liquid release rates release rates which indicate doses/dose indicate doses/dose rates >

> 200 x technical

> 2 x technical rates > Table 5.2 column Table 5.2 column "SAE" at the specifications limits for specifications limits for "GE" at the site boundary or site boundary or beyond.

> 15 minutes

> 60 minutes.

beyond.

[AA1]

5.2.3{1,2,3,4,5}

Dose projections or field surveys resulting from an actual imminent which indicate doses/dose rates > Table 5.2 column "Alert" at the site boundary or beyond.

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 14 of 24

IP-1024 Rev. 11 Emergency Classification - Emergency Action Levels 0

f% nr t

fA*Alf%11-TlV D0=I IAQ 5.3 Area Radiation Levels

[AA3]

5.3.2{1,2,3,4,5)

Sustained area radiation levels > 15 mRem/hr in EITHER:

Control Room OR Central Alarm Station and Secondary Alarm Station

[AA3]

5.3.3{1,2,3,4,5}

Sustained abnormal area radiation levels > 8 R/hr within any areas, Table 5.3 AND Access is required for safe operation or shutdown I ___________________

j ____________________

-) _________________

[AU2]

5.3.1{1,2,3,4,5}

Any sustained direct ARM readings > 100 x alarm or offscale high resulting from an uncontrolled process

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [51= Defuel Page 15 of 24 I

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Monitor GE SAE Alert UE R-27 53 ptCi/cc 5.3 laCi/cc 5.3 E-1 plCi/cc 2.3 E-3 pCi/cc R-44 53 giCi/cc 5.3 pCi/cc 5.3 E-1 pCi/cc 2.3 E-3 gCi/cc R-54 N/A N/A 2.5 E-1 giCi/cc 2.5 E-3 pCi/cc R-49 N/A N/A 2.7 E-2 IgCi/cc 2.7 E-4 lgCi/cc Table 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 5000 mRem/hr 500 mRem/hr N/A (for 1 hr. of inhalation)

[1]= Power Operations [21= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 16 of 24 Table 5.1 Effluent Monitor Classification Thresholds

Emergency Classification IP-1 024 Rev. 11 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [51= Defuel Page 17 of 24 Table 5.3 Plant Areas Condensate Storage Tank RWST Service Water Pump Structure Service Water Valve Pit East Fuel Storage Building Primary Auxiliary Building/Fan House 480 Volt Switchgear Room (Control Building)

Cable Spreading Room/Electrical Tunnel Diesel Generator Building/Fuel Tank Area Auxiliary Feedwater Pump Building Battery Room (Control Building 33'0" ele.)

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels

(.ATFC.ORY RflI ELECTRICAL FAILURES Category General Site Area Alert U~nusual Event

[SG1]

[SS1]

[SA1]

[SU1]

6.1 6.1.5 {1,2}

6.1.4 {1,2}

6.1.2 {3,4,5}

6.1.111,2,3,4,5}

Loss of AC Power Loss of all emergency AC Loss of AC power to all 480 volt Loss of AC power to all 480 volt busses (5A, Unplanned loss of offsite Sources power busses (5A,2A/3A,6A) for 2A/3A, 6A) for > 15 minutes.

power to all 480V AND EITHER:

> 15 minutes.

AND busses(5A,2A/3A,6A) for >

Power restoration to AND Inability to power required core cooling/

15 minutes.

required core cooling Inability to power required core spent fuel cooling systems with alternate systems is not likely in cooling systems with alternate power sources for > 15 minutes.

< 1 hr.

power sources for > 15 minutes.

[SA5]

OR 6.1.3 {1,2}

Actual or imminent entry AC power capability to 480 volt busses into ORANGE or RED (5A,2A/3A,6A) reduced to only one of the path on F-0.2, "Core following sources for > 15 minutes.:

Cooling" 480V EDG 21 0

480V EDG 22 480V EDG 23 Unit Auxiliary Transformer*

Station Auxiliary Transformer*

13.8 KV gas turbine auto transformer*

with 86P or 86BU tripped, all offsite power supplies must be considered as one power supply

[SS3]

[SU7]

6.2 6.2.2 {1,2}

6.2.1 {3,4}

Loss of DC Power Loss of bus voltage (< 105 vdc) for Unplanned loss of bus Sources

> 15 minutes on all of the DC voltage (< 105 vdc) for Busses.

> 15 minutes on any DC bus resulting in the loss of decay heat removal capability.

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 18 of 24

[11= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 19 of 24 Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 7.0 EQUIPMENT FAILURES Category General Shte Area i

Alert

~Unsa Event

[SU2]

7.1 7.1.1 {1,2}

Technical Specifications/

Plant is not brought to required Requirements operating mode within Technical Specifications LCO Action Statement Time.

[HS2]

[HA1]

[HU1]

7.2 7.2.5 {1,2,3,4,5}

7.2.2 {1,2}

7.2.1 {1,2}

System Failures or Control Control Room Evacuation Turbine failure generated missiles Report of main turbine failure requiring Room Evacuation AND which causes or potentially causes turbine trip resulting in:

Plant control cannot be any required safety related system or Damage to turbine generator seals established per A0127.1.9, structure to become inoperable, causing release of lubricating oil or "Control Room hydrogen Inaccessibility/ Safe

[HA5]

OR Shutdown" in < 15 minutes 7.2.3 {1,2,3,4,5}

Casing penetration Entry into AOI-27.1.9, "Control Room Inaccessibility/ Safe Shutdown Control"

[SA3]

7.2.4 {3,4}

Reactor coolant temperature cannot be maintained < 200OF

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 20 of 24 Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 7.0 EQUIPMENT FAILURES Category General Site Area Alert Unusual Event

[SS61

[SA4]

[SU3]

7.3 Loss of Indications/

7.3.4 {1,2}

7.3.3 {1,2) 7.3.1 {1,21 Alarms/Communication Loss of most (approx. 75%)

Unplanned loss of most (approx.

Unplanned loss of most (approx. 75%)

Capability safety system annunciators 75%) safety system annunciators or safety system annunciators or or indications on Control indications on Control Room Panels indications on Control Room Panels Room Panels for > 15 minutes for > 15 minutes AND AND AND Loss of ability to monitor Increased surveillance is required for Increased surveillance is required for critical safety function status safe plant operation safe plant operation AND EITHER:

[SU6]

AND A significant plant transient in 7.3.2 {1,2,3,4,5}

A significant plant transient in progress Loss of all communications capability progress OR affecting the ability to EITHER:

Proteus and SAS are unavailable Perform routine operations OR Notify offsite agencies or personnel

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 8.0 HAZARDS Category General Site Area Alert A

UnussaI~vent

[HG1]

[HS1]

[HA4]

[HU4]

8.1 8.1.4 (1,2,3,4,5) 8.1.3 (1,2,3,4,5) 8.1.2 (1,2,3,4,5) 8.1.1 {1,2,3,4,5}

Security Security Event which Intrusion into a plant Intrusion into plant Protected Area by Bomb device or other indication of attempted Threats results in:

security vital area an adversary sabotage discovered within plant Protected Area Loss of plant control by an adversary OR OR from the Control OR Any security event which represents Notification of any credible site specific security Room Any security event an actual substantial degradation of threat by the Security Shift Supervisor or outside AND which represents the level of safety of the plant.

agency (NRC, military or law enforcement)

Loss of remote actual or likely shutdown capability failures of plant systems needed to protect the public.

[HA2]

[HU2]

8.2 8.2.3 (1,2,3,4,5) 8.2.1 (1,2,3,4,5) Confirmed fire in or contiguous to Fire or Fire or explosion in any plant area, any plant area, Table 8.2 not extinguished in Explosion Table 8.2, which causes or potentially 15 minutes of Control Room notification.

causes any required safety related

[HUl]

system or structure to become 8.2.2 (1,2,3,4,5) Report by plant personnel of an inoperable explosion within Protected Area boundary which impacts plant safety related systems or structures.

[HA1]

[HUl]

8.3 8.3.3 (1,2,3,4,51 8.3.1 (1,2,3,4,5)

Man-Made Vehicle crash or projectile impact Vehicle crash into or projectile which impacts plant Events which causes or potentially causes safety related structures or systems within any required safety related system or Protected Area boundary structure to become inoperable,

[HU3]

Table 8.2 8.3.2 (1,2,3,4,5)

[HA3]

Report or detection of toxic or flammable gases 8.3.4 {1,2,3,4,5) that could enter or have entered within the Report or detection of toxic or Protected Area boundary in amounts that could flammable gases within a plant area, affect the health of plant personnel or safe plant Table 8.2, in concentrations that will operation be life threatening to plant personnel OR or preclude access to equipment Report by local, county or state officials, or Unit 3, (even when using personal protective for potential evacuation of site personnel based on equipment) needed for safe plant offsite event operation

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 21 of 24

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 8.0 HAZARDS Category General Site Area Alert Unusual Event

[HAI]

[HU1]

8.4 8.4.4 {1,2,3,4,5}

8.4.1 {1,2,3,4,5} Earthquake felt in plant based Natural Events Earthquake felt in-plant based upon upon a consensus of Control Room Operators on consensus of Control Room duty Operators on duty AND AND Notification received from Unit 3 that an Notification from Unit 3 that an earthquake has been detected on their earthquake of a magnitude > 0.15g instrumentation.

horizontal or > 0.1 Og vertical has

[HU1]

occurred.

8.4.2 {1,2,3,4,5}

[HAl]

Report by plant personnel of tornado within plant 8.4.5 {1.2.3.4.5) Sustained winds Protected Area boundary

> 100 mph

[HU1]

OR 8.4.3 {1,2,3,4,5}

Tornado strikes a plant vital area, River level 2 14.5' (OMSL)

Table 8.2 OR

[HAl]

Service water bay level < -4.5' (OMSL) 8.4.6 {1,2,3,4,5} Assessment by the Control Room personnel that a natural event has occurred which causes or potentially causes any required safety system or structure to become inoperable, Table 8.2

[HAl]

8.4.7 {1,2,3,4,5}

River level Ž15' (OSML)

OR Low service water bay level resulting in a loss of service water flow

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 22 of 24

Emergency Classification IP-1024 Rev. 11 - Emergency Action Levels CATEGORY 8.0 HAZARDS

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [41= Refuel [5]= Defuel Page 23 of 24 Table 8.2 Plant Vital Areas

"* Condensate Storage Tank

"* RWST

"* Service Water Pump Structure

"* Service Water Valve Pit East

"* Fuel Storage Building

"* Primary Auxiliary Building/Fan House

"* Vapor containment Building

"* 480 Volt Switchgear Room (Control Building)

"* Cable Spreading Room/Electrical Tunnel

"* Central Control Room

"* Diesel Generator Building/Fuel Tank Area

"* Auxiliary Feedwater Pump Building

"* Battery Room (Control Building 33'0" ele)

"* Central Alarm Station

Emergency Classification IP-1 024 Rev. 11 - Emergency Action Levels CATEGORY 9.0 Category General Sit$ Area Aler Unusual Event 9.1

[HG2]

[HS3]

[HA6]

[HU5]

Other 9.1.7 {1,2,3,4,5}

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

9.1.3 {1,2,3,4,5}

9.1.1 {1,2,3,4,5}

As determined by the Shift As determined by the Shift Manager or Any event, as determined by Any event, as determined by Manager or Emergency Director, Emergency Director, events are in progress the Shift Manager or the Shift Manager or events are in progress which which indicate actual or likely failures of Emergency Director, that Emergency Director, that indicate actual, or imminent core plant systems needed to protect the public, could cause or has caused could lead to or has led to a damage and the potential for a Any releases are not expected to result in actual substantial potential degradation of the large release of radioactive exposures which exceed EPA PAGs.

degradation of the level of level of safety of the plant.

material in excess of EPA PAGs safety of the plant.

outside the site boundary.

[FC7,RCS6,PC8]

9.1.6 {1,2}

[FC7,RCS6]

[PC8]

9.1.8 {1,2}

Any event, as determined by the Shift 9.1.4 {1,2}

9.1.2 {1,2}

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

the Shift Manager or the Shift Manager or Director, that could lead or has led Loss or potential loss of both fuel clad Emergency Director, that Emergency Director, that to a loss of any two fission product and RCS barrier, Attachment A.

could lead or has led to a could lead to or has led to a barriers and loss or potential loss OR loss or potential loss of either loss or potential loss of of the third, Attachment 1.

Loss or potential loss of either fuel clad fuel clad or RCS barrier, containment, Attachment 1.

or RCS barrier in conjunction with a loss.

of containment, Attachment 1.

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 24 of 24

ENTERGY INDIAN POINT STATION EMERGENCY PLANNING Emergency Operations Facility Prepared by:

Approval:

Al Lee Print Name Frank Inzirillo Print Name Signature n4ature Date 7/Dat Date Effective Date:

J// /0 2-IP-1030 (EOF) R6. doc 20027021200 Page 1 of 50 IP-1030 Rev 6

Emergency Operations Facility IP-1030 Rev. 6 Table of Contents Section 1.0 P U R P O S E...................................................................................................................................................

4 2.0 DISCUSSION..............................................................................................................................................

4 3.0 PRECAUTIONS AND LIM ITATIONS.....................................................................................................

4 4.0 EQUIPM ENT AND M ATIREALS...................................................................................................

4

.5.0 INSTRUCTIONS........................................................................................................................................

5 5.1 Offsite Radiological Assessment Director..............................................................................

5 5.2 Dose Assessment Health Phycisist..........................................................................................

5 5.3 M id as O perato r............................................................................................................................

5 5.4 Survey Team Health Phycisist................................................................................................

5 5.5 Technical Advisor to Emergency Director...............................................................................

5 5.6 EOF Communicator #1........................................................................................................

5 5.7 EOF Communicator #2.......................................................................................................

5 5.8 EOF Clerical Staff........................................................................................................................

5 5.9 EOF SAS / Proteus Operator...................................................................................................

5

6.0 REFERENCES

6 7.0 ATTACHMENTS :Offsite Radiological Assessment Director Checklist...................................................

25 : Dose Assessment Health Phycisist Checklist...............................................................

33 : M IDAS Operator Checklist........................................................................................

37 : Survey Team Health Phycisist Checklist.....................................................................

41 : Technical Advisor to Emergency Director Checklist..................................................

45 : EOF Communicator #1 Checklist.................................................................................

48 : EOF Communicator #2 Checklist................................................................................

52 : EOF Clerical Staff Checklist........................................................................................

55 : EOF SAS / Proteus Operator.......................................................................................

59 Page 2 of 50

Emergency Operations Facility IP-1030 Rev. 6 8.0 ADDENDUM A ddend um 1 :E O F L ayout.........................................................................................................................

67 Addendum 2:NYS Radiological Data Form (Part I & II) (Form IP-1030-1).......................................

69 Addendum 3:EOF Radiological Survey Map (Form IP-1030-3)........................................................

72 A ddendum 4:D irections to N Y S EO C.................................................................................................

73 Addendum 5:EPA 302.4 Nuclide Table (Form IP-1030-4).................................................................

74 Addendum 6:Offsite Survey Team Data Sheet (Form IP-1030-5).....................................................

75 Page 3 of 50

Emergency Operations Facility IP-1030 Rev. 6 1.0 PURPOSE Along with procedure IP-EP-255, Emergency Operations Facility Management and Liaisons, to describe the activation and operation of the Emergency Operations Facility (EOF) 2.0 DISCUSSION None 3.0 PRECAUTIONS AND LIMITATIONS EOF habitability checks are necessary to ensure long-term manning of the EOF.

Should conditions exist which may result in a loss of long-term habitability of the EOF, evaluate the need for relocation of emergency response functions to the Alternate EOF in accordance with IP-1045 "Activation of Alternate Emergency Operations Facility."

4.0 EQUIPMENT AND MATERIALS 4.1 The following types of equipment and materials are available for use in the EOF 4.1.1 Plant information systems:

"* EDDS

"* SAS

"* Proteus

"* Meteorological Displays 4.1.2 Radiological equipment needed to perform offsite monitoring:

"* Field Monitoring kits

"* Survey equipment for performance of facility habitability checks 4.1.3 Dose Assessment and plume tracking equipment:

"* Plant Integration Computer System (PICS)

"* MEANS

"* Map table 4.1.4 Communication systems needed to transfer important data to offsite authorities:

"* V-Band communications consoles

"* Telephones

"* Fax Machines Page 4 of 50

Emergency Operations Facility IP-1 030 Rev. 6 4.1.5 Procedures and forms:

IP2 Emergency Plan

"* IP2 Emergency Plan Implementing Procedures

"* Position Binders

"* Forms 4.1.6 Office Supplies 4.2 The key to the EOF is located in a break glass container in the EOF entry way.

5.0 INSTRUCTIONS 5.1 The Offsite Radiological Assessment Director (ORAD) shall follow the instructions outlined Attachment 1, Offsite Radiological Assessment Director (ORAD) Checklist 5.2 The Dose Assessment Health Physicist (DAHP) shall follow the instructions outlined in Attachment 2, Dose Assessment Health Physicist Checklist.

5.3 The Midas Operator shall follow the instructions outlined Attachment 3, MIDAS Operator Checklist.

5.4 The Survey Team Health Physicist (STHP) shall follow the instructions outlined in, Survey Team Health Physicist Checklist.

5.5 The Technical Advisor to Emergency Director shall follow the instructions outlined in, Technical Advisor (TA) Checklist 5.6 The EOF Communicator #1 shall follow the instructions outlined in Attachment 6, EOF Communicator #1. Checklist 5.7 The EOF Communicator #2 shall follow the instructions outlined in Attachment 7, EOF Communicator #2. Checklist 5.8 The EOF Clerical Staff shall follow the instructions outlined in Attachment 8, EOF Clerks. Checklist 5.9 The EOF SAS Proteus Operator shall follow the instructions outlined in Attachment 9, EOF SAS Proteus Operator Checklist Page 5 of 50

Emergency Operations Facility IP-1030 Rev. 6

6.0 REFERENCES

6.1 IP-1021, "Manual Update and Readout of Proteus Plant Parameter Data" 6.2 IP-1024, "Emergency Classification" 6.3 IP-1027, "Site Personnel Accountability and Evacuation" 6.4 IP-1048,

'Termination & Recovery" 6.5 IP-EP-255, "Emergency Operations Facility Management and Liaisons" 7.0 ATTACHMENTS 7.1, Offsite Radiological Assessment Director (ORAD) Checklist 7.2, Dose Assessment Health Physicist (DAHP) Checklist 7.3, MIDAS Operator Checklist 7.4, Survey Team Health Physicist (STHP)Checklist 7.5, EOF Technical Advisor Checklist 7.6, EOF Communicator #1 Checklist 7.7, EOF Communicator #2 Checklist 7.8, EOF Clerical Staff Checklist 7.9, EOF SAS / Proteus Operator 8.0 ADDENDUM 8.1 Addendum 1, EOF Layout 8.2 Addendum 2, NYS Radiological Data Form (Part I & II) (Form IP-1030-1) 8.3 Addendum 3, Sample Form - EOF Radiological Survey Map (Form IP-1030-3) 8.4 Addendum 4, Directions to NYS EOC 8.5 Addendum 5., EPA 302.4 Nuclide Table (Form IP-1030-4) 8.6 Addendum 6, Sample Form - Offsite Survey Team Data Sheet (Form IP-1030-5)

Page 6 of 50

Emergency Operations Facility IP-1 030 Rev. 6 Offsite Radiological Assessment Director (ORAD)

Sheet 1 of 8 Initial Responsibility/Activity Notes 1.0 Assume the position of ORAD.

1.1 Review facility status boards, EDDS information and any other available sources to become familiar with current plant status.

1.2 Obtain briefing from the EOF Manager or Emergency Director A. Use an Essential Information Checklist (Form IP-1035-2) to document briefing items.

B. Request any additional information on current status of emergency response.

1.3 IF the EOF has NOT been activated THEN:

NOTE:

Offsite Dose Assessment and Radiological Monitoring responsibilities may be transferred to the ORAD before the EOF is fully activated.

A. WHEN the following minimum staff is available THEN inform the EOF Manager or the ED that you are ready to conduct offsite monitoring activity.

1. Field Monitoring Team Members (2)

2. EOF Communicator #1 B. WHEN ready to assume offsite (outside Protected Area) monitoring responsibilities from the CCR THEN contact the CCR and formally assume these responsibilities.

C. Review Normal EOF Staffing (Form IP-1030-2) to verify full EOF Staffing for offsite radiological tracking.

D. IF additional personnel are required THEN inform the EOF Manager to direct callout of needed personnel.

E. Notify the EOF staff that you have assumed these responsibilities.

Page 7 of 50

Emergency Operations Facility IP-1030 Rev. 6 Offsite Radiological Assessment Director (ORAD)

Sheet 2 of 8 Initial Responsibility/Activity (con't)

Notes F Direct the MIDAS Operator to disarm (or disarm lAW steps in MIDAS Operator's Checklist) the Halon Fire Protection System (Real emergencies only)

G IF there has been a release of radioactive to the environment THEN:

1. Direct the MIDAS Operator to place (or place lAW steps in MIDAS Operator's Checklist) the EOF ventilation in the internal recirculation mode.

2. Contact the Unit #3 Control Room and request that a Field Monitoring Team report to EOF H IF the CCR performed off site dose assessments and made a Protective Action Recommendation THEN:

1. Obtain and review NYS Radiological Emergency Data Form

- Part I and Part II

2. Verify or have the Dose Assessment HP verify dose assessment calculations.

3. Evaluate Protective Action Recommendations.

4. Notify the ED or CCR if there are any discrepancies.

1.4 IF relieving another ORAD THEN perform a formal turnover with the current ORAD:

A Review the current ORAD's activity log B Obtain briefing form current ORAD on the emergency and any actions the have been competed or are in progress.

C Make an announcement to the EOF Staff that you are now the ORAD.

Page 8 of 50

Emergency Operations Facility IP-1030 Rev. 6 Offsite Radiological Assessment Director (ORAD)

Sheet 3 of 8 Continuous Responsibility/Activity Notes 2.0 Ensure habitability surveys are performed in the EOF 2.1 Assign an HP Technician to the position of Survey Team Health Physicist (STHP) providing them the following instructions:

A Perform steps in Attachment 6, Survey Team Health Physicist (STHP) Checklist 2.2 IF there is a potential for surface or airborne contamination with in the EOF THEN A Suspend eating and drinking until you ensure EOF food and drinking water supplies are consumable.

B Determine the survey and radiological controls needed for the EOF based on plant conditions and whether there has been a release or not.

C Provide further guidance to STHP on frequency of surveys and on the level of contamination controls required.

2.3 IF the following conditions are present THEN inform the EOF Manager and/or the ED that an organized evacuation of the EOF to the AEOF should be considered.

"* Exposure rates > 80 mRem/Hr TEDE OR 500mRem/Hr TODE

"* Projected Whole Body Dose for a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period is > 1 Rem TEDE OR Thyroid Dose >5 Rem TODE Airborne concentrations which may result in exceeding occupational limits for inhalation specified in 10CFR20, Appendix B, Table 1.

2.4 Evacuation may be performed at rates below those listed based on plant conditions and response needs.

Page 9 of 50

Emergency Operations Facility IP-1030 Rev. 6 Offsite Radiological Assessment Director (ORAD)

Sheet 4 of 8 3.0 Maintain personnel accountability in the EOF 3.1 Keep apprised of the whereabouts of Field Monitoring Teams and other personnel assigned to you at all times.

3.2 IF you are temporarily leaving the work area THEN A Inform the EOF Manager if you are leaving the work area.

B Upon return, obtain a briefing from the EOF Manager on any events which have occurred while you were away.

4.0 Maintain a Log 4.1 Use Form IP-1023-4, ERO Log Sheet to log information.

4.2 Log when you assumed the duties of ORAD.

4.3 Log significant decisions and important details used to make decisions.

5.0 Develop and provide recommendations for EAL and classification level changes based on radiological considerations to the ED.

5.1 Compare dose projection and field survey results with EAL criteria to determine the impact on the existing classification level.

5.2 Notify the ED of any EALs affected by changes in radiological conditions.

6.0 Develop and provide recommendations for offsite PARs based on radiological considerations to the ERM.

6.1 Notify the ED of any changes in radiological conditions which may effect the PAR 6.2 Use procedure IP-EP-410, Protective Action Recommendations to determine proper PAR.

6.3 Document Entergy PARs whenever a General Emergency is declared.

6.4 Review PARs whenever radiological conditions change significantly.

Page 10 of 50

Emergency Operations Facility IP-1 030 Rev. 6 Offsite Radiological Assessment Director (ORAD)

Sheet 5 of 8 Continuous Responsibility/Activity (con't)

Notes 7.0 Maintain communications with the TSC Radiological Advisor to discuss radiological conditions and on and off site response actions.

7.1 Contact the TSC Radiological Advisor for information on releases or potential releases and plant conditions which may lead to offsite radiological effects.

7.2 Periodically contact the TSC Radiological Advisor to provide updates on new dose projections, results of environmental monitoring and to provide technical assistance as needed.

8.0 Coordinate and direct the dose assessment and environmental monitoring efforts.

8.1 Supervise the activities of the Dose Assessment HP, MIDAS Operator, EOF Communicator #1 and the Field Monitoring Teams 8.2 Ensure the Health Physics Network (HPN) is manned when requested by the NRC 8.3 Determine the periodicity of dose projection calculations.

A Direct the Dose Assessment HP to perform offsite dose projections using IP-EP-310, Dose Assessment.

B Direct MIDAS Operator to obtain meteorological data, plume plot and Reuter-Stokes Sentri System readings, using EP-IP 510, Meteorological, Radiological & Plant Data Acquisition System.

8.4 Analyze dose assessment and environmental information to determine any actual or potential offsite consequences of the event.

8.5 Determine anticipated plume based on meteorological data.

8.6 Mark plume front and times on map table map.

8.7 Based on projected plume travel path select offsite sample points and indicate them on Form IP-1030-5.

Page 11 of 50

Emergency Operations Facility IP-1030 Rev. 6 Offsite Radiological Assessment Director (ORAD)

Sheet 6 of 8 Continuous Responsibility/Activity (con't)

Notes 8.8 Determine special instructions to be provided to monitoring teams:

A IF the expected thyroid dose is greater than 25 Rem THEN consider issuing KI B Team tracking efforts should be directed to limit their exposure to less than 5 Rem for the entire emergency.

8.9 IF site perimeter surveys are needed for sectors 1,14, 15 or 16 THEN contact the OSC to have in-plant HP technicians perform survey.

8.10 Teams should not go into radiation fields greater than 1 Rem/hr without specific directions from you. Direct EOF Communicator #1 to have Field Monitoring Teams survey anticipated plume path:

A Brief teams on expected doses, plume path and any special instructions or safety precautions (such as use of KI, respirators, or protective clothing).

B Have teams pick up samples from designated sample points.

C Direct environmental monitoring be performed to confirm dose projections and track any offsite radioactive plume.

8.11 Compare projected doses with actual readings taken by field monitoring teams.

8.12 Determine which ERPAs are affected by any release and verify proper PARs have been issued.

8.13 Conduct periodic briefings with the ED and the EOF Manager to discuss the status of offsite radiological information and assessments.

8.14 Compare dose assessment and environmental monitoring efforts with state and county personnel located in the EOF or in the EOCs if county and state personnel are not located in the EOF.

8.15 Compare dose assessment and environmental monitoring efforts with the NRC Environmental Dose Assessment Coordinator once the NRC Site Team is in the EOF.

Page 12 of 50

Emergency Operations Facility Offsite Radiological Assessment Director (ORAD)

Sheet 7 of 8 9.0 Evaluate and direct the requirements for offsite emergency exposure.

9.1 Track EOF Staff emergency exposures.

A Monitor EOF personnel exposures or potential exposures and request ED to Authorize Emergency Exposures and the issuance of KI to Entergy emergency workers outside the Protected Area. (ED authorization of exposures is non delegable)

B IF EOF staff must receive exposure THEN request the ED authorize emergency exposures up to 1 Rem TEDE for all monitoring team personnel dispatched from the EOF and remainder of staff as required. This authorization shall be documented in the ED's ERO Log Sheet.

C IF emergency measures require additional exposure THEN request the ED to the raise the emergency exposure limit 1 Rem at a time up to 5 Rem.

D Emergency exposures beyond 5 Rem shall be authorized on an individual basis. Request the ED authorize these exposures using Form IP-1023-6, Emergency Exposure Authorization.

General guidelines (more details are listed on authorization form)

1. ERO members may receive up to 5 Rem TEDE (per event) for any required emergency activities.

2. ERO members may be authorized emergency exposures up to 10 Rem TEDE to protect vital equipment.

3. ERO members may be authorized emergency exposures up to 25 Rem TEDE to save a life.

4. Individuals may volunteer to receive greater than 25 Rem TEDE to save a life.

9.2 Request authorization for the issuance of KI for any large exposures or expected large exposures to the thyroid.

9.3 Direct the use of protective clothing and respirators as necessary for Entergy workers outside the Protected Area.

9.4 IF emergency workers are exposed to contamination or airborne activities THEN direct radiological evaluations and monitoring as needed. IP-1008, Personnel Radiological Check and Decontamination should be used for these checks.

Page 13 of 50 IP-1030 Rev. 6

Emergency Operations Facility IP-1030 Rev. 6 Offsite Radiological Assessment Director (ORAD)

Sheet 8 of 8 Continuous Responsibility/Activity (con't)

Notes 10.0 Report releases to the Environmental Protection Agency (EPA) 10.1 IF any radionuclide release exceeds the value listed in Appendix B to § 302.4, (Form IP-1030-4) Title 40CFR302 THEN A Notify the EPA National Response Center (phone number in Emergency Telephone Directory).

B Direct Communicator to identify report is pursuant to 40CFR302.

10.2 Document details of any communications with EPA.

11.0 Initial Post Accident Environmental Sampling NOTE:

After a radiological release preliminary sampling may be performed to aid in development of more extensive plan for environmental sampling.

11.1 Confer with Emergency Director and offsite radiological officials on need for sampling.

11.2 Refer to IP-1 004, Post Accident Offsite Environmental Surveys, Sampling and Counting for sampling guidelines Closeout Responsibility/Activitv 12.0 Direct Staff to return all equipment to proper storage locations.

13.0 Review all documentation the EOF Radiological Staff maintained during the emergency:

13.1 Ensure logs, forms and other documentation are complete 13.2 Ensure all temporary procedures used and/or developed are properly documented for use by Recovery Organization so that necessary actions can be taken for plant operations 14.0 Provide all logs and records to the Recovery Manager upon termination of the emergency and entry into the Recovery Phase.

Page 14 of 50

Emergency Operations Facility IP-1 030 Rev. 6 Dose Assessment Health Physicist (DAHP)

Sheet 1 of 4 Initial Responsibility/Activity Notes 1.0 Assume the position of DAHP.

1.1 Review facility status boards, EDDS information and any other available sources to become familiar with current plant status.

1.2 Obtain briefing from the ORAD or EOF Manager A. Use an Essential Information Checklist (Form IP-1035-2) to document briefing items.

B. Review NYS Radiological Emergency Data Form, Part II if copy is available.

C. Request any additional information on current status of emergency response.

1.5 IF relieving another DAHP THEN perform a formal turnover with the current DAHP:

D Review the current DAHP activity log E Obtain briefing form current DAHP on the emergency and any actions the have been competed or are in progress.

1.3 Inform the ORAD that you are now the DAHP.

Continuous Responsibility/Activity Notes 2.0 IF you are temporarily leaving the work area THEN 2.1 Inform the ORAD you are leaving the work area.

2.2 Upon return, obtain a briefing from the ORAD on any events which have occurred while you were away.

3.0 Maintain a Log 3.1 Use Form IP-1023-4, ERO Log Sheet to log information.

3.2 Log when you assumed the duties of DAHP.

3.3 Log significant decisions and important details used to make decisions.

Page 15 of 50

Emergency Operations Facility IP-1030 Rev. 6 Dose Assessment Health Physicist (DAHP)

Sheet 2 of 4 Continuous ResDonsibility/Activity (cont.)

Notes 4.0 Evaluate Plant Radiological Data 4.1 Obtain Form 42c data from EDDS display, SAS printouts or fax copies received from the TSC.

4.2 Review radiation monitor readings and evaluate for actual or potential radiological releases.

4.3 Contact the TSC Radiological Advisor for additional information on plant radiological conditions and assistance in interpreting data.

4.4 IF there are any indications of a radiological release THEN perform step 5.0 of this checklist.

5.0 IF there has been a release or potential release of radioactive materials from the plant THEN:

5.1 Perform dose projections utilizing procedure IP-EP-310, Dose Assessment, MEANS Program and procedure IP-520, Modular Emergency Assessment and Notification System (MEANS).

6.0 Assist the ORAD in directing Field Monitoring Teams to survey locations.

6.1 Use overlays to obtain an approximation of the plume location 6.2 Determine which emergency sampling sites would be appropriate to send the Field Monitoring Teams to.

6.3 Use Xu/Q values to approximate relative values between locations.

Page 16 of 50

Emergency Operations Facility IP-1030 Rev. 6 Dose Assessment Health Physicist (DAHP)

Sheet 3 of 4 Continuous Responsibility/Activity (con't)

Notes 7.0 Evaluate the offsite survey data.

7.1 Calculate the charcoal / silver zeolite iodine and particulate activities using procedure IP-1020, Airborne Radioiodine Determination.

7.2 Determine the equivalent thyroid and whole body exposure rates utilizing Procedure IP-EP-310, "Dose Assessment" 7.3 Complete Form IP-1030-5, Offsite Survey Data and review data with the ORAD 8.0 Establish communications with the NRC via the HPN phone line.

8.1 Dial the number listed on the V-Band console or listed in the Emergency Telephone Directory.

8.2 Inform the NRC that the EOF is activated and performing offsite dose assessment activities. Brief them on any potential releases and answer any questions.

8.3 IF requested by the NRC to stay on THEN stay on the line and request the ORAD to locate another individual to assist in HPN line communications.

8.4 IF continuous communications are not requested THEN receive calls from the NRC on the HPN when phone rings.

Page 17 of 50 Dose Assessment Health Physicist (DAHP)

Sheet 4 of 4 Page 18 of 50 Emergency Operations Facility IP-1030 Rev. 6 Continuous Responsibility/Activity (con't)

Notes 9.0 Review Reuter-Stokes Sentri readings.

9.1 Obtain the readings from the MIDAS Operator 9.2 Compare the projected values and the measured offstie exposure rates with the Reuter-Stokes readings 9.3 IF there are large discrepancies THEN Inform the ORAD and continue to gather and analyze data to resolve values.

9.4 Present Reuter-Stokes data to ORAD for review Closeout Responsibility/Activity 10.0 Return all equipment to proper storage locations.

11.0 Review all documentation the DAHPs maintained during the emergency:

A. Ensure logs, forms and other documentation are complete B. Ensure any items which need follow up investigations are identified to be completed during the Recovery Phase 12.0 Provide all logs and records to the ORAD upon termination of the emergency and entry into the Recovery Phase.

Emergency Operations Facility IP-1030 Rev. 6 MIDAS Operator Sheet 1 of 4 Initial Responsibility/Activity Notes 1.0 Assume the position of MIDAS Operator.

1.1 Sign in on the Facility Sign-in Board 1.2 Review facility status boards, EDDS information and any other available sources to become familiar with current plant status.

1.3 Obtain briefing from the DAHP or the ORAD A. Review NYS Radiological Emergency Data Form, Part II if copy is available.

B. Request any additional information on current status of emergency response.

1.4 IF relieving another MIDAS Operator THEN perform a formal turnover with the current MIDAS Operator:

A. Review the current MIDAS Operator activity log B. Obtain briefing form current MIDAS Operator on the emergency and any actions the have been competed or are in progress.

1.5 Inform the DAHP that you are now the MIDAS Operator.

1.6 IF the facility has NOT been activated THEN A. Check operability and availability of MIDAS equipment, Reuter Stokes Systems and Meteorological data.

B. Report any equipment problems to the DAHP or ORAD.

Continuous Responsibility/Activity Notes 2.0 IF you are temporarily leaving the work area THEN 2.1 Inform the DAHP or ORAD you are leaving the work area.

2.2 Upon return, obtain a briefing from the DAHP or ORAD on any events which have occurred while you were away.

Page 19 of 50

Emergency Operations Facility IP-1030 Rev. 6 MIDAS Operator Sheet 2 of 4 Continuous Responsibility/Activity (cont.)

Notes 3.0 Maintain a Log 3.1 Use Form IP-1023-4, ERO Log Sheet to log information.

3.2 Log when you assumed the duties of MIDAS Operator.

3.3 Log significant decisions, important details used to make decisions and any equipment operability issues.

4.0 WHEN directed by the ORAD THEN disarm the EOF Halon System 4.1 Obtain the key to the FIKE Fire Suppression System control panel from the EOF key locker.

4.2 Open the upper compartment of the FIKE control panel located on the west wall of the EOF next to the key locker.

4.3 Toggle the module switch (the switch is located in the lower left corner of the panel.) from the "Armed" position to the "S1" position.

4.4 IF the ORAD does NOT direct this action THEN ask the ORAD if the action is required.

5.0 WHEN directed by the ORAD THEN place the EOF ventilation on internal recirculation.

5.1 Obtain the key to the EOF Electrical Equipment Room from the EOF key locker.

5.2 Locate the EOF HVAC damper control system switches on the East wall of the EOF Electrical Equipment Room.

5.3 Rotate all three (3) damper control knobs CLOCKWISE to close the dampers.

5.4 Place the three (3) AC Unit control switches to the "OVERRIDE" (up) position 5.5 Inform the ORAD and log when you have placed ventilation system in recircualtion and return key to key locker.

5.6 IF the ORAD does NOT direct this action THEN ask the ORAD if the action is required.

Page 20 of 50

Emergency Operations Facility IP-1030 Rev. 6 MIDAS Operator Sheet 3 of 4 Continuous Responsibility/Activity (con't)

Notes 6.0 Maintain the MET Data Status Board 6.1 Use procedureEP-IP-510, Meteorological, Radiological & Plant Data Acquisition System. to retrieve weather predictions.

6.2 Obtain the latest measured MET data from systems every 15 minutes.

A Update the MET Data Status Board to display the correct data.

B Notify the ORAD of any changes in the meteorological data.

6.3 Obtain weather predictions from MIDAS and/or Weather Bureau A Update the MET Data Status Board to display the correct data.

B Notify the ORAD of any significant changes in the weather forecast data 7.0 Obtain Reuter-Stokes data.

7.1 Use procedure EP-IP-510, Meteorological, Radiological & Plant Data Acquisition System to obtain Reuter-Stokes monitor data.

7.2 IF any readings indicate above background levels THEN inform the DAHP and ORAD immediately of the readings.

8.0 Assist in obtaining radiological release data and performance dose projections as directed.

8.1 Use the Plant Information Computer System (PICS) to, obtain data.

8.2 Review dose assessment data with the DAHP and ORAD Page 21 of 50

Emergency Operations Facility IP-1030 Rev. 6 MIDAS Operator Sheet 4 of 4 Closeout Responsibility/Activity 9.0 Rearm the EOF Halon System 9.1 Obtain the key to the FIKE Fire Suppression System control panel from the EOF key locker.

9.2 Open the upper compartment of the FIKE control panel located on the west wall of the EOF next to the key locker.

9.3 Toggle the module switch (the switch is located in the lower left corner of the panel.) from the "Sl" (up) position to the "Armed" (down) position.

10.0 Return the EOF ventilation to normal.

10.1 Obtain the key to the EOF Electrical Equipment Room from the EOF key locker.

10.2 Locate the EOF HVAC damper control system switches on the East wall of the EOF Electrical Equipment Room.

10.3 Rotate all three (3) damper control knobs COUNTER CLOCKWISE half way to open the dampers.

10.4 Place the three (3) AC control switches to the "NORMAL" (down) position 11.0 Return all equipment used by MIDAS Operators to it's proper storage locations.

12.0 Review all documentation the MIDAS Operator maintained during the emergency:

12.1 Ensure logs, forms and other documentation are complete 12.2 Ensure any items which need follow up investigations are identified to be completed during the Recovery Phase 13.0 Provide all logs and records to the ORAD upon termination of the emergency and entry into the Recovery Phase.

Page 22 of 50

Emergency Operations Facility Survey Team Health Physicist (STHP)

IP-1030 Rev. 6 Sheet 1 of 4 Initial Responsibility/Activity Notes 1.0 When directed by the ORAD assume the position of STHP.

1.1 Sign in on the Facility Sign In Board.

1.2 Periodically review this checklist throughout the emergency to determine which actions are appropriate for current conditions.

1.3 IF relieving another STHP THEN perform a formal turnover with the current STHP:

A. Review the current EOF survey data B. Obtain briefing form current STHP on the emergency and any actions the have been competed or are in progress.

Continuous Responsibility/Activity Notes 2.0 Confer with the ORAD or DAHP on the need to set up EOF Radiological Controls. When directed set up EOF entrance as follows:

2.1 Set up stanchions, rope barricade, and frisker in the main hall entrance to EOF work area.

2.2 Set frisker alarm to two (2) times background.

2.3 Set up Step Off Pads (SOPs) at entrance.

A IF hallway contamination levels are LESS THAN 1000 dpm/100 cm2 THEN use SOP labeled "CHECK SHOES BEFORE STEPPING HERE" B IF hallway contamination levels are GREATER THAN 1000 dpm/1 00 cm 2 THEN use SOP labeled "REMOVE PROTECTIVE CLOTHING BEFORE STEPPING HERE" AND C Place a waste receptacle and clean shoe covers near the SOP location.

2.4 Post the door in the upper level EOF near the Clerks as "Emergency Exit Only" 2.5 Check to ensure door to West stairwell (to upper EOF) is locked.

Page 23 of 50

Emergency Operations Facility IP-1030 Rev. 6 Survey Team Health Physicist (STHP)

Sheet 2 of 4 Continuous Responsibility/Activity (cont.)

Notes 3.0 Monitor Habitability of the EOF 3.1 Survey building using an Ion Chamber instrument approximately every 30 minutes. Survey times can be changed at the discretion of the ORAD.

3.2 Take Beta and Gamma readings throughout occupied areas of the EOF and hallways record readings on EOF Radiological Survey (Form IP-1030-3).

3.3 Take smears at building entrance, EOF entrance and in hallways.

Record results on EOF Radiological Survey (Form IP-1030-3) 3.4 IF any readings are found to be above background THEN inform the ORAD or DAHP immediately.

3.5 Use procedure IP-1 041, Use of Triton to Monitor for Radiogas" to set up the Triton monitor.

3.6 IF Triton monitor alarms or surveys indicate contamination THEN monitor air in the EOF A Set up air sampler near HP Work Area B IF beta survey results are greater than 50 mr/hr OR the iodine 131 activity on a charcoal filter cartridge is greater than 10 -8 uCi/cc THEN use silver zeolite filter cartridge.

C Set up MS-2/SPA-3 Counter in the lower level of the EOF by the HP area.

D Determine airborne air activity using procedure IP-1 020, Airborne Activity Determination. Record results EOF Radiological Survey (Form IP-1 030-3).

4.0 IF the Security Guards do NOT bring two (2) radios THEN obtain Emergency Planning Radios 4.1 Call the Command Guard House and request they send the two (2)

Emergency Planning Radios to the EOF 4.2 Provide radios to Security Guards Page 24 of 50

Emergency Operations Facility IP-1 030 Rev. 6 Survey Team Health Physicist (STHP)

Sheet 3 of 4 Continuous Responsibility/Activity (con't)

Notes 5.0 Assign Dosimetry 5.1 IF the EOF Security Guards do NOT have a TLD or dosimeter THEN assign a TLD badge and dosimeter to the EOF Security Guards.

5.2 Place one (1) each TLD badge and dosimeter in the upper and lower areas of the EOF work areas to monitor EOF personnel exposures.

5.3 Ensure Field Monitoring Team members are issued TLD badges and dosimeter.

6.0 Personnel Exposure Control - ALARA 6.1 IF Entergy Emergency Personnel outside the Protected Area must receive emergency exposures THEN confer with the ORAD and EOF Manager to establish controls and limits.

A Emergency Exposures may be authorized by the Emergency Director up to 5 Rem for the event regardless of prior year-to date exposures.

B Limits will normally be set at 1 Rem and raised 1 Rem at a time up to 5 Rem.

NOTE EOF Communicator #1 shall track exposures of Field Monitoring Team members.

6.2 IF any Entergy emergency workers outside the Protected Area are receiving radiological exposures THEN record exposures on Individual Exposure Tracking Log (Form IP-1023-3) 6.3 Maintain Total Effective Dose Equivalent (TEDE) less than established emergency exposure limits.

6.4 IF any worker must receive greater than 5 Rem THEN Have the ORAD request the ED authorize these exposures using Form IP 1023-6, Emergency Exposure Authorization.

Page 25 of 50 7.0 IF directed to determine thyroid burdens THEN arrange for emergency workers to receive Whole Body counts at a onsite or offsite counting station.

Emergency Operations Facility Survey Team Health Physicist (STHP)

IP-1030 Rev. 6 Sheet 4 of 4 Continuous Responsibility/Activity (con't)

Notes 8.0 IF directed to perform onsite surveys THEN use procedure IP 1015, Radiological Surveys Outside the Protected Area.

9.0 IF directed to perform site perimeter surveys THEN use procedure IP-1 015, Radiological Surveys Outside the Protected Area..

10.0 IF directed to perform personnel contamination checks and decontamination THEN use procedure IP-1008, Personnel Radiological Check and Decontamination.

11.0 IF directed to perform vehicle contamination checks and decontamination THEN use procedure IP-1009, Radiological Check and Decontamination of Vehicles.

12.0 IF directed to check equipment leaving the site THEN use procedure IP-1 014, Radiological Check of Equipment Before it leaves the Site.

Closeout Responsibility/Activity 13.0 Review all documentation the STHPs maintained during the emergency:

13.1 Ensure logs, forms and other documentation are complete 13.2 Ensure any items which need follow up investigations are identified to be completed during the Recovery Phase 14.0 Provide all logs and records to the ORAD upon termination of the emergency and entry into the Recovery Phase.

Page 26 of 50

Emergency Operations Facility EOF Technical Advisor (TA)

Sheet 1 of 3 Initial Responsibility/Activity 1.0 Assume the position of TA.

1.1 Sign in on the Facility Sign-in Board 1.2 Review facility status boards, EDDS information and any other available sources to become familiar with current plant status.

1.3 Confer with the Emergency Director and EOF Manager on emergency status 1.4 IF relieving another TA THEN perform a formal turnover with the current TA:

A. Review the current TA activity log B. Obtain briefing form current TA on the emergency and any actions the have been competed or are in progress.

1.5 Inform the Emergency Director that you are now the TA.

IP-1030 Rev. 6 Notes Continuous Responsibility/Activity Notes 2.0 IF you are temporarily leaving the work area THEN 2.1 Inform the DAHP or ORAD you are leaving the work area.

2.2 Upon return, obtain a briefing from the DAHP or ORAD on any events which have occurred while you were away.

3.0 Maintain a Log 3.1 Use Form IP-1023-4, ERO Log Sheet to log information.

3.2 Log when you assumed the duties of Emergency Director Technical Advisor.

3.3 Log significant decisions, important details used to make decisions and any equipment operability issues.

Page 27 of 50 I

Emergency Operations Facility IP-1 030 Rev. 6 EOF Technical Advisor (TA)

Sheet 2 of 3 Continuous Responsibility/Activity (cont.)

Notes 4.0 Obtain and monitor plant data:

4.1 Monitor plant data and operations information on the EOF-TSC CCR dedicated phone line.

4.2 Monitor plant data on the Emergency Data Display System (EDDS), SAS Computer Terminal and Proteus Computer.

4.3 Advise ED on the following items:

A Any significant change in the condition of the plant B Any observable trends in plant data C Major Operator actions being undertaken D Any condition which may effect the emergency classification.

4.4 Advise the ORAD of any observed changes in plant radiological data.

4.5 IF any of the EOF plant data computer systems are not functioning THEN inform a SAS/Proteus operator of malfunctions.

5.0 Maintain Plant Status Chronology on easel pad.

5.1 Enter major information on plant status or changes to plant status obtained from CCR or TSC 5.2 WHEN easel sheet gets full THEN:

A Have Clerical Staff transcribe information onto log sheet, place sheet with TA logs.

B Have Clerical Staff hang completed easel sheet on the wall between upper and lower levels of EOF.

6.0 Assist ED in interpreting plant data 6.1 Provide technical advice on plant operating procedures 6.2 Provide technical advice on Severe Accident Management Guidelines.

Page 28 of 50

Emergency Operations Facility IP-1030 Rev. 6 EOF Technical Advisor (TA)

Sheet 3 of 3 Page 29 of 50 Continuous Responsibility/Activity (cont.)

Notes 7.0 Assist Emergency Director in conduct of briefings 7.1 Assist the ED in preparations for facility briefings.

7.2 When directed by the ED provide summary briefings of plant conditions to EOF Staff and/or offsite authorities present in the EOF.

8.0 Return all equipment to it's proper storage locations.

9.0 Review all documentation the ED Technical Advisors maintained during the emergency:

9.1 Ensure logs, forms and other documentation are complete 9.2 Ensure any items which need follow up investigations are identified to be completed during the Recovery Phase 10.0 Provide all logs and records to the EOF Manager upon termination of the emergency and entry into the Recovery Phase.

Emergency Operations Facility IP-1030 Rev. 6 EOF Communicator No. 1 Sheet 1 of 4 Initial Responsibility/Activit Notes 1.0 Assume the position of EOF Communicator No. 1.

1.1 Review facility status boards, Emergency Data Display System (EDDS) information and any other available sources to become familiar with current plant status.

1.2 Obtain briefing from the Dose Assessment HP (DAHP) or the Offsite Radiological Assessment Director (ORAD).

A. Review Field Monitoring Team data.

B. Request any additional information on current status of emergency response.

1.3 IF relieving another communicator THEN perform a formal turnover with the current EOF Communicator No. 1:

A. Review the current EOF Communicator No. 1 activity log.

B. Obtain briefing from current EOF Communicator No. 1 on the emergency and any actions the have been completed or are in progress.

1.4 Inform the ORAD and DAHP that you are now EOF Communicator No. 1.

Page 30 of 50 I

Emergency Operations Facility IP-1 030 Rev. 6 EOF Communicator No. 1 Sheet 2 of 4 Continuous Responsibility/Activity Notes 2.0 Transmit directions to the Offsite Teams Note:

Offsite Teams are designated as Unit # 2 or Unit # 3 2.1 Use the Radio or Cell Phones to communicate with teams.

2.2 Confer with the ORAD and DAHP to determine the sample points and the expected whole body exposure rates based on dose projections.

2.3 Enter selected sample point(s) and assigned team number on Form IP-1 030-5, Offsite Survey Team Data Sheet.

2.4 Contact the each team and direct them to the designated sample point providing following information:

A The expected whole body dose rates B Methods of traversing the plume to keep their exposure as low as possible, such as going around plume or traveling through low field areas.

2.5 Have teams verify instructions by repeating them back.

3.0 Receive and Record Field Monitoring Team Data 3.1 Have teams state sample point for which data is being transmitted.

3.2 Record survey data on Form IP-1 030-5, Offsite Survey Team Data Sheet.

3.3 Verify numbers by repeating values back to Team 3.4 Inform the ORAD or DAHP immediately of survey and sample results Page 31 of 50

Emergency Operations Facility IP-1030 Rev. 6 EOF Communicator No. 1 Sheet 3 of 4 Continuous Responsibil ity/Activitv (con't)

Notes 4.0 Receive and Record Field Monitoring Team Data 4.1 Have teams state sample locations for which data is being transmitted.

4.2 Record survey data on Form 1030-5, Offsite Survey Team Data Sheet.

4.3 Verify numbers by repeating values back to each team.

4.4 Inform the ORAD or DAHP immediately of survey and sample results.

5.0 Maintain Field Monitoring Team Exposure Records.

5.1 IF any exposure rates are above background THEN obtain team member whole body exposure (dosimetry readings) each time they radio or call in.

5.2 IF any team members are receiving radiological exposures THEN record exposures on Individual Exposure Tracking Log (Form IP 1023-3) 6.0 Keep Field Monitoring Teams informed of major changes in emergency status:

6.1 Changes in emergency classification.

6.2 Start or stop of any offsite releases of radioactive materials.

7.0 Obtain new sample locations and points from ORAD Repeat above steps to continue plume tracking until ORAD determined surveys and sampling are no longer necessary.

Sheet 4 of 4 Page 32 of 50

Emergency Operations Facilit Page 33 of 50 Closeout ResPonsibility/Activity 8.0 Return all equipment to proper storage locations.

9.0 Review all documentation EOF Communicator No. ls maintained during the emergency:

9.1 Ensure logs, forms and other documentation are complete 9.2 Ensure any items which need follow up investigations are identified to be completed during the Recovery Phase 10.0 Provide all logs and records to the ORAD upon termination of the emergency and entry into the Recovery Phase.

IP-1030 ty Rev. 6 EOF Communicator No. 1

IP-1030 Rev. 6 Emergency Operations Facility EOF Communicator No. 2 Sheet 1 of 3 Initial Responsibility/Activity Notes 1.0 Assume the position of EOF Communicator No. 2.

1.1 Review facility status boards, Emergency Data Display System (EDDS) information and any other available sources to become familiar with current plant status.

1.2 Obtain briefing from the EOF Manager or the Emergency Director A. Review NYS Radiological Emergency Data Form Part I data which has been transmitted B. Request any additional information on current status of emergency response.

1.3 IF relieving another communicator THEN perform a formal turnover with the current EOF Communicator No. 2:

A. Review the current EOF Communicator No. 2 activity log.

B. Obtain briefing from current EOF Communicator No. 2 on the emergency and any actions the have been completed or are in progress.

C. Determine the time the next notification update is due to be transmitted.

1.4 Inform the EOF Manager and ED that you are now EOF Communicator No. 2.

Continuous Responsibility/Activity Notes 2.0 IF you are temporarily leaving the work area THEN 2.1 Inform the EOF Manager you are leaving the work area.

2.2 Upon return, obtain a briefing from the EOF Manager on any events which have occurred while you were away.

3.0 Maintain a Log 3.1 Use Form IP-1023-4, ERO Log Sheet to log information.

3.2 Log when you assumed the duties of EOF Communicator No.2.

3.3 Log all communications that are not already documented on Forms.

Page 34 of 50

Emergency Operations Facility IP-1030 Rev. 6 EOF Communicator No. 2 Sheet 2 of 3 Continuous Responsibility/Activity (cont.)

Notes 4.0 lorm required notifications to Offsite Authorities.

NOTES:

Start notification of any change in classification within 15 minutes of the classification change.

The MEANS Computer program may be used to print NYS Radiological Emergency Data Forms 4.1 IF the emergency classification changes(upgrade, downgrade, terminates) THEN perform the following:

A Complete or obtain from ED a NYS Radiological Emergency Data Form Part 1 (Form IP-1030-1)

B Ensure the ED has signed the NYS Radiological Emergency Data Form to indicate approval for transmittal.

C Communicate the information on the completed form(s) to the offsite authorities per instructions on Alert/SAE/GE Upgrade/Update Notification Checklist (Form IP-1002-3) 4.2 IF the emergency classification DOES NOT change THEN perform subsequent notifications as follows:

A Complete or obtain from ED a NYS Radiological Emergency Data Form (Part I) when any of the following conditions are met:

"* It has been approximately 30 minutes since the last form was transmitted.

"* The plant status has changed (Stable, improving, degrading or entry into the recovery phase)

"* There has been a change in the status of an actual or potential radiological release, B IF there is a change in radiological release data THEN include transmittal of data on NYS Radiological Emergency Data Form Part II Page 35 of 50

IP-1030 Rev. 6 Emergency Operations Facility EOF Communicator No. 2 Sheet 3 of 3 Continuous Responsibility/Activity (cont.)

Notes C Ensure the ED has signed the NYS Radiological Emergency Data Form(s) to indicate approval for transmittal.

D Communicate the information on the completed form(s) to the offsite authorities per instructions on Alert/SAE/GE Upgrade/Update Notification Checklist (Form IP-1002-3) 5.0 WHEN directed by the Emergency Director (ED) THEN obtain accountability status from the OSC Manager and/ or Unit 3 Watch Supervisor.

6.0 Industry group notifications 6.1 Notify the following:

"* American Nuclear Insurers

"* New York Public Service Commission 6.2 Notify the EOF Manager the notifications were made or not made.

Closeout Responsibility/Activity 7.0 Return all equipment to proper storage locations.

8.0 Review all documentation EOF Communicator No. 2 maintained during the emergency:

8.1 Ensure logs, forms and other documentation are complete 9.0 Provide all logs and records to the EOF Manager upon termination of the emergency and entry into the Recovery Phase.

Page 36 of 50

Emergency Operations Facility IP-1030 Rev. 6 EOF Clerical Staff Sheet 1 of 4 Initial Responsibility/Activity Notes 1.0 Assume the position of EOF Clerical.

1.1 Sign in on the Facility Sign-in Board 1.2 Obtain briefing from the EOF Manager 1.3 IF relieving another clerk THEN perform a formal turnover with the current clerk:

A. Review current emergency status B. Obtain briefing from current Clerical Staff on the emergency and any actions the have been competed or are in progress.

1.4 Inform the EOF Manager that you are now part of the EOF Clerical Staff.

Continuous Responsibility/Activity Notes 2.0 Process Plant Status Data 2.1 IF the Emergency Data Display System (EDDS) is operating THEN perform the following:

A. Obtain computer printout of Forms 42a, 42b and 42c trend data screens every 15 minutes.

B. Make and distribute copies of updated Forms 42a, 42b and 42c to representative located in the EOF.

Telecopy forms (a, b & c) to the following locations and record times sent in the Telecopy Log, Form 19:

"* State

"* County EOCs

"* NRC

"* JNC Page 37 of 50

Emergency Operations Facility IP-1 030 Rev. 6 EOF Clerical Staff Sheet 2 of 4 Continuous ResPonsibility/Activity (cont.)

Notes 2.2 IF the Emergency Data Display System (EDDS) is NOT operating THEN perform the following:

A. Inform the EOF Manager B. Receive Forms 42a, 42b and 42c via telecopier from the TSC.

C. Prepare transparencies of forms and place on projector.

D. Make and distribute copies of forms to NRC, FEMA, State and County Representatives at the EOF E. Telecopy forms (a, b & c) to the State and County EOCs, JNC and NRC and record times sent in the Telecopy Log (Form 19).

2.3 IF the Emergency Data Display System (EDDS) is NOT operating AND Forms 42a, 42b and 42c are NOT available via telecopier from the TSC THEN perform the following:

A. Inform the EOF Manager B. Receive data on Forms 42a, 42b and 42c from the EOF SAS Proteus Operator and the TSC C. Prepare transparencies of forms and place on projector.

D. Make and distribute copies of updated Forms 42a, 42b and 42c to NRC, FEMA, State and County Representatives at the EOF.

E. Telecopy forms (a, b & c) to the State and County EOCs, JNC and NRC and record times sent in the Telecopy Log (Form 19).

2.4 IF all of the following systems are NOT operating: EDDS, Telecopiers and EOF SAS Proteus Computer Terminals:

THEN A. Inform the EOF manager that equipment necessary to obtain plant data in the EOF is not operating B. Request the SAS / Proteus Operator obtain Form 42a, 42b and 42c data via phone from the TSC C. Distribute forms as specified in step 2.3 above..

Page 38 of 50

Emergency Operations Facility IP-1030 Rev. 6 EOF Clerical Staff Sheet 3 of 4 Continuous Responsibility/Activity (cont.)

Notes 3.0 Process the NYS Radiological Emergency Data Form Parts I &

II as follows:

3.1 Receive form(s) from the EOF Communicator #2, verifying that the form(s) are signed by the Emergency Director.

3.2 Telecopy form(s) to NYS, Counties, JNC and NRC 3.3 Record time of telecopy on Telecopy Log, Form 18 3.4 Make and distribute copies of form to NRC, FEMA, State and County representatives in the EOF.

3.5 Return original form to EOF Communicator #2 4.0 Process the Offsite Survey Team Data (Form IP-1030-5) as follows:

4.1 Receive form from the ORAD 4.2 Make copies of form and distribute to NRC, FEMA, State and County representatives in the EOF.

4.3 Telecopy form to NYS and County EOCs. (Ask the ORAD for the order in which to transmit forms to the counties.)

5.0 Receive and distribute telecopies from outside sources as follows:

5.1 Make copies of all documents received.

5.2 Distribute to addressee if known 5.3 For any document containing radiological data distribute copies to ORAD and NRC, FEMA, State and County representatives in the EOF.

5.4 Maintain copies of all telecopies.

Page 39 of 50

Emergency Operations Facility IP-1030 Rev. 6 EOF Clerical Staff Sheet 4 of 4 Continuous Responsibility/Activity (cont.)

Notes 6.0 Copy Chronology Easel Pad as follows:

6.1 Receive completed easel pad from ED Technical Advisor 6.2 Transcribe the information from the easel pad and give transcript to the ED Technical Advisor 6.3 Tape the easel pad to the wall between the upper and lower levels of the EOF.

7.0 Perform accountability duty for the Upper Level of the EOF as follows:

7.1 Record the names and arrival times of personnel stationed in the upper level EOF.

Closeout Responsibility/Activity 8.0 Return all equipment to proper storage locations.

9.0 Review all documentation maintained during the emergency by the clerical staff to ensure it is complete and organized.

10.0 Provide all logs and records to the EOF Manager upon termination of the emergency and entry into the Recovery Phase.

Page 40 of 50

Emergency Operations Facility IP-1 030 Rev. 6 EOF SAS / Proteus Operator Sheet 1 of 2 Initial Responsibility/Activity Notes 1.0 Assume the position of EOF SAS / Proteus Operator.

1.1 Sign in on the Facility Sign-in Board 1.2 IF the EOF has not been previously activated THEN perform the following steps:

A. Start the EDDS computers to display plant data.

1. Start computer

2. Log on to the network

3. Launch "Internet Explorer" from the windows desktop

4. From the "Favorites" menu select EDDS (Address http://epccrr/edds/!main.htm)

5. Select "Go To Trend Pages"

6. Select "Form 42A" for monitor labeled Form 42A

7. Adjust display to display entire form.

8. Return to step 1 and repeat for Forms 42B and 42C

9. Repeat steps 1-5 above for the EDDS terminal(s) located upstairs in the State and County work area.

B. Verify SAS Terminals are operational to display plant data (adjust brightness)

C. Verify Proteus Computer is operational to display plant data.

D. Ensure the Plant Integration Computer System (PICS) is operational.

E. IF the proteus computer is not properly displaying data THEN refer to IP-1 021, "Manual Update and Readout of Proteus Plant Parameter Data" Page 41 of 50

Emergency Operations Facility IP-1030 Rev. 6 EOF SAS / Proteus Operator Sheet 2 of 2 Initial Responsibility/Activity (cont.)

Notes 1.3 IF relieving another EOF SAS / Proteus Operator THEN perform a formal turnover with the current SAS / Proteus Operator:

A. Review current emergency status B. Obtain briefing from current SAS / Proteus Operator on the emergency and any actions the have been competed or are in progress.

1.4 Inform the EOF Manager that you are now the EOF SAS / Proteus Operator Continuous Responsibility/Activity Notes 2.0 IF the Emergency Data Display System (EDDS) is NOT operating THEN perform the following:

A. Inform the EOF Manager B. Contact the TSC Data Coordinator to verify the server is operating properly.

C. Attempt to call up data. Procedure IP-1 026, Emergency Data Acquisition, provides further guidance on system troubleshooting.

3.0 Continue to monitor EOF information systems and assist EOF Staff in obtaining information as needed.

Closeout Responsibility/Activity 4.0 Return all equipment to proper storage locations.

5.0 Review all documentation maintained during the emergency by the EOF SAS / Proteus Operator to ensure it is complete and organized.

6.0 Provide all logs and records to the EOF Manager upon termination of the emergency and entry into the Recovery Phase.

Page 42 of 50

Emergency Operations Facility Addendum 1 EOF Layout Sheet 1 of 2 Lower Level Work Area I

I r

MIDAS MIDAS Operator or Door ORAD Dose Assessment HP Security Post, Frisker and Monitoring Team Setup Area pV MET Data Computer Equipment EDDS Displays Conference Room / NRC Work Area Page 43 of 50 IP-1030 Rev. 6 I

Information Liaison L Emergency Director Map Table I

ED Technical Advisor EOF Manager Door A

EOF Communicator

1 S

EOF Cormnunicator

2 Door

Emergency Operations Facility IP-1030 Rev. 6 Addendum 1 EOF Layout Sheet 2 of 2 Upper Level Work Area Page 44 of 50

Emergency Operations Facility IP-1030 Rev. 6 Addendum 2 NYS Radiological Data Form (Part I) (Form IP-1030-1)

Sheet 1 of 2 New York State Radiological Emergency Data Form Part I - General Information Instructions

1.

This message being transmitted on: __

at: _0 AM VIA: A. RECS (Dam)

(Ti-)

0 PM B. Other

2.

This is..... A. NOT an Exercise B. An Exercise

3.

The Facility Providing this Information is:

A. INDIAN POINT NUMBER 2 B. INDIAN POINT NUMBER 3

4.

The Emergency A. Unusual Event C. Site Area Emergency E. Emergency F. Recovery B. Alert D. General Emergency Terminated G. Transportation Incident

5.

This Emergency Classification Declared on:

at:

0 AM (tDu)

(T-mt) 0 PM

6.

Release of A. No Release Radioactive Materials B. Release BELOW federally approved operating limits (Technical Specifications) due to the Classified Event:

El To Atmosphere El To Water C. Release ABOVE federally approved operating limits (Technical Specifications)

El To Atmosphere U To Water D. Unmonitored Release - requiring evaluation

7.

Protective Action Recommendations:

A. No need for Protective Actions outside the site boundary.

B. EVACUATE the following ERPAs:

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 C. SHELTER all remaining ERPAs.

8.

EAL Number:

Brief Event Description

9.

The Plant status is:

A. Stable C. Degrading E. Cold Shutdown B. Improving D. Hot Shutdown

10.

Reactor Shutdown:

A. Not Applicable B.

at: _AM (D..)

jTu)

OPM

11.

Wind Speed:

Meters/Second at elevation 10 meters.

12.

Wind Direction: (From)_

Degrees at elevation 10 meters.

13.

Stability Class:

A B

C D

E F G

14.

Report By:

at Telephone Number (914) 737-8929 (Communicator's Name)

Message Received by:

-[Message Ended at:

Emergency Director Review and Approval:

Part 1 Page I of I Form IP-1030- I Re, 2 Page 45 of 50

Emergency Operations Facility IP-1 030 Rev. 6 Addendum 2 NYS Radiological Data Form (Part II) (Form IP-1030-1)

Sheet 2 of 2 New York State Radiological Emergency Data Form Part II - Radiological Assessment Data This is:

A. NOT an Exercise B. An Exercise

14.

Message transmitted at:

Date:_

Time:

Location / Facility transmitted from:

16.

General release information:

A.

Event Release started Date Time:

B.

Event Release expected to end Date:

Time:

C. Event Release ended:

Date:

Time:

D. Reactor Shutdown:

N/A OR Date:

Time:

Meteorological Data As of Date: __

Time:

E.

Wind Speed meters/second At elevation:

meters F.

Wind Direction:

degrees At elevation:

meters G. Stability class (Pasquill):

A B C D E F G

17.

Atmospheric release information:

As of Date Time_

A.

Release from:

0 Ground C Elevated D.

Noble gas release rate:

Ci/sec B.

Iodine/Noble gas ratio:

E.

Iodine release rate Ci/sec (As d OR Atual)

C. Total release rate:

Ci/sec F.

Particulate release rate Ci/sec

18.

Waterborne release information:

As of Date Time_

A. Volume of release gallons C.

Radiolnuclides in release:

B.

Total concentration:

pCi/ml D. Total activity released Ci

19.

Dose calculations (based on a release duration of __

hours)

Calculation is based on (circle one):

A. Inplant measurements B.

Field Measurements C. Assumed source term Table below applies to (circle one) A. Atmospheric release B. Waterborne release DOSE DISTANCE XP/Q TEDE (Ren)

TEDE Rein)TODE (Rein)

Site Boundary 2 Miles 5 Miles 10 Miles Miles

20.

Field measurement of dose rates or surface contamination/deposition:

Mile/Sector OR Dose Rate (mR/hr) OR Mile/Degrees Location OR Sampling Point Time of Reading Contamination (pCimn 2)

Emergency Director Review and Approval:

Part I1 Page I of I Form IP-1030-1 Rev 2 Page 46 of 50

Emergency Operations Facility IP-1030 Rev. 6 Addendum 3 EOF Radiological Survey Map (Form IP-1030-3)

Sheet 1 of 1 EOF Radiological Survey Map Form IP-1030-3 Rev 0 Page 47 of 50 By:

Area / ltem:,Occupied Areas EOF / Service Center Date:

Time:

Type of Survey:

[1 Rad 0 Cont

[0 Air Meter / Serial #

Smear Counter/Serial #

Map Key:

=Dose Rate, * =Contact, P* =Beta, 0 =Smear, H =Head, C =Chest, K =Knee, FL = Floor Air Sample Results:

i Particulate:rcoal:

Air Sample Counter / Serial #

Highest mr/hour Reading:

Comments:

1---1 0C 0

0 Lower Level

Emergency Operations Facility IP-1030 Rev. 6 Addendum 4 State Campus Office Building Map Sheet 1 of 1 From the SotAh Take the NYS Thruway (1-87)

Northbound to 1-90 Eastbound (Exit 24)

After the toll booth, proceed straight on 1.90 to Exit 3 Page 48 of 50

Emergency Operations Facility IP-1030 Rev. 6 Addendum 5 Appendix B to § 302.4 The table of reportable amounts of radionuclides from CFR 40 PART 302 DESIGNATION, REPORT-ABLE QUANTITIES, AND NOTIFICATION Maintained current by Emergency Planning Department and distributed to ERO position binders where required.

The table is designated as Form IP-1 030-4, titled "APPENDIX B TO § 302.4 RADIONUCLIDES" Current Revision is 0 7 pages Page 49 of 50

Addendum 6 Offsite Survey Data Sheet (Form IP-1030-5)

Sheet 1 of 1 Page 50 of 50 Emergency Operations Facility IP-1030 Rev. 6 C:

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Text

SUBJECT:

6.0 REFERENCES

6.0 REFERENCES

6.0 REFERENCES

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